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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 20, 2000 NSEE: Commonwealth Edison Company FACILITIES: LaSalle County Station, Units 1 and 2 SUBJECT: SUMMARY OF JUNE 8, 2000, MEETING WITH COMMONWEALTH EDISON COMPANY TO DISCUSS THE DESIGN OF PIPE SUPPORTS AT LASALLE COUNTY STATION, UNITS 1 AND 2 On June 8, 2000, the U. S. Nuclear Regulatory Commission (NRC) met with the Commonwealth Edison Company (ComEd) to discuss the licensee's analytical approach to the design of pipe supports at LaSalle County Station, Units 1 and 2. On April 12, 2000, the NRC held a conference call with ComEd to discuss the anchor bolt stiffness values used in pipe support calculations and to resolve the fundamental issue related to the appropriateness of modeling the structural attachments of base plates as pinned connections. The staff also requested a meeting with CoinEd to discuss the issue. By letter dated April 18, 2000, the NRC submitted a letter to CoinEd listing the specific concerns to be addressed at the meeting. At the meeting on June 8, 2000, CoinEd provided a description of the analysis it used to conclude that the pipe supports can transfer the loads from the pipes to the wall with a margin of four against ultimate structural failure. The licensee stated that its analysis bounds the population of pipe supports at LaSalle. At the conclusion of the meeting, the NRC staff requested that the licensee submit a letter describing its design approach and a discussion of how the sample of supports analyzed by ComEd are representative of all of the supports at the site. ComEd agreed to provide a letter within 30 days of the meeting. One of the issues addressed in the April 18, 2000, letter concerned the in-structure floor response values for operating basis earthquake and safe shutdown earthquake. Based on discussions with the licensee, the staff agreed to separate this issue from the June 8, 2000, meeting. A list of those attending the meeting is provided as Enclosure 1. The slides used by CoinEd during the meeting are provided in Enclosure 2. Donna M. Skay, Project Manager, ion 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.: 50-373, 50-374 Enclosures: 1. Meeting Attendees 2. Slides cc w/encls: See next page
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UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

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Page 1: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

June 20, 2000

NSEE: Commonwealth Edison Company

FACILITIES: LaSalle County Station, Units 1 and 2

SUBJECT: SUMMARY OF JUNE 8, 2000, MEETING WITH COMMONWEALTH EDISON COMPANY TO DISCUSS THE DESIGN OF PIPE SUPPORTS AT LASALLE COUNTY STATION, UNITS 1 AND 2

On June 8, 2000, the U. S. Nuclear Regulatory Commission (NRC) met with the Commonwealth Edison Company (ComEd) to discuss the licensee's analytical approach to the design of pipe supports at LaSalle County Station, Units 1 and 2.

On April 12, 2000, the NRC held a conference call with ComEd to discuss the anchor bolt stiffness values used in pipe support calculations and to resolve the fundamental issue related to the appropriateness of modeling the structural attachments of base plates as pinned connections. The staff also requested a meeting with CoinEd to discuss the issue. By letter dated April 18, 2000, the NRC submitted a letter to CoinEd listing the specific concerns to be addressed at the meeting.

At the meeting on June 8, 2000, CoinEd provided a description of the analysis it used to conclude that the pipe supports can transfer the loads from the pipes to the wall with a margin of four against ultimate structural failure. The licensee stated that its analysis bounds the population of pipe supports at LaSalle. At the conclusion of the meeting, the NRC staff requested that the licensee submit a letter describing its design approach and a discussion of how the sample of supports analyzed by ComEd are representative of all of the supports at the site. ComEd agreed to provide a letter within 30 days of the meeting. One of the issues addressed in the April 18, 2000, letter concerned the in-structure floor response values for operating basis earthquake and safe shutdown earthquake. Based on discussions with the licensee, the staff agreed to separate this issue from the June 8, 2000, meeting.

A list of those attending the meeting is provided as Enclosure 1. The slides used by CoinEd during the meeting are provided in Enclosure 2.

Donna M. Skay, Project Manager, ion 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Docket Nos.: 50-373, 50-374

Enclosures: 1. Meeting Attendees 2. Slides

cc w/encls: See next page

Page 2: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

I" June 20, 2000

LICENSEE: Commonwealth Edison Company

FACILITIES: LaSalle County Station, Units 1 and 2

SUBJECT: SUMMARY OF JUNE 8,2000, MEETING WITH COMMONWEALTH EDISON COMPANY TO DISCUSS THE DESIGN OF PIPE SUPPORTS AT LASALLE COUNTY STATION, UNITS 1 AND 2

On June 8, 2000, the U. S. Nuclear Regulatory Commission (NRC) met with the Commonwealth Edison Company (ComEd) to discuss the licensee's analytical approach to the design of pipe supports at LaSalle County Station, Units I and 2.

On April 12, 2000, the NRC held a conference call with ComEd to discuss the anchor bolt stiffness values used in pipe support calculations and to resolve the fundamental issue related to the appropriateness of modeling the structural attachments of base plates as pinned connections. The staff also requested a meeting with ComEd to discuss the issue. By letter dated April 18, 2000, the NRC submitted a letter to CoinEd listing the specific concerns to be addressed at the meeting.

At the meeting on June 8, 2000, ComEd provided a description of the analysis it used to conclude that the pipe supports can transfer the loads from the pipes to the wall with a margin of four against ultimate structural failure. The licensee stated that its analysis bounds the population of pipe supports at LaSalle. At the conclusion of the meeting, the NRC staff requested that the licensee submit a letter describing its design approach and a discussion of how the sample of supports analyzed by ComEd are representative of all of the supports at the site. ComEd agreed to provide a letter within 30 days of the meeting. One of the issues addressed in the April 18, 2000, letter concerned the in-structure floor response values for operating basis earthquake and safe shutdown earthquake. Based on discussions with the licensee, the staff agreed to separate this issue from the June 8, 2000, meeting.

A list of those attending the meeting Is provided as Enclosure 1; ".The slides used by ComEd during the meeting are provided in Enclosure 2.

IRA/

Donna M. Skay, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Docket Nos.: 50-373, 50-374

Enclosures: 1. Meeting Attendees 2. Slides

cc w/encls: See next page *See previous concurrence

OFFICE PM:PDIII/2 - LA:PDIII/2 BC:EMEB, SC:P V/2 NAME D. Skay /C. Moore* G._Imbr1014--______

DATE 06/ 1 /00 06/16/00 06/ / 5/00 ý'ý6/ 7-000 DOCUMENT NAME: G:\PDIII-2\lasalle\MTG6-8-OOSUM.WV

Page 3: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

MEETING SUMMARY DISTRIBUTION FORJUNE 8. 2000 MTG W/COMED

Distribution: PUBLIC J. Zwolinski (JAZ) S. Black (SCB) A. Mendiola PD 111-2 r/f S. Bailey (SNB) D. Skay (DMS6) OGC OPA (e-mail to OPA) ACRS T. Quay (TRQ) R. McIntyre (RPM1) E. Imbro (EXI) J. Ma (JSMI) K. Manoly (KAM) J. Gavula (JAGI) C. Moore (ACM) G. Grant, Rill B. P. Jain, (BPJ) R. Pettis (RLP4)

Page 4: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

0. Kingsley Commonwealth Edison Company

LaSalle County Station Units 1 and 2

cc:

Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603

Robert Cushing, Chief, Public Utilities Division Illinois Attorney General's Office 100 W. Randolph Street Chicago, Illinois 60601

Assistant Attomey General 100 W. Randolph St. Suite 12 Chicago, Illinois 60601

U.S. NRC-LaSalle Resident Inspectors Office 2605 N. 21st Road Marseilles, Illinois 61341-9756

Chairman LaSalle County Board 707 Etna Road Ottawa, Illinois 61350

Attorney General 500 S. Second Street Springfield, Illinois 62701

Chairman Illinois Commerce Commission 527 E. Capitol Avenue, Leland Building Springfield, Illinois 62706

Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704

Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351

Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515

Commonwealth Edison Company Site Vice President - LaSalle 2601 N. 21st Road Marseilles, Illinois 61341-9757

Mr. David Helwig Senior Vice President Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515

Mr. Gene H. Stanley Vice President - Nuclear Operations Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515

Mr. Christopher Crane Senior VP - Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515

Commonwealth Edison Company LaSalle Station Manager 2601 N. 21st Road Marseilles, Illinois 61341-9757

Page 5: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

0. Kingsley LaSaile County Station Commonwealth Edison Company -2- Units I and 2

Mr. R. M. Krich Vice President - Regulatory Services Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515

Commonwealth Edison Company Reg. Assurance Supervisor - LaSalle 2601 N. 21st Road Marseilles, Illinois 61341-9757

Ms. Pamela B. Stroebel Senior Vice President and General Counsel Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690-0767

Page 6: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

MEETING TO DISCUSS PIPE SUPPORT DESIGN

JUNE 8. 2000

AFFILIATIONNAME

Donna Skay Anthony Mendiola Gene Imbro Kamal Manoly John Ma B.P. Jain Jim Gavula T. R. Quay Rich McIntyre Robert Pettis R. M. Krich W. M. Bohlke D. Bost J. T. Conner P. C. Riccardella Javad Moslemian Ron Janowiak H. Roger Gavankar Robert Brady R. Kennedy (by phone)

NRC/NRR/DLPM NRC/NRR/DLPM NRC/NRR/DE/EMEB NRC/NRR/DE/EMEB NRC/NRR/DE/EMEB NRC/NRR/DE/EMEB NRC/Region III NRC/NRR/DIPM NRC/NRR/DIPM NRC/NRR/DIPM ComEd/Regulatory Services ComEdfEngineering CornEd/Engineering CornEd/Engineering Structural Integrity Associates Sargent & Lundy ComEd/Engineering ComEd/Engineering ComEd/Regulatory Services

ENCLOSURE 1

Page 7: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

ENCLOSURE 2F, "f

LaSalle County Station, Units I & 2 Presentation to the NRC

Resolution ofPipe Support Analysis Issues

June 8, 2000

CornEd.1 of 34

Page 8: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

q'%.

LaSalle County Station Analysis of Pipe Supports

o3 Introduction and Purpose C Review of Analytical Issues E Description of Additional Analyses C3 Results and Comparisons o APLAN/ADINA Comparison

El Summary

W. H. Bohlke

J. T. Conner

D. Bost

2 of 34 ConEd

Page 9: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

V

Origin of Issue

cJCornEd review of S&L calculations, questioned

the use of pinned end conditions for pipe support

baseplates (Spring 1999) .

o In response, a problem identification form(PIF)

was generated and samp ling study performed to vfsi gen meratedhodolog, and design margins verify design me, ;t0 C;P''•.

(Spring 1999) d the

SNRC review of the sampling study questioned the

adequacy of the documentation regarding the

anchor bolt stiffness values (Fall 1999)

3 of 34

Page 10: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Origin of Issue

1 CornEd provided additional information in a letter dated Dec. 21, 1999 *:- The analysis inputs used were developed and

documented in accordance with Reg. Guide 1.64 and ANSI N45.2.1 1(i.e., used "state of the art")

*:. The method for establishing stiffness values was taken directly from the IEB 79-02 ComEd response. (July 5, 1979 Letter from Cordell Reed to J.G. Keppler)

*:. ComEd considers the method for determining the stiffness values consistent with the plant licensing basis

4 of 34 Cd

Page 11: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Origin of Issue

J NRC issued RAI's in February and April 2000 o CornEd provided an additional response in March

of 2000 iJ This meeting provides the results of additional

analyses to facilitate issue resolution

5 of 34A PIdi

Page 12: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

44j.

ComEd Review Efforts in 1999

1 LaSalle Pipe Support Licensing Design Basis *:. Uses various boundary conditions which have been

selected by the designer based on the support details (Fixed-ends or Pinned-ends)

: Uses secant modulus at design ultimate for anchor bolt stiffness as required by the methodology established in IEB 79-02 commitments

6 of 34 d

Page 13: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

ComEd Review Efforts in 1999

o Independent reviews of the design basis and sampling study results were performed by Dr. du Bouchet, Dr. Kennedy, Stone & Webster Engg. Corp, Raytheon Engineers, and Harstead & Assoc.

o The CoinEd conclusions were: •:- Modeling techniques are appropriate and conservative

"* Sample Study "* Boundary Conditions

•:. The overall support designs have adequate margins. * Steel and anchor design

7 of 34 d

Page 14: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

"I1

Problem Statement

o Demonstrate that the use of the secant modulus at design ultimate for anchor bolt stiffness is appropriate for LaSalle pipe support design

8 of 34CoI

Page 15: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

CornEd Conclusions

c Use of the secant modulus at design ultimate for anchor bolt stiffness values ensures a safety factor of 4

C()flS* ? I ll"Ot 'l tV'l te I

9 of 34 C~~

Page 16: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Basis for Conclusions

J Given a support with Concrete Expansion Anchors (CEA's) at maximum design load, the support loads can be increased by a factor of 4 before the CEA ultimate capacity is reached.

o This was demonstrated in the 1979 ComEd submittal for IEB 79-02.

o New analyses have revalidated this finding for two highly stressed supports selected by the NRC.

10 of 34 COITEc

Page 17: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

FEM Beam Elements First Support (M09 RH04-2883S)

11 of 34I

0

"OC=Ed

Page 18: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Anchor Plate Modeling Details First Support

Y

12.25 in.

15mn. i.i

H H 1.5 in. 1.5 in.

W8x31 Anchor Plate

1.62 in.L

1.63 in._

,U1.75 in. Y

z-=j)x

1.5 in. ,,

IW6x25 Arnchor Pint~

1.5 inTL

1.5

12 of 34

Page 19: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

FEM Beam Elements Second Support (M09 LP28-2804X)

- �

13 of 34 ComEd

Page 20: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Anchor Plate Modeling Details Second Support

1.5 Inches n•

W4x13 Anchor Plate (3/4 in. Din Bolts)

1.5 Inches

6.0 Inches

Inches

Inches

Inches

Inches1.5 Inches Embedment Plate 1.5 Inches (3/4 in. Din Bolts)

15 Inches

1.5 Inches

W8x31 Anchor Plate

(I In. Din Bolts

-T -

y

15

1.5 Inches 12 InchesS.

z14 of 34 'CornEd

1.5

Page 21: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Finite Element Modeling Approach for Anchor Plates

. #* , ' . ' " -. •:, :�...

Concrete Surface

Node

Shear Stiffness

Anchor Plate

CornEd15 of 34

Shear

Page 22: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Basis for Conclusions

Results Using Non-Linear Stiffness

16 of 34

__First Support Second Support Design Basis Interaction Ratio 0.96 0.8

Safety Factor at Ultimate 4 5.5 Capacity

_ __ ___ __ I ____ _ I _____

Co d

Page 23: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Basis for Conclusions

* .*ed�&' *'.', '".*.--& ,N��,*-r.- ¼,-*-,....

Comparison of Secant Modulus vs. Non-Linear Results

Support 1 Support 2 Secant Modulus Anchor Bolt 12,239 lbs 20,831 lbs Load

Non-Linear Anchor Bolt Load 12,000 lbs 19,355 lbs

Ratio of Secant Modulus/Non- 1.02 1.08 Linear

The applied support load corresponds to the load at the intersection of the design ultimate secant modulus (linear) and the non-linear curve. The fact that the ratio is about 1.0 demonstrates that the margin calculations are path independent and applies to all pipe supports. (i.e., results are bounding)

17 of 34

Page 24: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Basis for Conclusions

E 79-02 Margin Guidance- Licensee Action #2 S:. "Verify that the concrete expansion anchor bolts have

the following minimum factor of safety.. .a. Four - For wedge and sleeve type anchor bolts...The Bulletin factors of safety were intended for the maximum support load including the SSE..."

ComEd's Demonstrated Margin *:. Given a support with the anchor at maximum design

load, the support loads can be increased by more than a factor of 4 before the anchor ultimate capacity is reached.

18 of 34 CarlEc t

Page 25: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Anchor Bolt Load-Displacement Curves (Showing Secant Moduli) 30000 "

- 518 Inch Bolt -3/4 Inch Bolt

- 1 Inch Bolt

0.200 0.400 0.600 0.800 1.000

Displacement (inches)

1.200 1.400 1.600 1.800

C/~

25000

m 20000 C 0

0 15000 -j

C ,.2

C

10000

5000

0 IL

0.000

19 of 34

Page 26: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

ComEd Conclusions

of 4

SThe "2-Step Bounding" method is more conservative than the 1-Step approach JTh !f !i 1i,! !

20 of 34 Co111Ed j0

Page 27: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Basis for Conclusions

2-Step vs. 1-Step Method " 1-Step Analysis of the same two pipe supports was

performed using inputs that are consistent with the previous "2-Step bounding" analysis

" The anchor bolt loads at Node 6 (first support) and Node 1 (second support) were compared

"o Results show that the "2-Step bounding" loads are greater than the 1-Step method

"J Through iteration, the 2-Step method approaches the 1Step method

21 of 34 Cd

Page 28: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

2-Step Bounding vs. 1-Step Comparison of Results

0 Comparison of maximum bolt tensions:

22 of 34

First Support Second Support M09-RH04-2883S M09-LP28-2804X

"2-step bounding" 1.825 kips 3.47 kips approach

1-step approach 1.159 kips 0.89 kips

Ratio of 2-Step/I- 1.5 3.8 Step

Page 29: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

ComEd Conclusions

/ Use of the secant modulus at design ultimate for anchor bolt stiffness values ensures a safety factor of 4

/ The "2-Step Bounding" method is more conservative than the 1-Step approach

o The analytical tools used to design baseplates provide conservative results (i.e., APLAN)

23 of 34 COIEc

Page 30: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Comparison of APLAN vs. ADINA Results for Base Plate of Pipe Support VGOJ-0024X

o Purpose - To demonstrate that the rotational stiffness corresponding to the two bending moments (102.89 kip-in and 17.72 kip-in)in calculation No. L-002379, using the APLAN code are similar to the values computed using the ADINA code

24 of 34 CornEd

Page 31: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Comparison of APLAN vs. ADINA Results for Base Plate of Pipe Support VGOI-0024X

P fL x4",15"x1x15 11

CEA -X/2

(TYP)

Dimensions and Coordinate System for the 15"x15"x3/4" CEA Plate

Cornid25 of 34

Page 32: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Comparison of APLAN vs. ADINA Results for Base Plate of Pipe Support VGO1-0024X

Results Load Case 1: Mx=102.89 kip-inch, My=-0.94 kip-inch, Fz=5.46 kips

I

Ion~

Rotational Stiffness about x axis

ADINA 80.89 kip-in/deg

APLAN 86.3 kip-in/deg

ADINA/APLAN Ratio 0.94

26 of 34

Page 33: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Comparison of APLAN vs. ADINA Results for Base Plate of Pipe Support VGOI-0024X

Results Load Case 2: Mx=1772 kip-inch, My=O.08 kip-inch, Fz=5.64 kips

Corn I

Rotational Stiffness about x axis

ADINA 47.03 kip-in/deg APLAN 48.8 kip-in/deg

ADINA/APLAN Ratio 0.96

27 of 34

4

Page 34: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

a

Comparison of APLAN vs. ADINA Results for Base Plate of Pipe Support VGOI-0024X

Observations/Conclusions o The ADINA/APLAN ratios indicate that APLAN yields similar results

o Results are correlated and demonstrate that baseplate behavior is correctly captured using APLAN

•:. Large tension causes the plate to lift off the concrete, the additional small applied moment is not of sufficient magnitude to cause the plate to bear on the concrete thus resulting in lower rotational stiffness

•:. The case with the direct tension plus a large applied moment causes the plate to bear on the concrete resulting in a larger rotational stiffness

28 of 34

Page 35: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

C

ComEd Conclusions

I I l I llll m 1, r 1 * *I

/" Use of the secant modulus at design ultimate for anchor bolt stiffness values ensures a safety factor of 4

, The "2-Step Bounding" method is more conservative than the 1-Step approach

,/The analytical tools used to design baseplates provide conservative results (i.e., APLAN)

29 of 34 ConIEd

Page 36: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

f

Additional Requests by the NRC

1 Determine the bending moment and bolt loads using a "more realistic bolt stiffness" that corresponds to operational loading

nVerify CornEd "2-Step bounding"approach is more conservative than 1-Step approach for anchor bolt loads

1 Verification of APLAN results for rotational stiffness values

30 of 34 CoiEc .f

Page 37: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Summary

r Use of the secant modulus at design ultimate has been adequately justified, and shown to ensure a support safety factor in excess of 4

•:. This restates the CornEd position established in IEB 79-02 This is demonstrated analytically by the new analysis

31 of 34 CONIEc I

Page 38: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

4)

Summary

i The "2-Step bounding" method bounds the resultsof the 1-Step method

•:o Anchor loads are greater using the "2-Step Bounding" method

• The 2-Step method upon iteration approaches the 1Step results

Corvnd I

32 of 34

IMP""

Page 39: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Summary

1 The use of APLAN for baseplate analysis is appropriate

*:o Comparision has shown that anchor bolt rotational stiffness results are consistent and conservative with the results from other public domain software (i.e., ADINA)

CornEd33 of 34

Page 40: UNITED STATES NUCLEAR REGULATORY COMMISSION … · Mr. Christopher Crane Senior VP -Nuclear Operations Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite

Summary

r The analytical methodologies employed at LaSalle County Station for the design and analysis of pipe supports and their base plates are conservative

CrndEd34 of 34