Surveillance Instruction SI-4.4.10.1,Revisions 8-11, 'Preservice … · 2012. 11. 30. · 9 table of contents s ect ion section section section 4.0 section 5.0 section section section

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SURVELLANC INTRUJCT ION

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PRES'P, VTCE BFASELINE INSPECTIONAIN, D I NS TRVC 1 NrP'CTIO7 T P RUC.MT7 FOR

T•ENiSSEr VALLEYAUTh ORIT"Y1VATTSER NCLAPAN

UNITS 1 A'D 2

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Chcmical EngineerInstrument N:aintcnne"S~up.- rvi so r

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TABLE OF CONTENTS

S ECT ION

SECTION

SECTION

SECTION 4.0

SECTION 5.0

SECTION

SECTION

SECTION

SECTION

SECTION

SEC3TION:

SECTIMO

6.0

7.0

8.1

9.0

13.0

AP.END. X AAPPENDIX EAPFENDIX CAFFEN;DIX u

PAGE NO.

1

2

3

INTRODUCTION

INSERVICE INSPECTION PROGIRAM,-

BASELINE AND ISI PFOCRAM EXAMINATIONS -

TVA CLASS A CO(M'ONENTS

BASELINE AND I11 PROGRAM EXAMINATIONS -

TVA CLASS B COrIPONENTS

BASELINE AND ISI PROGRAM EXAMINATIONS -

TVA CLASSES C AND D COMWONENTS

REPAIRS

SYSTEN PREPSSURE TESTS

PUMP A1,7T VAILVE TESTING

AUTHORIZED INSPECTOR

EXO.>:TNA''I ON.?9 Y!,)

AW IEPIAN .Q CQIERT,`

R-7:1 1:E 1{, C .-

Y' RA IS

TA',2LE:,.- /"D 1)R'\WINGS

CALERA.TION BLOCKSPHOTOGRAPHSNOTIFICATIONCF' 4 DI .A1-'

SI-4.4.10.1Table of ContnntsPage I of 1Revision 11

Various porticns of ,h.ie tasli:, e and iazervice progra:m; ,ill be performed"by either NU' PR CA QP. -aff p..r.onnc. or contractor: retained as required.

ontrct. preparaLi.., admi • 'i • .rat ion, and supervision will be the re-

*,ponsibility of the NUC FR CA Staff.

inspeci•nc. - u, plans and/or Quality AUsurance Programs submitted by outside*contractors shall be reviewed and approved by the NUC FR QA Staff and

Isubmitted to the plant superintendent for approval prior to use. All

specific NDE procedures used during the inspection program shall be

reviewed and approved in accordance with OKAM Fart !I, Section 6.3.

cJWheriever inspection requirements are beWng accomplished a NU, FR QA Staff%representative shall be onsite to coordinate activities. The >NUC FR QA

*Staff representative's responsibilities shall include but are net limited

to: coordinating with Health Physics Section when work is to be oceoplishcdin radiation areas, to ensure scf folding and lghting: is pro.vded asrequired, to coordin.te insulation removal in insp-ection areas and tointerfacc with Wec thift F30"n'e- in r'egrs, to cold sn.tdawn st..a.u ofthe unit. He will be the de.:in:gnned TVA r.p....ative to ensure contractcomp.lican.e, prop~er dipc>:sc. of n.eeded proced'ure c..ange:z Wc' boh TVA

ano contractor . r. .jc .:co ,-: ina.o'-dan ith approved vendor CA ugand Section 6.3, Part 11 of the LOQA.

.,,AdA WT0.. 1y , the NUC PH. CA St-,af'f re r z nt t v ...... -e ....... tl for.. ."'

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WBNP.SI-4.4. 10.1Page A of 32Revision 8

3.1.8 Control Rod Drive 11ousin_•

There are 78 control. rod housings penetrating theclosure heAds. The housings consist of a 6-inchO.D. adapter (A-182, 304SS) &nd a 4-inch O.D. body(SB-]67, Inconel).

F"•: thte pr•!•er-ice baseline, epproxiiatcly 17 CRI)hou,%Ina weldh will be ultrasonically examined(17 periph(ýral CRD housing). Two welds shallbe examined dur"ing the first. inupection interval.

319 Auiliry F ad Adepter

There are four auxiliary head adapters. The adapters

consist of (SB-166) steel, (SA-182 304SS), inconci, inconel

butter, low alloy butter and SA-533. For the preservico

baseline, 16 welds will be ultrasonically examined.

3.2 Pressurizer

3.2.1 Longitudinal and Circumferential Seasr Welds

There are five circumferential seaim welds, eachapproximately 24 feet in length, t-,talin- 120 feet,and four vertical welds, totaling appr.oximately44 feet in the shell cylinderical region. Allseam welds are accessible from the exterior surfaceeynd will be inspected from the O.D. as part of thepreservice baseline aud inservice inspection. Thlertare no circumferential or meriodional head welds.

All shell and head sections are fabricated ofSA--533, Cr. A, class 2. m neeiibdenU.steel and are clad with austenitic stainlesssteel.

3.2.2 Nozzle-to-Vessel Welds, and Nozzle Ssfe Fldc-

There are four 6-irch nozzles, oýrne 4--ijCi nozzle,and one 14-inch nozzle a:,d one 1"o-iancl i.D.r.ti.7pad which will be examined ultrasonically from the O.D.for the preservice baseline and inservice inspectioninterval. The inside radii of each of thesewill be examined at the time the nozzle-to-vesselwelds are being inspected.

W ,WBNPSI-4.4. 10.1Page 26 of 32Revision 9

4.3.1.3 Feedwater

* There are 283 class B circumferentialwelds subject to examination. Approximately

* 40 of these welds will be examinedduring the first inservice inspectioninterval, and welds duriag the4 interva]s and for the preservicebaseline.

The entire system is carbon steel.

In appendix A, .Table B lists the weldsize, number of welds, scheduledinspections, and type of examinations. Weld mapsare included in Attachment 7.TVA intends to terminate feedwaterclass B on each feedwater loop afterthe outermost containent isolationvalve (FCV.3-33, 3-47, 3-87, 3-100) folrbaseline and ISI purposes. This isconsistant with Regulatory Guide 1.26.

4.3.2 Pressure-Retainin$ Bolting

Pressure-retaining bolting larger than 1 inchin diameter shall be visually examined for thepreservice baseline and each inservice intervalic- -ecordane with !,C-2!00 and •WC-2411 ofSection X1. Ten percent of the pressure-retainingbolzino (or 2 bolts or stuis;• whhiche'.'er is greater)in each joint selected for exantination in accordancewith IWC-2100 and IWC-2411 shall be ultrasonicallyexamined for the preservice baseline and 4 inspecticnintervals.

4.3.3 Intev-raiiy-Welded Sup.,orts and Support Com!ponents

Integrally-welded supports shall be surfaceexamined for the preservice baseline and duringthe inservice inspection intervals inaccordance with IVIC-21]0 and WCr-2411.

All nonintegrally welded supports selected forexamination in accordance with IWC-2100 and IWC-2411shall be visually examined for the baseline andeach inspection interval.Unless a condition exists which should merit

a detail record of the condition, only acheckoff 5heet record will be maintained verifyingvisual inspection of supports.

-26-

TABLE A

viAtij. 1,ir hfcrri.:c hcspctina Pro ram - Clase "A" Cf•ponentn

Exazinn tion CategoryTot al S a.p1e methfte of Fre2 Tabl-r"fIe Tc•t-d Izn'e ction t iOpntit- InIsn, IVWB,-2600, Sectica XIComponent

16. Versel cladding

17. Vessel interior surfaccsand core support structures

* 18. Control rod drive housings* 19. Aumxiliary Head Adapter

B. Pressurizer

I. Circ•waferential welds

2. Longitudina1 welds

3. wedzzle-te-7es.e1 wedsand cozzle-to-vesselitnside radiused sectionis

4. Ifeater penetrations

5. Nozzle-to-safe end welds

Pressure-retainiag bolting

Vessel suprort skirt- -,aeId

Vessel cladding

6 Pat'ches

40 SG 120!mnth Month Month

2 2 2

Ceneral Surveillance

1 1 "17 216 1.6

120 ft.

44 Ft.

7

1.5 ft

1 ft.

2

78 20

6 6

16 If

23 it. 2.5 ft.

I Patch

3 ft.

1 ft.

3

B-I- I

B-N-IB-N-3

B-0B-B

3 ft.

2 ft.

2

6 7 7

2 2 2

.5 ft.

I

5

I ft.

6

1 ft

B-G-2

B-11

B-I-2

uI-4.4.10. 1

Appendix APage 3 of 9

Revisioa 8

Dr-•i-ain Numnber

,nd R -rarks

NIA

ProcedureN wr.bc r

N-VT-l

N/A N-VT-I

** Fr, O.o.& CIN-2684C *LMT-UT-2,,XevlI1 T4 2ev. 11GUI 685 an - 1

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From O.D.L0H-M-2570-A

From extcrior(IWA-5000)

From 0.0.

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Remote viewing

S0 e ATTACHMtENT 3

LMT-UT-2 Rev. ill

KrT-UT-2 Rev. II

L[r-UT-2 Rev. 11

N-VT-i

WIB-UT- 1

N -VT- I

Lfr-UT-2 Rev. A

N-VT-I

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TABLE A

Watts5 Bar Inser-v-ice Inn-ection Pro7!n- - Class "A" ConpomntsL

Total. Savrp1e ?4ftjId ofsae-pla Tcrted [~vc~ _ _

~4) ~C l~Wrc~th ~tJ~ ~krnth

Exmar-inat~ioa CaitegoryFr"~ Table

M B-2600, Section X1

peferemaceDrawing Num~ber

and Resmrks

3. Residual Leat~ re~oval -,yst--C~rcumferential and scr Ct %aelds14" SS10o" SSR." SS

2'SS

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S~fety i-njection aySttev

Circ~i-fereatial and Socket welds* c"ss

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1- 1/2" SS

21

131.5

(later)

12

(later)

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TABILE B

Watts -Car iescrvicle 1nnvtoIns)ýtolProgram - Classc "B"~- p - --

4,7 - Y r S Z,ýIp-1e lMetbld ofI•W Te!- t~ ed~ iazrtinn (Thaatity InspectedI

40 gdo 120Month Houth Mouth

Exzminatiom Cate~goryFrc;: Table

IWC-2600, 5ectieca -,I

1. esidual hcat removal v OCircumiferenitial welds18', S514" SS12" SSlo0l SS8", SS

ILoagitud:Lna1 Seami Weldc

2. Ssfety Injec'tion sy.3tern,Circu~fremtial Welds

* 61" SS3. Main Steam

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16' CS6" CS

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SI-4.4.10.1Appendix DPage I of 2Revision 11

APPENDIX D

This occm-t establihee the r..c...r. to formally notify

PiantZ MnaC ment and/or NC PH- Q Staff o•. We presence of

.....as..... decLy, wivn a the p ,rfurm.:e of nonr-dest,.ruct ,ive

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reiwedl and sig.ned by the Fiel'd Superis•"• .'

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PART I - FiUDINC'S:

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UNITED STATES

NUCLEAR REGULATORY COMMISSION? •WASHINGTON, D. C. 20555

April 25, 1980

ALL POWER REACTOR LICENSEES

Gentlemen:

SUBJECT: CLARIFICATION OF NRC REQUIREMENTS FOR EMERGENCY RESPONSEFACILITIES AT EACH SITE

Over the past several months the NRC staff has been conducting reviews ofeach licensee's proposal to upgrade their plant to cope with emergencies.The lessons learned and emergency planning review teams have identifiedareas where clarification of the NRC position is necessary. Our previousrequirements for the TSC have been modified to allow an onsite TSC in closeproximity to the control room that would not meet the habitability require-ments, provided that a backup, habitable TSC is located near the site.

It is the purpose of this letter to set forth clarification of NRR's require-ments for the three emergency response facilities defined in my September 13,1979 letter to "All Operating Nuclear Power Plants". Additional specificcriteria for these facilities is under development. The schedule for implementingthese requirements has not changed.

If you have any questions regarding this clarification, please contact theNRC Project Manager for your facility.

Sincerely,

SenectorDivision of perating ReactorsOffice of Nuclear Reactor Regulation

Enclosure:Emergency Response

Facilities

EMERGENCY RESPONSE FACILITIES

CONTROL ROM

I Not

OPERATIONALSUPPORTCENTER

comnmunications toCR, OTSC, EOF

CloseProximity

o assembly area forsupport personnel

Technical DataEmphasis - Reactor/Systems Status

* Essential Radiological DataManagement Presence* Sr. Plant Management* Sr. Plant Engineers* NRC Emergency Response Team (5 persons)Communications- Main link to EOF and NRCHabitable (CR criteria) - If TSC nothabitable, backup habitable TSC mustbe provided on or nearzsite.

Plant Security Boundary

ITE Technical DataENCY • Emphasis on Radiological Info.TIONS (meteorology)ITY Same data as sent to NRC available

Licensee Recovery Personnel* Licensee senior management (corporatelevel)

* Recovery ManagerFederal, State, Local Governments may use.NRC including Sr. NRC officialEmphasis on off-site emergency plansPress Facility (periodic pool briefings)Habitability - direct radiation and

isolable ventilation systems; HEPAfilters in new facilities

Alternate location designated

ONSITETECHNICAL

SUPPORT

CENTER

NEARSEMERGOPERAFACIL

EMERGENCY RESPONSE FACILITIES

Onsite Technical Support Center

An onsite technical support center (TSC) shall be-maintained by each operatingnuclear power plant. The TSC shall be separate from, but in very close proximityto, the control room and be within the plant security boundary. While care mustbe taken in selecting technical input available in the TSC, it appears likelythat access to additional control room data would be required during an emergency.The location of the TSC shall also be such as to facilitate occasional face-to-facecontact between key control room and TSC supervisors (management presence). Theemphasis in designing the TSC information displays should be on reactor systemsstatus. Those individuals who are knowledgeable of and responsible for engineeringand management support of reactor operations in the event of an accident willreport to the TSC (minimum size 25 persons including 5 NRC). Those persons whoare responsible for the overall management of the utility resources includingrecovery following an accident (e.g., corporate managers) should-report to theEOF (see below). Upon activation, the TSC will provide the main communicationlink between the plant and the operator's near-site Emergency Operations Facility,and the main communication link to the NRC for plant operations matters. TheTSC must be habitable to the same degree as the control room for postulatedaccidents (SRP 6.4 as revised by NUREG-0660). Where the primary, in-plant,TSC is not made habitable because of site-specific considerations, a backupTSC which does meet the habitability requirements must be provided on or nearthe site. Parameters transmitted by any nuclear data link installed to meetfuture NRC requirements should be available for display in the TSC and theEOF.

Onsite Operational Support Center (Assembly Area)

The Operational Support Center shall be the place to which the operations supportpersonnel report in an emergency situation. Communications will be provided withthe control room, OTSC and EOF.

Emergency Operations Facility (Near-Site)

The Emergency Operations Facility (EOF) will be operated by the licensee for con-tinued evaluation and coordination of licensee activities related to an emergencyhaving or potentially having environmental consequences. The EOF must have thecapability to display the same plant data and radiological information as will berequired for transmittal to the NRC. The EOF will have sufficient space toaccommodate representatives from Federal, State and local governments if desiredby those agencies, including facilities for the senior NRC representative (10)on-site. In addition, the major State and local response agencies may performdata analysis jointly with the licensee. Overall management of utility resourcesincluding recovery operations following an accident (e.g., by corporate management)shall be managed from this facility. Press facilities for about 20 people shallbe available at the Emergency Operations Facility (periodic use). Site meteorologyshould be used to the extent practical for determining the EOF location. TheEOF should be located within about one mile of the reactor. The EOF should bea substantial structure, providing significant shielding factors from directradiation and the capability to isolate ventilation systems. Filtration systems(at least HEPA filters) shall be provided in new structures. Arrangementsshall be made to activate an alternate EOF in the event that the nearsite EOFbecomes uninhabitable.

Emergency Response Facilities

Activation Occupants Back-up ifCenter Location Required? In Charge Number Skills Function Data Display Habitability Not Habitable

Existing Shift Utility - Operational Plant Control Wide AccidentControl Room Supervisor Variable & Technical Spectrum (SRP 6.4

In Plant No or with NUREG-0660)Upgraded Senior Plant NRC (1)Control Room Official

Interim Should be Yes Senior Plant Utility - Engineering & Emergency .Direct Display No Requirement Control RoomTechnical near Official Variable Senior Plant Engineering or Call-up ofSupport Control Management Support for Plant ParametersCenter (TSC) Room NRC (5) Control Room Necessary for(by 1/1/81) Assessment

Permanent TSC Must be in Yes, for Senior Plant 25 Engineering & Accident Assess- Direct Display Either TSC or Habitable TSCvery close Alert, Site Official. (5 NRC) Senior Plant ment by Opera- of plant safety backup must be near site ifproximity to Emergency Management tions Engineers; system para- isame as Control primary TSC notControl Room or General Support to meters, call-up Room Except for habitable

Emergency Control Room display of System(by I/I/81) Class during Accidents radiological Redundancy

( / parameters

Emergency Near Site Yes, for Senior Plant 10 NRC, Corporate 1. Overall Direct display Shielding Alternate EOFOperations (within Alert, Site or Corporate including Management, Management of of radiologi- against direct required awayFacility (EOF) about 1 Emergency Official Regional Radiological Utility cal and meteo- radiation & ven- from site; no

mile) or General Director, Accident Resources rological tilation isolation habitabilityEmergency 20 utility Assessment 2. Analysis parameters. capability requirementsClass including of Plant At least that for alternate

radiologi effluents met; provided to NRCcal acci- offsite moni-dent toring forassessment offsite actionand decisionsCorporate 3. Briefingmanagement, location for5 State and offsitelocal, officials and

press pools.(periodic)