NEF-6.4A (5/89) CALCULATION ANALYSIS Nuclear Engineering Department SECTION SHEET 1 OF 9 I. D. NO. 0 O OQ~Eld PLANT Q~ UNIT / Q SAFETY RELATED YES ~ NO SYSTEM e~ II 9 + o ah R,HR TITLE FILE LOCATION MICROFILM NO. COMPANY CALCULATED BY: CHECKED BY: APPROVED BY: ~. A/ DATE / ~ (pg, DATE Jd'ATE PROBLEM DESCRIPTION: (s DESIGN BASIS OR REFERENCES: METHOD OF VERIFICATION: REVISIONS NO. REASON FOR CHANGE PREP'D BY DATE CKD. BY DATE APVD. BY DATE SE CTION ENGINEER NED REC RD-NE LANT COPY cVj METHOD OF VERIFICATION: NEF64A.DOC C:IFORM,D-E/FF-363 o-gl 'IIo PLANT LIFETIME DATE TO FLANT 0 NON PERMANE.'IT MINIMUiVl RETENTION YRS. 9808100%04 9808i7 PDR ADQCK 05000$ i5 H PDR P %.P* iD
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NEF-6.4A(5/89)
CALCULATION ANALYSIS
Nuclear Engineering Department
SECTION SHEET 1 OF 9
I.D. NO. 0 O OQ~Eld PLANT Q~ UNIT / Q
SAFETY RELATED YES ~ NOSYSTEM e~ II 9 + o ah
R,HR
TITLE
FILE LOCATION
MICROFILM NO.
COMPANY
CALCULATED BY:
CHECKED BY:
APPROVED BY:
~. A/DATE
/ ~ (pg,DATE
Jd'ATE
PROBLEM DESCRIPTION:
(s
DESIGN BASIS OR REFERENCES:
METHOD OF VERIFICATION:
REVISIONS
NO. REASON FOR CHANGEPREP'D
BY DATECKD.BY DATE
APVD.BY DATE
SE CTION
ENGINEER
NED REC RD-NELANTCOPYcVj
METHOD OF VERIFICATION:
NEF64A.DOCC:IFORM,D-E/FF-363
o-gl 'IIo
PLANT LIFETIMEDATE TO FLANT
0 NON PERMANE.'ITMINIMUiVlRETENTION YRS.
9808100%04 9808i7PDR ADQCK 05000$ i5H PDR
P %.P* iD
fL
'
At
HXP900904JEWPage 2 of 3
RHR PUMP NPSH AT SATURATED CONDITIONS
~Pur ose
Westinghouse Owners Group (WOG) letter OG-90-44 dated August 2, 1990,identified a concern with regard to the operation of the residual heatremoval (RHR) pumps while the plant is at half loop.
The letter states that, typically, a maximum reactor coolant system (RCS)temperature of 160 F is used to calculate the available NPSH for the RHR
0
pump. While reviewing Generic Letters 87-12, "Loss of RHR while the RCS
is partially filled," and 88-17, "Loss of decay heat removal," it becameclear to the WOG that under these conditions, the RHR pump could beoperating in the RHR mode taking suction from the RCS hot leg atsaturated rather than subcooled conditions.
I
This calculation will determine if adequate NPSH is available to operatethe RHR pump under saturated conditions, which could occur as a result ofa loss of RHR event at mid-loop.
Conclusion
As shown on the attached graph (Attachment 1), there is adequate NPSHavailable for the RHR pumps to operate when they are taking suction from
0the RCS at saturated conditions (212 F when vented to atmosphericressure).P
Westinghouse Owners Group (WOG) Letter OG-90-44 dated August 2,1990, (Attachment 4)
RCS level at half-loop, 614"-0" per procedure 2-0HP-4021.002.005
3. RHR pump suction elevation 575'-0" per Drawing No. 1-5415-16
4. Hydraulic friction loss calculation program HFLC5 available in theHEP&T Section file 13.22.2.1
5. Ingersoll-Rand curve N-315 typical for the RHR pumps at Cook NuclearPlant (Attachment 5)
6. The computer print-out attached is output from the HFLC5 program(Attachment 2). The input for the program (flow, pipe length,fittings and valves) is tabulated on the attached pipe friction datasheet (Attachment 3). The data sheet was generated from thedrawings listed below:
1-54211-54151-RH-29
1-RH-281-SI-41-SI-2
HXP900904JEUPage 3 of 3
Net positive suction head (NPSH) formula taken from CameronHydraulic Data, 16th edition Pg 1-10
For positive (flooded) suctionNPSH h - h + h - h
a vpa st fswhere: h - absolute pressure (in feet) on surface of the
aliquid supply levelh vapor pressure of the liquid at thevpa
temperature being pumped ( in feet)h static height (in feet) that liquid supplystlevel is above or below the pump centerlineh all suction line losses (in feet)fs
Calculation
Net Positive Suction Head availableNPSH h - h + h - h
a a vpa st fswhere: fluid water at 212 F
0
h 14.696 psi (33.96 feet) - 1 atmosphere
h 14. 696 psi (33. 96 feet)vpa(Standard Handbook for Mechanical Engineers 7th editionMarks, Table 28, page 4-38)
To: Westinghouse Owners Group Primary RepresentativesOperations Subcommittee RepresentativesAnalysis Subcommittee Representatives
Subject: Westinghouse Owners GroupRHR Pum NPSM At Saturated Conditions
This letter is to notify all WOG utilities of a concern associated withperation of the RHR pump at mid-loop conditions that may apply at some plants.
When the plant is operating in the Residual Heat Removal (RHR) mode, the netpositive suction head (NPSH) for the RHR pump is calculated based on subcooledconditions in the Reactor Coolant System (RCS). Typically, a maximum RCS
temperature of 160 F is used to calculate the available NPSH for the RHR
pump. Since the Reactor Coolant Pump (RCP) is assumed to be operating abovethis temperature, the RCS will be pressurized to approximately 400 psig toensure proper RCP operating conditions and NPSH for the RHR pump is not aconcern.
Over the past several years, a significant amount of effort has been expended bythe utilities and Westinghouse to address NRC Generic Letters 87- 12, "Loss ofResidual Heat Removal (RHR) While the Reactor Coolant System (RCS) is PartiallyFilled" and 88-17, "Loss of Decay Heat Removal". In responding to the genericletters, it has become clear that under these conditions the RHR pump could beoperating in the RHR mode taking suction from the RCS hot leg at saturatedrather than subcooled conditions. In addition, the Westinghouse Owners Grouphas recently issued the Abnormal Response Guideline, ARG-1, "Loss of ResidualHeat Removal While Operating at Mid-Loop Conditions", which directs the operatorto run the RHR pump at saturated conditions if the RCS has heated up as a resultof losing RHR while at mid-loop.
1248G
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The available NPSH for the RHR pump will be much less at saturated RCS
conditions than subcooled conditions. A preliminary investigation of thissituation indicates that for some plants adequate NPSH may not be available atsaturated conditions in the RCS, especially at higher RHR pump flowrates. A
typical range of RHR pump flowrates is 500 gpm to 3,000 gpm. Based upon theresults of this preliminary review, each plant should perform an evaluation todetermine if adequate NPSH is available -to operate the RHR pump under saturatedconditions in the RCS, which could occur as a result of a loss of RHR event atmid-loop.
Should you have any questions concerning the above information, please contactRuss Oft at Westinghouse, 412-374-4465 or myself, 603-474-9574, X3347.
Very truly yours,
+EpML.A. Walsh, ChairmanOperations SubcommitteeWestinghouse Owners Group
LAW/RROft
cc: Steering CommitteeJ.B. George, TU ElectricC.K. HcCoy, Georgia PowerK.J. Yoytell
1248G
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NEk-6.4B" (9/50)NED CALCULATION
VERIFICATION CHECKLIST
Calculation I.D. No.:
Title: 8> H Cc ((ot'/
Authorized verifier: '.o-jI«» ~ seato1/
Calculation Preparer:
Date: ~(0/3o drDate: ~ ~ 4
The Authorized Verifier shall use this checklist to evaluate thecalculation against the following questions. A basis for theresponse to all questions (reference to a section of thecalculation or other, document) shall be'oted in the "Remarks"column as well as resolution of verifier's comments.
3.
4 ~
5.
6.
7.
8.
Are the assumption(s)reasonable?
Is the calculationdeemed acceptable?
Checked* : Remarks«
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