ML17335A152
| ML17335A152 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/30/1990 |
| From: | Wagner J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17335A147 | List: |
| References | |
| HXP900904JEW, NUDOCS 9808100104 | |
| Download: ML17335A152 (15) | |
Text
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 DATETO FLANT 0 NON PERMANE.'IT MINIMUiVlRETENTION YRS.
9808100%04 9808i7 PDR ADQCK 05000$ i5 H
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At HXP900904JEW Page 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 heat removal (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 became clear to the WOG that under these conditions, the RHR pump could be operating in the RHR mode taking suction from the RCS hot leg at saturated rather than subcooled conditions.
I This calculation will determine if adequate NPSH is available to operate the RHR pump under saturated conditions, which could occur as a result of a loss of RHR event at mid-loop.
Conclusion As shown on the attached graph (Attachment 1), there is adequate NPSH available for the RHR pumps to operate when they are taking suction from 0
the RCS at saturated conditions (212 F when vented to atmospheric ressure).
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 the HEP&T Section file 13.22.2.1 5.
Ingersoll-Rand curve N-315 typical for the RHR pumps at Cook Nuclear Plant (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 data sheet (Attachment 3).
The data sheet was generated from the drawings listed below:
1-5421 1-5415 1-RH-29 1-RH-28 1-SI-4 1-SI-2
HXP900904JEU Page 3 of 3 Net positive suction head (NPSH) formula taken from Cameron Hydraulic Data, 16th edition Pg 1-10 For positive (flooded) suction NPSH h
- h
+ h
- h a
vpa st fs where:
h - absolute pressure (in feet) on surface of the aliquid supply level h
vapor pressure of the liquid at the vpa temperature being pumped (in feet) h static height (in feet) that liquid supply st level is above or below the pump centerline h
all suction line losses (in feet) fs Calculation Net Positive Suction Head available NPSH h
- h
+ h
- h a
a vpa st fs where:
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 edition Marks, Table 28, page 4-38) h 614
- 575 39 feet st half loop elevation - 614 feet pump centerline - 575 feet hf 6.93 feet with fluid flow of 3000 gpm (ref. Attachment 2) fs NPSH - 33.96
- 33.96 + 39
- 6.93 32.07 feet Similarly NPSH was calculated for the following flows:
a Flow m
NPSHa feet 3000 3500 4000 4500 5000 32.07 29.62 26.83 23.65 20.1
Residual Heat Removal Pump 500 450 400 350 300 250 200 150 Total head (ft)
HPSH 100 90 80 70 60 50 40 30 100 50 0
-"20 10 0
500 1000 1500 2000 2500 3000 3500 4000 4500 5000 GALLON PER MINUTE PUMP CURVE ~ NPSHr ~ NPSIIa(212 F)
Pf4 io/D.G/qo
4
. PIPE FRICTION a:rhrnpsh CALC INPUT FILE XS-a:rhrnpsha R
~~me~
c
. d gyp/ oop o 9~F u INPUT DATA FOR THE HFLC5 SYS.
RES.
CALC.
C NSISTS OF THE FOLLOWING DATA:
T TEMPERTURE DEG F E PXPE ABSOLUTE ROUGHNESS (FT.)
N FXRST PIPE SEGMENT NUMBER N1 LAST PIPE SEGMENT NUMBER QDES DESIGN FLOW THRU PIPE SEGMENT (GPM)
QMIN MINIMUM FLOW THRU PIPE SEGMENT (GPM)
QMAX MAXIMUM FLOW THRU PIPE SEGMENT (GPM)
QDELT FLOW INCREMENT THRU PIPE SEGMENT (GPM)
D PIPE SEGMENT INTERNAL DXA. (XN.)
L PIPE SEGMENT LENGTH (FT.)
K PIPE SEGMENT K FACTORS L/D PIPE SEGMENT L/D FACTORS FOLLOWING IS YOUR INPUT DATA T
E N
Nl 212.00
.00015 1
1 QDES QMXN 3000.00 3000.00 QMAX 5000.00 QDELT D
500.00 13.124 L
170.35 K
L/D
. 50 465. 00 FOLLOWING IS HFLC5 RESULTS ER TEMP. (F)
SITY (LBM/CUFT)
VISCOSITY(LBM/SEC/FT)
PIPE ABS ROUGHNESS(FT) 212.00 59.74
.190201E-03
.150000E-03 PIPE SEG NO FLOW-GPM 3000.0 3500.0 4000.0 4500.0 5000.0 1
VEL(FPS) 7.12 8.30 9.49 10.67 11.86 PIPE DIA(XD-IN) =
13.124 LHD(FT)
KHD(FT)
LDHD(FT) 1.64
.39 4.90 2.22
.54
- 6. 63 2.88
.70 8.59 3.63
.89 10.84 4.47 1.09 13.34 TOT HD (FT) 6.93 9.38 12.17 15.35 18.90 REYNOLDS NUMBER FRICTION FACTOR TABLE PIPE SEG DES.
FLOW RE.NO.
F-FACTOR 1
3000.0 2444029.0
.0134 HEAD LOSS 6.93
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OG-90-44 August 2, 1990 To: Westinghouse Owners Group Primary Representatives Operations Subcommittee Representatives Analysis Subcommittee Representatives
Subject:
Westinghouse Owners Group RHR Pum NPSM At Saturated Conditions This letter is to notify all WOG utilities of a concern associated with peration 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 net positive suction head (NPSH) for the RHR pump is calculated based on subcooled conditions 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 above this temperature, the RCS will be pressurized to approximately 400 psig to ensure proper RCP operating conditions and NPSH for the RHR pump is not a
concern.
Over the past several
- years, a significant amount of effort has been expended by the utilities and Westinghouse to address NRC Generic Letters 87-12, "Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) is Partially Filled" and 88-17, "Loss of Decay Heat Removal".
In responding to the generic letters, it has become clear that under these conditions the RHR pump could be operating in the RHR mode taking suction from the RCS hot leg at saturated rather than subcooled conditions.
In addition, the Westinghouse Owners Group has recently issued the Abnormal
Response
Guideline, ARG-1, "Loss of Residual Heat Removal While Operating at Mid-Loop Conditions", which directs the operator to run the RHR pump at saturated conditions if the RCS has heated up as a result of losing RHR while at mid-loop.
1248G
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A preliminary investigation of this situation indicates that for some plants adequate NPSH may not be available at saturated 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 the results of this preliminary review, each plant should perform an evaluation to determine if adequate NPSH is available -to operate the RHR pump under saturated conditions in the
Should you have any questions concerning the above information, please contact Russ Oft at Westinghouse, 412-374-4465 or myself, 603-474-9574, X3347.
Very truly yours,
+EpM L.A. Walsh, Chairman Operations Subcommittee Westinghouse Owners Group LAW/RROft cc: Steering Committee J.B.
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NED CALCULATION VERIFICATION CHECKLIST Calculation I.D. No.:
Title:
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Authorized verifier:
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Calculation Preparer:
Date:
~(0/3o dr Date:
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4 The Authorized Verifier shall use this checklist to evaluate the calculation against the following questions.
A basis for the response to all questions (reference to a section of the calculation or other, document) shall be'oted in the "Remarks" column as well as resolution of verifier's comments.
3.
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