ML17325B361
| ML17325B361 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/28/1989 |
| From: | Giitter J Office of Nuclear Reactor Regulation |
| To: | Alexich M AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17325B363 | List: |
| References | |
| NUDOCS 8912070372 | |
| Download: ML17325B361 (31) | |
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November 28, 1989 Docket Nos.
50-315 and 50-316 Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 8, 1989 WITH AMERICAN ELECTRIC POWER TO DISCUSS THE D.C.
COOK IN-SERVICE TESTING PROGRAM.
On November 8, 1989, the staff met with AEP to readdress relief requests that were denied in the staff's August 29,'989 safety evaluation (SE).
Meeting attendees are listed in Enclosure 1.
Slides used during the presentation (all non-proprietary) are provided as Enclosure 2.
AEP discussed those recommendations of the safety evaluation which they are planning to adopt and provided technical justification and clarification for the remaining issues in the safety evaluation.
Resolution of the SE issues is discussed in the enclosed supplemental safety evaluation (Enclosure 3).
The staff requested that AEP resubmit their modified IST program by February 16, 1990 so that an approved program can be in place by April 1, 1990.
Sincerely, Q~jISjmj sl+llvP lm
'oseph G. Giitter, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation DISTRIBUTION
'RTREE NRC
& LOCAL PDRs PD31 GRAY FILE JSNIEZEK JTHOMA JGI ITTER OGC EJORDAN ACRS(10)
JCLIFFORD BJORGENSEN, SRI BRUCE BURGESS, RIII
- See previous concurrence
<RiPD31:DRSP (A7D/PDDI1:DRSP JGI ITTER JTfKfMA 1112 /89
" 'l/Q/89 COOK IST MTG EMEB LMARSH 11/22/89 9('912070372'91128 PDR ADQCN; 05000315 p
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Docket Nos. 50-315 and 50-316 Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 8, 1989 WITH AMERICAN ELECTRIC POWER TO DISCUSS THE D.C.
COOK IN-SERVICE TESTING PROGRAM.
On November 8, 1989, the staff met with AEP to readdress relief requests that were denied in the staff's August 29, 1989 safety evaluation (SE).
Meeting attendees are listed in Enclosure 1.
Slides used during the presentation (a11 non-proprietary) are provided as Enclosure 2.
AEP discussed those recommendations of the safety evaluation which they are planning to adopt and provided technical justification and clarification for the remaining issues in the safety evaluation.
Resolution of the SE issues is discussed in the enclosed supplemental safety evaluation (Enclosure 3).
The staff requested that AEP resubmit their modified IST program by February 16, 1990 so that an approved program can be in place by April 1, 1990.
Sincerely, DISTRIBUTION NRC 8
LOCAL PDRs PD31 GRAY FILE JSNIEZEK JTHOMA JGI ITTER OGC EJORDAN ACRS(10)
JCLIFFORD John F. Stang, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation PM/ DQ.QRSP JG 75NJ 11
/89 (A)D/PD31: DRSP JTHOMA 11/
/89 EMEB LMARSH 11/g'+89 COOK IST MTG
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 28, 1989 Docket Nos.
50-315 and 50-316 Mr. Mi 1 ton P. Alexich, Vice Pres ident Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Nr. Alexich:
SUBJECT:
SUMMARY
OF l'1EETING HELD ON NOVEMBER 8, 1989 WITH AMERICAN ELECTRIC POh'ER TO DISCUSS THE D.C.
COOK IN-SERVICE TESTING PROGRAM.
On November 8, 1989, the staff met with AEP to readdress relief requests that were denied in the staff's August 29, 1989 safety evaluation (SE).
Meeting atteIIdees are listed in Enclosure 1.
Slides used during the presentation (all non-proprietary) are provided as Enclosure 2.
AEP discussed those recommendations of the safety evaluation which they are planning to adopt and provided technical justification and clarification for the remaining issues in the safety evaluation.
Resolution of the SE issues is discussed in the enclosed supplemental safety evaluation (Enclosure 3).
The staff requested that AEP resubmit their modified IST program by February 16, 1990 so that an approved program can be in place by April 1, 1990.
S incere ly, Joseph G. Giitter, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects Office of Nuclear Reactor Regulation
Mr. Milton Alexich Indiana Michigan Power Company Donald C.
Cook Nuclear Plant CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Comoission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Depar tment of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C. Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 Mr. S. Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
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ENCLOSURE I NAME Steve Brewer Edward V. Gilabert Dilip Vadodaria TITLE
- Manager, NS
& L ORGANIZATION AEPSC Piping
& Valves Nuclear.Engineer ing AEPSC
- Engineer, Tech Support AEPSC Thaddeus R. Stephens Jeff St.
Amand Production Supervising Engineer Mechanical Performance Supervisor D
C COOK D
C COOK Byron.Bradley Donna J. Moeller Tech Eng - IST Perf Eng D
C COOK NS L Nuclear Engineer AEPSC III John Huang Joseph G. Giitter Ted Sul livan MEB Project Manager Section Chief, EMEB NRR NRR/NRC NRC/NRR/EMEB
ENCLOSURE 2
SER FOR DONALD C.
COOK NUCLEAR PLANT INSERVICE TESTING (IST)
FOR PUMPS AND VALVES o
SER ISSUES NO LONGER IN CONTENTION o
APPENDIX C
OF SER
- INCLUDING GL 89-04 DISCUSSION o
ADDITIONAL TECHNICAL JUSTIFICATION FOR SER ISSUES STILL IN CONTENTION
0 ISSUES NO LONGER IN CONTENTION PP-31N AND -31S
--SPENT FUEL PIT COOLING PUMPS ISSUE DENIED RELIEF FROM THE FLOW MEASUREMENTS.
COMPLY WITH THE SER INSTALL INSTRUMENTATION TENTATIVE COMPLETION DATE JANUARY 31, 1990
ISSUES NQ LONGER IN CONTENTION W
M m
W TDAFP CHECK VALVE ISSUE o
CONDITIONALLY GRANTED RELIEF VALVE CLOSURE VERIFIED BY DISASSEMBLY IN ACCORDANCE WITH GL 89-04 NOTE:
FULL STROKE TO THE OPEN POSITION ON A COLD SHUTDOWN FREQUENCY PROGRAM NOTE REVISION
ISSUES NO LONGER IN CONTENTION ESW-109 (145),
-115 (240),
AND -243 ISSUE DENIED RELIEF REQUESTED FROM THE REQUIREMENT TO QUARTERLY EXERCISE THE VALVES TO THE OPEN POSITION
- TEST ON A COLD SHUTDOWN FREQUENCY PROGRAM NOTE REVISION
t
APPENDIX C
I)
IDENTIFY NOTES AS COLD SHUTDOWN JUSTIFICATION OR RELIEF REQUEST
- REVISION TO PROGRAM NOTES NOTE FW-134 AND FM-135 (C
LD H TD W
TIFICATIO THESE VALVES ARE LOCATED ON THE SUCTION AND DISCHARGE LINES OF THE TURBINE DRIVEN AUXILIARYFEEDPUMP.
THE MAXIMUM FLOW RATE THROUGH THE TURBINE DRIVEN AUXILIARY FEEDPUMP DURING IST IS APPROXIMATELY 700 GPM USING THE PUMP TEST LINE.
PASSING THE DESIGN FLOW OF 900 GPM THROUGH THESE VALVES WOULD REQUIRE DELIVERING COLD AUXILIARYFEEDWATER WATER TO THE STEAM GENERATORS.
THIS WOULD RESULT IN THERMAL SHOCK TO THE STEAM GENERATOR NOZZLES.
THEREFORE, THESE VALVES WILL Bf PART STROKE EXERCISED QUARTERLY AND FULL STROKE EXERCISED (PASSING DESIGN FLOW OF 900 GPM THROUGH THE VALVES) AT A COLD SHUTDOWN FREQUENCY.
APPENDIX C
2)
FAST ACTING VAL'VES
- REVISION TO PROGRAM - MAXIMUM LIMITING STROKE TIMES OF UP TO TWO SECONDS
APPENDIX C
3)
TESTING BY DISASSEMBLY-GL 89-04 PROPOSED CHANGE TO PROGRAM
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~ I OTE THE RELIEF REQUEST NOTES WZLL INDICATE WHEN AI.TERNATIVE TESTING ZS TO BE PERFORMED ON A CHECK VALVE PER GL 89 04 i ITEM 4'2, ZN LIEU OF THE STROKE TESTING REQUIRED BY SECTION XI, PARAGRAPH INf 3521.
ALTERNATIVE TESTING WILL BE ACCOMPLISHED BY DISASSEMBLY OR RADIOGRAPHY DURING REFUELING OUTAGES.
THESE METHODS ARE EXPLAINED BELOW:
(A)
DISASSEMBLY METHOD - THE VALVE BONNET WILL BE
- REMOVED, THE DISC MANUALLY FULL STROKE EXERCISED AND THE VALVE INTERNALS VISUALLY INSPECTED PER GL 89-04.
THE RESULTS OF THIS TEST WILL BE DOCUMENTED.
(B)
RADIOGRAPHY METHOD << THIS METHOD WILL BE USED AS AN ALTERNATIVE TESTZNG METHOD TO DETERMINE THE DISC POSITION UNDER NO FLOW OR REVERSE FLOW CONDITIONS (I ~ E ~ t VALVE SEATED).
THISi ZN CONJUNCTION WITH THE FULL FORWARD FLOW TESTING OF THE VALVEg CAN PROVIDE'SSURANCE THAT THE DISC ZS FREE TO MOVE FROM FULl. OPEN POSITION DURING FORWARD FLOW TO THE CLOSED POSITION WITH NO'FLOW OR REVERSE FLOW CONDITIONS.
THE RESULTS OF THIS TEST WILL BE DOCUMENTED.
J
APPENDIX C
DISCUSSED LATER 5)
FW-134 AND -135 FULL FLOW TESTING PART STROKE QUARTERLY FULL STROKE TEST ON A COLD SHUTDOWN FREQUENCY
APPENDIX C 6)
CONTAINMENT ISOLATION VALVE TESTING DOCUMENT IN THE IST PROGRAM 7), 8)
AND 9)
DISCUSSED LATER
APPENDIX C 10)
NOTE 6
FOR SI--161
- DISCREPANCY WILL BE CORRECTED 11)
RH-108E AND -108W DISCUSSED LATER
I e,
APPENDIX C 12)
XRY-221 AND -222 NO REQUIRED FAIL SAFE POSITION 13)
CRY-470 DISCUSSED LATER 14)
ESM-109 (145),
-114(240)
AND -243 DISCUSSED EARLIER M
W W
- INCLUDE RELIEF REQUEST
APPENDIX C
16)
ESW-111(141), --112 (142),
-113 (143),
AND -114(144)
NO RELIEF REQUEST REQUIRED
- ALL REQUIRED TESTS FOR SECTION XI ARE PERFORMED NOTE ON DISASSEMBLY
RESPONSE
TO IE BULLETIN 83-03 17)
SPENT FUEL PIT COOLING PUMP FLOW MEASUREMENTS DISCUSSED EARLIER
ISSUE ISSUES STILL IN CONTENTION W
W W
W FEEDWATER HEADER CHECK VALVES:
DENIED RELIEF REQUESTED FROM QUARTERLY EXERCISING TO THE CLOSED POSITION ADDITIONAL JUSTIFICATION ALTERNATE TEST METHOD - DISASSEMBLY ON REFUELING OUTAGE FREQUENCY NO POSITION INDICATORS
- NOT-POSITIVE BACKSEAT VALVES AT COLD SHUTDOWN - DISASSEMBLY COULD DELAY RETURN TO POWER
- DRAINING THE SG FEEDWATER HEADER
- MANUALLY LIFTING VALVE BONNET
- WHIP RESTRAINT DISASSEMBLY HEAVY, LARGE COMPONENT
ISSUES STILL IN CONTENTION QRV-200 AND -251 NORMAL CHARGING CONTROL VALVES ISSUE DENIED RELIEF REQUESTED FROM FAIL SAFE TESTING AND STROKE TIMING REQUIREMENTS ADDITIONAL JUSTIFICATION STROKE TIMING NO LOCAL OR REMOTE POSITION INDICATOR FAIL SAFE POSITION
- QRV-200 -
NONE REQUIRED
- QRV-251 - FAIL OPEN
- DISASSEMBLE THE AIR SUPPLY LINE
ISSUES STILL IN CONTENTION CRV-470 -
LETDOWN HEAT EXCHANGER TEMPERATURE CONTROL VALVE ISSUE DENIED RELIEF REQUESTED FROM FAIL SAFE TESTING ADDITIONAL JUSTIFICATION FAIL SAFE TEST AT POWER TO CLOSE POSITION IMPRACTICAL
- WITH LETDOWN OUT OF SERVICE PRESSURIZER LEVEL CONTROL CONCERNS
- WITH LETDOWN IN SERVICE
- HIGH TEMPERATURE, WHICH CAUSES
- FLASHING CAUSING POTENTIAL WATER HAMMER DAMAGE
- LIFTING OF THE LETDOWN LINE SAFETY VALVES FAIL SAFE TEST ON A COLD SHUTDOWN FREQUENCY
0 r
ISSUES STILL IN CONTENTION SI-189 CONTAINMENT ISOLATION CHECK VALVE DENIED RELIEF REQUESTED FROM EXERCISING VALVE TO OPEN POSITION ADDITIONAL JUSTIFICATION FULL STROKE ONLY POSSIBLE BY VALVE DISASSEMBLY FULL FLOW IS APPROXIMATELY 800 GPM
- 3/4-INCH TEST CONNECTION
-.VALVE LOCATED INSIDE CONTAINMENT PART STROKE TEST ON A COLD SHUTDOWN FREQUENCY FULL STROKE VERIFIED BY VALVE DISASSEMBLY ON A REFUELING OUTAGE FREQUENCY
ISSUES STILL IN CONTENTION RH-108E AND -108W RHR PUMP DISCHARGE LINE CHECK VALVES ISSUE DENIED REQUEST TO TEST ON A COLD SHUTDOWN FREQUENCY ADDITIONAL JUSTIFICATION FULL STROKE AT POWER OPERATION NOT DESIRABLE
- DESIGN MODIFICATION TO EXISTING INSTRUMENTATION (0-1500 GPM)
DESIGN FLOW 3000 GPM TWO-LOOP INJECTION CONFIGURATION PART STROKE QUARTERLY FULL STROKE ON A COLD SHUTDOWN FREQUENCY
ISSUES STILL IN CONTENTION REACTOR HEAD VENT VALVES PRESSURIZER VENT VALVES ISSUE DENIED RELIEF REQUESTED FROM REFUELING FREQUENCY, EXERCISING, STROKE TIMING, AND FAIL-SAFE TESTING REQUIREMENTS ADDITIONAL JUSTIFICATION PERFORM TESTING ON A COLD SHUTDOWN FREQUENCY WHEN RCS PRESSURE LESS THAN OR EQUAL TO 80 LBS