ML19340B359
| ML19340B359 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/03/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 8010220154 | |
| Download: ML19340B359 (13) | |
Text
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NUCLEA REG LIA OMMISSION y '. gg i g E
WASHINGTON, D. C. 20555 5
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s September 3, 1980 Docket No. 50-219 Mr.1. R. Finfrock, Jr.
Vice President - Generation Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960
Dear Mr. Finfrock:
We have completed a preliminary review of the Oyster Creek inservice testing program. We find that additional information is required to continue our review.
Enclosed are the questions and coments that need to be resolved.
Past experience with similar reviews at other plants has shown that the most efficient and effective way of resolving the remaining questions is through a meeting at the plant with the NRC reviewers, the plant operating personnel, and the responsible inservice testing engineer. A written response is not required at this time, but we request that your staff have the requested information and be prepared to discuss it at a meeting at the Oyster Creek plant.
It is our understanding that the dates of September 23 and 24,1980 are tentatively acceptable to your staff for the meeting.
The following personnel will represent the NRC at this meeting:
Walter Paulson, NRC Victor Nerses, NRC Herb Rockhold, EG&G John Fehringer, EG&G If you have any ques; ions concerning the enclosure or the proposed meeting, please contz ct Walter Paulson, 301-492-7214.
ennis M. Crutchfield, Ch f Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See page 2 8010220l Y f
o 0
Mr. 1. R. Finf rock, J r. September 3,1980 g
i cc w/ enclosure:
G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, Ns W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road i
Trenton, New Jersey 08628 g
GPU Service Corporation 4
ATTN: Mr. E. G. Wallace Consnissioner Licensing Manager New Jersey Department of Energy 260 Cherry Hill Road 101 Consnerce Street Parsippany, New Jersey 07054 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 917 15th Street, N. W.
Oyster Creek Nuclear Generating Washington, D. C.
20006 Station P. O. Box 388 Forked River, New Jersey 08731 Steven P. Russo, Esquire 248 Washington Street Resident inspector P. O. Box 1060 c/o U. S. NRC Toms River. New Jersey 08753 P. O. Box 128 Forked River, New Jersey 08731 Joseph W. Ferraro, Jr., Esquire i
Deputy Attorney General Director, Technical Assessment Div.
State of New Jersey Office of Radiation Programs Department of Law and Public Safety (AW-459) 1100 Raymond Boulevard U. S. Environmental Protection l
Newark, New Jersey 07012 Agency Crystal Mall #2 Ocean County Library Arli ngtor.
irginia 20460 Brick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS C00RDINATCP Lacey Township 26 Federal Plaza P. O. Box 475 New York, New' York 10007 Forked River, New Jersey 08731 Coasnissioner l
Department of Public Utilities State of New Jersey 101 Consnerce Street Newart, New Jersey 07102
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I-I QUESTIONS AND C0fmENTS CONCERNING THE JERSEY CENTRAL POWER AND LIGHT COMPANY COMPANY IN-5ERVICE TESTING PROGRAM FCR OYSTER CREEK (Ref:
Docket Number 50-219) 4 I
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OYSTER CREEK NUCLEAR STATION Pung Testing Program J
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How is flow rate measured for the poison punps?
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2.
How are the mechanical characteristics of the poison pumps determined and assured during the performance testing since neither vibration or bearing temperatures are measured?
3.
Provide the specific technical information that justifies pung testing intervals greater than that specified by Section XI.
4 provide the specific technical information that supports the determination that vibration is' a singularly reliable indication of l
punp mechanical condition and bearing temperature measurements are not required.
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5.
How is flow rate measured for the service water and emergency service water pumps? How are vibration measurements taken on these pumps?
6.
How is flow rate measured for the fire protection pumps? How are vibration measurements taken on these pumps?
7.
How is flow rate measured for the condensate transfer pumpsi 8.
How is flow rate measured for the Reactor Building closed tooling water pumps?
9.
How are differential pressure and flow rate measured for the Fuel Pool Cooling pumps?
10.
Is lubricant level or. pressure measured or observed for all pumps I
listed in the IST Program as required by Section XI?
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- 11. Review the safety related function of the diesel fuel oil transfer pumps to determine if. they should be included in the IST program.
- 12. What supplies cooling water to the Emergency Diesel Generators?
- 13. Are the Reactor Shutdown Cooling pumps ever utilized to mitigate the consequences of an accident or safely shutdown the plant?
Valve Testing Program A.
Isolation Condenser 1.
Review the safety related function of valves V-14-30, 31, 32, 33, 34, 35, 36 & 37 to determine if they should be categorized A.
i 2.
Specific relief m st be requested frem exercising category B passive valves V-14-2 and V-14-6.
B.
Reactor Shutdown Cooling 1
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Review the safety function of all valves listed in this system to determine if they should be categorized A.
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2.
Provide the P&ID that shows the major components and piping of j
the Reactor Shutdown cooling system for our review at the working 1
meeting.
C.
Poison System 1.
How are check valves V-19-37 and V-19-38 full stroke exercised
. quarterly?
2.
Specific relief must be requested from exercising category B passive valves V-19-35 and V-19-36.
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3.
Review the safety related functions of check valves V-19-20 and V-19-16 to determine if they should be categorized A/C. Provide the specific technical information why these valves cannot be exercised during power operation or cold shutdowns.
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4 Review the safety related function of the following valves to
- determine if they should be included in the IST program and I
categorized E.
V-19-29 (0-10)
V-19-22 (J-8) a V-19-15 (0-3)
V-19-14 (F -3 )
V-19-17 (F-2)
V-19-18 (F -2 )
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Containment Sp7av 1.
How are check valves V-21-10, 8, 4 & 2 full stroke exercised?
2.
Review the safety related function of the following valves to determine if they should be categorized A.
V-21-11 V-21-17 V-21-18 V-21-5 V-21-13 V-21-15 3.-
What is the safety related position of check valves V-21-20 &
f 19? Should these valves be categorized A/C?
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4.
Review the safety related function of the following valves to determine if they should be included in the IST program and categorized as indicated.
Category A Loca tion V '21-1
( E -9 )
V-21-3 (E-8)
,1 V-21-7 (E-7 )
V-21-9 (E-6)
Category A/E V-21-200 (B -8 )
l V-6-134 (S-7)
V-6-136 (8-9 )
i V-6-138 (C-10)
E.
Clean-uo Demineralizer i
1.
Review the safety related function of valves V-16-1, 2, 14 & 61
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to determine if they should be categorized A.
Provide the specific technical information why these valves cannot be exercised during power operation or cold shutdowns.
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2.
Review the safety related function of check valve V-16-62 to 1
determine if it should be categorized A/C. Provide the specific technical information why the reverse flow test for this valve cannot be performed during power operation or cold shutdown.
- 3. ' Review the safety related function of check valve V-16-84 to l
determine if it should be categorized A/C. What alternate methods'have been considered for testing this valve?
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Hydraulic Control Unit 1.
If valves 120, 121, 122 & 123 have no safety related functions, why are they included in the IST program?
o 2.
How is check valve 138 verified shyt during the control, rod scram i
test?
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3.
What is the technical specifications 4.2.A-0 frequency for the control red scram tests?
4.
How does the control rod scram test verify valve 106 exercises to 1*
j its safety related position?
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o 5.
Provice the P&ID that shows the scram discharge volume and associated piping and valves.
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6.
Review the safety related function of the following valves to determine if they should be included in the IST program and categorized as indicated.
Category C Location 108
( J-4 )
Category E F
101
( G-8 )
i 102 (F-5)
- 7. ' What is the safety related function of valve V-15-297 i
8.
Review the safety related function of check valves V-15-27 and V-15-28 to determine if they should be categorized A/C.
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Fuel Pool Cooling What is the safety related function of the fuel pool cooling 1.
sys ten?
H.
Core Soray Review the safety related function of valves V-20-32, V-20-3, 1.
V-20-33 and V-20 4 to determine if they should be categorized A.
j How are valves V-20-8, V-20-9, V-20-16, and V-20-22 full stroke 2.
exercised during power operation?
are check valves V-20-60 and V-20-61 full stroke exercised 3.
How I
ouring power operaticn?
How are valves V-20-10, V-20-II, V-20-38 and V-20-39 verified 4.
open during the quarterly exercising tests?
4 Are valves V-20-92, V-20-94, V-20-93 and V-20-95 normally open 5.
valves? Shoulo these valves be categorized A?
i How are check valves V-20-52, V-20-53, Y-20-54 and V-20-55 full
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6.
stroke exercised during power operation?
How are check valves V-20-50 and V-20-51 full stroke exercised to 7.
their safety related positions?
i Review the safety related functions of valves V-20-26 and V-20-27 8.
to determine if they should be categorized A.
4 Review the safety related functions of valves V-20-15, V-20-40, 9.
V-20-21 and V-20-41 to determine if they should be categorized How are these valves exercised during power operation without A.
4 potentially overpressurizing the adjacent low pressure piping?
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10.
R]vi;w the safety related functions of check valves NZO2-A
, B, C
& D to determine if they should be categorized A/C.
f 11.
Review the safety related functions of valves V-ll-ll8, V-11-110 and V-ll-ll4 to determine if they should be included in the IST program and categorized E.
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_ Reactor Head Coolino
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1.
Review the safety related function of valves V-31-2 and V-31-5 to detennine if they should be included in the IST program and i
categorized A and A/C respectively.
J.
1.
Review the safety related function of tne ADS valves, NR-108 A-E to determine if they should be categorized B/C.
Do these valves have a safety related function other than overpressure protection
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of the reactor vessel?
I 2.
Review the safety related function of valves V-1-106, V-1-107, i
V-1-110 and V-l-111 to determine if they should be categorized A 3.
Provide the specific technical information why valve V-1-lli cannot be full stroke exercised during power operation.
4 Review the safety related function of valv,.s V-1-7, V-1-8, V-1-9 and V-1-10 to determine if they should be categorized A.
Provide the specific technical justification for not full stroke exercising these valves during power operation.
5
, Review the safety related function of valves V-1-178, V-1-179, V-1-180 and V-1-181 to determine if they should be included in j
the IST program and categorized C.
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6.
Does valve V-1-71 have any safety related functions?
K.
Feedwa ter 1.
Review the safety related function of check valves V-2-71, V-2-72, V-2-73 and V-2-74 to determine if they should be l
categorized A.
How are these valves reverse flow tested?
L.
Condensate Transfer What is the safety related position of valves V-15-8 and V-l'5-97 1.
'.iow are these valves exercised to that position?
2.
Review the safety relatec function of valves V-II-8, V-ll-9, V-Il-10 and V-ll-ll to determine if they should be inclucec in 9
the IST program and categorized B.
M.
Service and Emergency Water 1.
Provide more detailed technical information why valves V-3-62 anc V-3-63 cannot be exerciseo to their safety related position quarterly.
2.
What'is the safety related function of valve V-3-59?
3.
Provide more detailed tecnnical information why valves V-3-87 and V-3-88 cannot be full stroke exercised during power operation.
Review the safety related function of the following valves to 4.
determine if they should be inc.luded in the IST program and
. categorized B passive.
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V-3-33 (E-5) j V 34 (F-5)
V-3-78 (A-7)
V 79 (8-7)
V-3-80 (B-9)
V-3-81 (C-9)
N.
Closed Cooling Water F
l 1.
Provide more detailed technical information why valves V-5-153 and V-5-154 cannot be full stroke exercised to their safety related position quarterly.
t 2.
Provide the specific technical information why check valve V-5-165 cannot be exercised during power operation and cold shu tdowns.
Should this valve be categorized A/C?
3.
Provide the specific technical information why valves V-5-147,
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V-5-166 and V-5-167 cannot be full stroke exercised during cold shutdowns.
Should these valves be categorized A?
s 4.
What is the safety related functon of valve V-5-136?
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P.
Fire Protection I
1.
What is the safety related function of valve V-9-28?
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2.
How are valves V-20-82, V-20-83, V-20-88 and V-20-89 full stroke
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exercised without contaminating the core spray system with fire system water?
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f 3.
Review the safety related function of the following valves to determine if they should be included in the IST progran and categorized B.
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V-9-5 (C-3) f V-9-9 (0-7)
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Rad Was te 1.
Review the safety related function of valves V-22-1, V-22-2, V-22-28 and V-22-29 to determine if they shcald be categorizea A.
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Demineralized Water Transfer l
1.
Review the safety related function of valves V-12-60 and V-12-13 to determine if they should be categorized A and A/C respectively.
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S.
Miscellaneous l
1.
Provide a list of containment isolation valves for our review at tne working meeting.
2.
Provide the P&ID's that show the drywell purge and ventilation sys tenis.
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3.
Provide the P&ID that shows the sample system.
1 4.
Provide the P&ID's that show the the diesel fuel transfer and starting air systems.
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5.
Does Oyster Creek utilize any excess flow check valves in instrument lines penetrating the drywell?
I 6.
Specific relief must be requested from the exercising requirements for each passive valve indicated in the IST program.
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