ML19351F164
| ML19351F164 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/08/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-06-04, TASK-6-4, TASK-RR LSO5-80-12-008, LSO5-80-12-8, NUDOCS 8101100048 | |
| Download: ML19351F164 (4) | |
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Docket No. 50-219 LS05-80-12-006 33 m
Mr.. I. R. Finfreck.,Jr.
9 Vice President - Jersey Central 7'
Power & Light Company fM Oyster Creek Nuclear Generating Station 82 n
.M' Post Office Box 388 Forked River. New Jersey 08731
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Dear Mr. Finfrock:
RE: OYSTER CREEK - CONTAINMENT ISOLATION SYSTEM REQUEST FOR ADDITIONAL INFORMATION The enclosed request for additional information has been prepared as part of our evaluation of the bypassing and resetting of engineered safety features, including the containment isolation system, at Oyster Creek.
Because this concern is also a part of the SEP (SEP Topic VI-4), response within 30 days is requested so that we maintain the peesent SEP review schedule.
Sincerely, Dennis M. Crutchfield Chief Operating Reactors Branch #5 Division of Licensing c oju DISTRIBUTION:
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,, a :.030 Docket No. 50-219 LS05-80-12-008 Mr. I. R. Finfrock, Jr.
Vice President - Jersey Central Power & Light Company Oyster Creek Nuclear Generating Station Post Office Box 368 Forked River, New Jersey 08731
Dear Mr. Finfrock:
RE: OYSTER CREEK - CONTAINMENT ISOLATION SYSTEM REQUEST FOR ADDITIONAL INFORMATI0d The enclosed request for additional information has been prepared as part of our evaluation of the bypassing and resetting of engineered safety features, including the containment isolation system, at Oyster Creek.
Because this concern is also a part of the SEP (SEP Topic VI '),
response within 30 days is requested so that we maintain the present SEP review schedule.
Sincerely, 7x.
DennisM.Crutchfieo,vjnief Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 1
Mr. I. R. Fi nf rock, J r.
0YSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-219 cc G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road Trenton, New Jersey 08628 i
GPU Service Corporation ATTN: Mr. E. G. Wallace Commissioner Licensing Manager New Jersey Department of Energy 260 Cherry Hill Road 101 Commerce' Street Parsippany, New Jersey 07054 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 91715th Street, N. W.
Oyster Creek Nuclear Generating Washington, D. C.
20006 Station i
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 Tons River, New Jersey 08753 P. O. Box 128 Forked River, New Jersey 08731 Joseph W. Ferraro, Jr., Esquire Deputy Attorney General Director, Technical Assessment Div.
State of New Jersey Office of Radiation Prograns Department of Law and Public Safety (AW-459) 1100 Raymond Boulevard U. S. Environmental Protection Newark, New Jersey 07012 Agency Crystal Mall #2 Ocean County Library Arlington, Virginia 20460 Brick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS COORDINATOR Lacey Township 26 Federal Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Commissioner Department of Public Utilities l
State of New Jersey 101 Commerce Street Newark, New Jersey 07102 iIr
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0YSTER CREEK REQUEST FOR ADDITIONAL INFORMATION BYPASS AND RESET OF CONTAINMENT ISOLATION AND OTilER ENGINEERED SAFETY FEATURES The following requirements are being used to evaluate the safety signals to all Engineered Safety Features (ESF) equipment which may have manual override capabilities:
Criterion 1--In keeping with the requirements of General Design Criteria 55 and 56, the overriding of one type of safety-actuation signal (e.g.,
radiation) should not cause the blocking of any other type of safety-actuation signal (e.g., pressure) for those valves that have no function besides containment isolation.
Criterion 2--Sufficient physical features (e.g., key lock switches) are to be provided to facilitate adequate administrative controls.
Criterion 3--A system level annunciation of the overriden status should be provided for every safety system impacted when any override is active (see R.G. 1.47).
Criterion 4--Diverse signals should be provided to initiate isolation of the containment ventilation system. Specifically, containment high radiation, safety injection actuation, and containment high pressure (where containment high pressure is not a portion of safety injection actuation) should automatically initiate containment ventilation isolation.
Criterion 5--The instrumentation and control systems provided to initiate the ESF should be designed and qualified as safety-grade equipment.
Criterion 6--The overriding or resetting of the ESF actuation signal should not cause any valve or damper to change position.
The following definition is given for clarity of use:
a.
Override: The signal is still present, and it is biccked in order to perform a function contrary to the signal. The term, " override," where used in this Request for Information, includes functionally equivalent techniques of signal modification (e.g., bypass).
a.
Reset: The signal has come and gone, and the circuit is being cleared in order to return it to normal condition.
Your letter of January 23, 1979 on Containment Purging during normal plant operations does not adequately respond to the NRC generic letter dated November 28, 1978.
1.
Describe the operation of your purge and vent valves, including diagrams as necessary to clarify. Describe any override of safety actuation signals (manual or automatic). Should an override bypass more than one type of actuation signal, provide a comitment to change the design to conform to Criterion 1 above.
2.
Describe the physical provisions supplied with your manual bypass (override) switches and reset switches.
If no such provisions are presently provided, describe the modifications you are going to make to meet Criterion 2 above.
3.
The NRC requires that the override of a system actuation signal be annunciated at the system level.
If an override is possible, describe the annunciation provided when an override is established.
4.
The NRC requires that, at a minimum, containment ventilation isolation (CVI) be accomplished on any of the following/ diverse conditions:
1.
Containment p-essure high 2.
Safety injection actuation 3.
Containment radiation high.
The FSAR indicates that your CVI valves do not isolate on actuation of safety injection. Describe the modifications you are going to make to meet Criterion 4 above.
5.
The NRC requires signals that initiate enrjineered safety equipment be derived from safety grade (Class 1E).
Describe the qualifications of the equipment used presently and of any new equipment, that is needed to meet Criterion 5 above.
6.
Verify that the overriding or resetting of a safety actuation signal does not cause any valve or damper to change position.
If this information was supplied as part of TMI Lessons Learned, please provide specific references.
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