ML19312D401
| ML19312D401 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/15/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Finfrock J JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-03-12, TASK-3-12, TASK-RR NUDOCS 8003240337 | |
| Download: ML19312D401 (4) | |
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f jo UNITED STATES g
NUCLEAR REGULATORY COMMISSION et a
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February 15, 1980 DocketNeo.
50-219 Mr. I. R. F i nf rock, J r.
Vice President - Generation Jersey Central Power & Light Company
-Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960
Dear Mr. Finfrock:
RE: ELECTRICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION OYSTER _ CREEK NUCLEAR GENERATING STATION, U!iIT NO.1 Reviews of the environmental qualification of safety-related electrical equipment have been initiated under Topic III-12 of the SEP progrr %
The reviews are being conducted in accordance with Enclosure 1,
'" Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors." The docucents considered in the reviews include licensee submittals on SEP Topic III-12 and supporting material including equipment qualification records.
Preliminary results of our review indicate deficiencies affecting the scope of equipment addressed, the definition of its environment, and the completeness cf the supporting documentation.
Accordingly, it is deemed necessary to increase the level of effort applied to these reviews by-the SEP licensees.
The SEP licensees are asked to perform the review of tneir safety-related equipment against the Guidelines of Encicsure *.. This program redirection will accelerate the qualification review process by assuring that the site visit by the NRC staff, which heretofore has served largely to generate questions concerning ceficiences in documentation, can instead concentrate on (1) review of discrepancies previously identified by the licensee and (2) auditing the basis for accepting the qualification of other equipment.
All SEP licensees are requestod to attend a meeting at the NRC Headquarters in Bethesda, Maryland, at 10:00 a.m., on February 21, 1980 in Room P-ll8 of the Phillips Buliding. The purpose of this meeting is to ensure full l
l l-N7 8003240
Mr. -1. R. Finfrock, Jr. -
understanding of the qualification review process. Necessary licensee submittals, site visits, and related schedules will be covered.
In order that you may begin your activity on this accelerated effort, we are providing Enclosure 2, " Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification is to be Addressed."
Sincerely, W WA Y w -*t-k A Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors -
Enclosures:
1.
Guidelines for Evaluating 2.
Guidelines for Identification e
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, February 15, 1980
' Mr. I. R. Fi nf rock, J r.
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 GPU Service Corporation ATTN: Mr. E. G. Wallace Mark L. First Licensing Manager Deputy Attorney General 260 Cherry Hill Road State of New Jersey Parsippany, New Jersey 07054 Department of Law and Public Safety Environmental Protection Section Anthony Z. Roisman 36 West State Street i
. Natural Resources Defense Council Trenton, New Jersey 08625 917 15th Street, N. W.
Washington, D. C.
20006 Joseph T. Carroll, Jr.
Plant Superintendent Oyster Creek Nuclear Generating Steven P. Russo, Esquire Station 248 Washington Street P. O. Box 388 P. O. Box 1060 Forked River, New Jersey 08731 Toms River, New Jersey 08753 Joseph W. Ferraro, Jr., Esquire Director, Technical _ Assessment Deputy Attorney General Division State of New Jersey Office of Radiation Programs 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 Town 5+6p Branch i;
401 Chambers Bridge Road U. S. Environmental Protection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS COORDINATOR i
Lacey Township 26 Federal Plaza l
P. O. Box 475 New York, New York 10007 l
Forked River, New Jersey 08731 l
Robert M. Lazo, Esq., Chairman l
Commissioner Atomic Safety and Licensing Board l
Department of Public Utilities U. S. Nuclear Regulatory Conmission State of New Jersey Washington, D. C.
20555 101 Commerce Street New3c(, 'Niv Jersey 07102 j
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- Mr. 1. R. Fi nf rock, J r. -
4-February 15, 1980 CC'
' Dr. Hugh C. Paxton, Member
~ Los Alamos Scientific Laboratory P. O. Box 1663 Los Alamos, New Mexico 87544 Dr. Paul W. Purdom, Member Director, Center for Urban Research and Environmental Studies Drexel University 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 l
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ENCLOSURE 1 GUIDELINES FOR EVALUATING ENVIRONMENTAL QUALIFICATION OF CLASS IE ELECTRICAL EQUIPMENT IN OPERATING REACTORS 1.0 Introduction 2.0 Discussion 3.0 Identification of Class IE Equipment 5
'4.0 Service Conditions 4.1 Service Condittons Inside Containment for a Loss of Coolant Accident (LOCA) 1.
Temperature and Pressure Steam Conditions 2.
Radiation 3.
Submergence 4.
Chemical Sprays 4.2 Service Conditions for a PWR Main Stean Line Break (MSLB)
Inside Containment 1.
Temperature and Pressure Steam Conditions 2.
Radiation 3.
Submergence 4.
Chemical Sprays 4.3 Service Conditions Outside Containment 4.3.1 Areas Subject to a Severe Environment as a Result of a Hioh Eneroy Line Break (HELB) 4.3.2 Areas Where Fluids are Recirculated From Inside Containment to Accomplish Long-Term Emergency Core Cooling Following a LOCA l.
Temaerature, Pressure and Relative Humidity DUPLICATE DOCUMENT l
Entire document previously
{ li entered into system under:
30 ANO No. of pages:
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0 0
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._ 2 4.3.3 Areas Normally Mai tained at Room Conditions
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5.0- Qualification Methods 5.1 Selection-of Qualification Method 5.2 Qualification by Type Testing
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' Simulated Service Conditions and Test Duration 2.
Test Specimen 3.
Test Sequence
- 4. ' Test Specimen Aging
- 5.
Functional Testing and Failure Criteria 6.
Installation-Interfaces 5.3 ~Qu'alification by a Combination of Methods (Test, Evaluation, Analysis) 6.0 Ma rgin '
7.0 Aalng
. 8.0 Documentation Appendix A
. Typical Equipment / Functions Needed for Mitigat.on of a LOCA or MSLB Accident Appendix B - Guidelines' for Evaluating Radiation Service Conditions Inside Containment for a LOCA and MSLB Accident Appendix C - Thermal and Radiation ~ Aging Degradation of Selected Materials 4
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