ML19296D875
| ML19296D875 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/15/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML17249A984 | List: |
| References | |
| TASK-03-12, TASK-3-12, TASK-RR NUDOCS 8003130392 | |
| Download: ML19296D875 (2) | |
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UNITED STATES m,,
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February 15, 1980 Docket No.
50-245 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
RE: ELECTRICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION MILLSTONE NUCLEAR POWER STATION, UNIT NO.1 Reviews of the environmental qualification of safety-related electrical equipment have been initiated under Topic III-12 of the SEP program.
The reviews are being conducted in accordance with Enclosure 1,
" Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors." The documents 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 environnent, and the completeness of the supporting documentation.
Accordingly, it is deemed necessary to increase the level of effort applied to these reviews oy tt ( SEP licensees.
The JEP licensees are asked to perform the review of their safety-related equipment against the Guidelines of Enclosure 1.
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 deficiences in cocumentation, 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 requested to attend a meeting at the NRC Headquarters in Bethesda, Maryland, at 10:00 a.m., on February 21, 1980 in Room P-ll8 cf the Phillips-Buliding.
The purpose of this meeting is to ensure full
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Mr. W. G. Counsil 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, t/
pf Mu Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Enclosures:
1.
Guidelines for Evaluating 2.
Guidelines for Identification 6
Mr. W. G. Counsil February 15, 1980 cc William H. Cuddy, Esquire Connecticut Energy Agency Day, Berry & Howard ATTN: Assistant Director Counselors at Law Research and Policy One Constitution Plaza Devel opment Hartford, Connecticut 06103 Department of Planning and Energy Policy Anthony Z. Roisman 20 Grand Street Natural Resources Defense Council Hartford, Connecticut 06106 917 15th Street, N. W.
Washington, D. C.
20005 Director, Technical Assessment Division Northeast Nuclear Energy Company Office of Radiation Programs ATTN: Superintendent (AW-459)
Millstone Plant U. S. Environmental Protection P. O. Box 128 Agency Waterford, Connecticut 06385 Crystal Mall #2 Arlington, Virginia 20460 Mr. Janes R. Himmelwright Northeast Utilities Service Company U. S. Environnental Protection P. O. Box 270 Agency Hartford, Connecticut 06101 Region I Office ATTN: EIS COORDINATOR Resident Inspector JFK Federal Building c/o U. S. NRC Boston, Massachusetts 02203 P. O. Box Drawer KK Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 First Selectman of the Town of Waterford Hall of Records 200 Boston Post Road Waterford, Connecticut 06385
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 3
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 Sorays PA Main Stean Line Break (MSLB) r ns e Co a n en+
1.
Temperature and Pressure Steam Conditions 2.
_Ra d i a t ion 3.
Subtergence 4
Chemical Sorays 4.3 Service Conditions Outside Containment 4.3.1 Areas Subject to a Severe Environment as a Result of a Hich Eneroy Line Break HELB) 4.3.2 Areas Where Fluids are Retirculated From Inside Containment to Accomplish Lona-Term Emergency Core Cooline Following a LOCA 1.
Ternerature, Pressure and Relative Humidity 2.
Radiation 3.
Sub ergence 4
Che-ical Sorays
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4.3.3 Areas Normally Mai tained at Room Conditions 5.0 Qualification Methods 5.1 Selection of Qualification Method 5.2 Qualification by Type Testino 1.
Simulated Service Conditions and Test Duration 6
2.
Test Specimen 3.
Test Secuence 4.
Test Specimen Aging 5.
Functional Testing and Failure Criteria 6.
Installation Interfaces 5.3 Qualification by a Combination of Methods (Test, Evaluation, Analysis) 6.0 Ma rgin 7.0 Acino 8.0 Documentation Appendix A - Typical Equipment / Functions Needed for Mitigac;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 9
.