ML20041C861
| ML20041C861 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/22/1982 |
| From: | Caruso R Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML20041C862 | List: |
| References | |
| IEB-80-06, IEB-80-6, LSO5-82-02-081, LSO5-82-2-81, NUDOCS 8203020616 | |
| Download: ML20041C861 (10) | |
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Docket No. 50-29 RCaruso LS05-82-02-081 OELD
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OI&E Mr. James A. Kay q
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Dear Mr. Kay:
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SUBJECT:
I&E BULLETIN 80-06, ENGINEERED SAFETY FEATURES (ESF) RESET + m jf '
CONTROLS - YANKEE NUCLEAR POWER STATION (YANKEE-R0WE)
We have completed our review of your response to I&E Bulletin 80-06 with regard to Yankee Nuclear Power Station (Yankee-Rowe) and have determined that you satisfied our concerns. We therefore consider this item resolved. A copy of our safety evaluation is enclosed.
Si erely Ralph Caruso, Project Manager Operating Reactors Branch #5 Division of Licensing 3p,Cl
Enclosure:
Safety Evaluation
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Mr. James A. Kay February 22, 1982 -
CC Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massacnusetts 02108 U. S. Environmental Protection Agency Region I Office ATTN: Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203
-Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 w
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SAFETY EVALUATION REPORT YANKEE NUCLEAR POWER PLANT LICENSEE RESPONSE TO I&E BULLETIN 80-06, ENGINEERED SAFETY ~ FEATURES (ESF). RESET CONTROLS INTRODUCTION Instances have been reported at operating nuclear power plants where it had been found that following the reset of an ESF actuated signal, certain equipment, e.g., ventilation dampers, motors, and valves, would return to its normal mode, which could compromise the protective actions of the af-fected systems.
As a result, on March 13, 1980, the NRC issued I&E Bulletin 80-06 requesting certain actions to be taken by licensees for all PWR and BWR facilities with operating licenses,
, EVALUATION The enclosed report (SRO-291) was prepared for us by EG&G, Inc., San Ramon, California, as part of our technical assistance contractor program.
It provides their technical evaluation of the licensee's response to I&E Bulletin 80-06 in accordance with NRC-provided guida~nce.
EG&G reported the licensee's conclusion that all safety-related equipment remains in its emergency mode upon reset of the ESF actuating signals with two exceptions:
(1)
Charging pumps (2) Accumulator N2 pilot supply valves s
.s The licensee committed to complete design modifications to the control circuits of the above items.
EG&G reviewed these modifications and reported. them technically satisfactory.
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~ l The licensee reported the completion of verification tests to verify that all associated equipment is consistent with the reviewed schematics.
CONCLUSION Based on the information and documents provided by the licensee and on our review of the contractor's report, we conclude that the licensee has satis-fied the concerns of I&E Bulletin 80-06.
Therefore, we find the ESF re-set controls for the Yankee Nuclear Power Plant to be in compliance with NRC criteria.
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