ML20055D037
| ML20055D037 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/02/1990 |
| From: | Devincentis J YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYR-90-083, BYR-90-83, NUDOCS 9007030129 | |
| Download: ML20055D037 (2) | |
Text
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i YANKEEATOMICELECTRIC COMPANY
"'C",*,?s*]llg*,*l" e
580 Main Street, Bolton, Massachusetts 01740-1398 July 2, 1990 BYR 90-083 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 f
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) Letter from USNRC dated September 20, 1989, " Request For Action Related to Resolution of Unresolved Safety Issue A-47, Safety Implication of Control Systems In LWR Nuclear Power Plants. Pursuant to 10CFR50.54(f) - Generic Letter 89-19" (c) NUELG 1217, " Evaluation of Safety Implications of Control Systems in LWR Nuclear Power Plants - Technical Findings Related to USI A-47" (d) NUREG 1218, " Regulatory Analysis For Resolution of USI A-47" (e) Letter from YAEC to USNRC dated March 19, 1990
Subject:
Response to Commitment to Provide Scope and Schedule for Confirmatory Analysis by July 2, 1990
Dear Sir:
In Reference (b), the-USNRC requested that Yankee evaluate the need to-modify Yankee Nuclear Power Station's (YNPS) steam generator overfill protection'. Yankee provided its initial response in Reference (e) which concluded that additional hardware and procedural modifications were not warranted. Additionally, Yankee committed to provide the USNRC with the scope
.and schedule for a steam generator overfill protection confirmatory analysis by July 2, 1990. This submittal provides that information.
The scope of the confirmatory analysis will include:
1.
Identification of potential overfill scenarios.
Overfill scenarios will consider both normal and abnormal operating configurations. Key variables to be evaluated will include:
(a) Manual and automatic level control.
(b) Number and type of feedwater pumps operable.
(c) Various feedwater line configurations.
2.
Overf111 rate and plant response.
The steam generator overfill rate and plant response will be determined for various bounding scenarios identified in Item 1.
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,,. United States Nuclear Regulatory Commission July 2, 1990 Document Control Desk Page 2 BYR 90-083 3.
Frequency of overfill scenarios.
Yankee's PRA models will be used to evaluate the frequency of occurrence for each bounding overfill scenario.
4.
Impact on overall risk.
The contribution to overall risk will be determined.
5.
Cost / Benefit analysis.
A cost / benefit analysis will be performed for potential plant derign or procedure modifications.
3 6.
Conclusion.
Yankee will provide its detailed conclusions and, if necessary, schedule for any warranted plant or procedure modifications.
Yankee will provide the above confirmatory analysis to the USNRC on or before January 31, 1991.
We trust you will find this submittal satisfactory, however, should you desire additional information please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY I,L Bds John DeVincentis Vice President JDV/tlp/WPP44/35 Attachment ec: USh'RC Region I USNRC Resident Inspector COMMONWEALTH OF MASSACHUSETTS)
)ss WORCESTER COUNTY
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Then personally appeared before me, John DeVincentis, who, oeing duly sworn, did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of~ Yankee Atomic Electric Company and that the statements therein are true to the best of his knowledge and belief.
2ntmnal Helen D. Sammarco Notary Public My Commission Expires November 7, 1991
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