ML20005B404
| ML20005B404 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/30/1981 |
| From: | Randazza J Maine Yankee |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20005B405 | List: |
| References | |
| FMY-81-94, NUDOCS 8107080186 | |
| Download: ML20005B404 (3) | |
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W Proposed Chg No. 86 - Supplement 1 AUGUSTA A NE 6
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(207) 623-3521 O
June 30, 1981 y(5~
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FMY 81-94
/Y l3 gf United States Ntaclear Regulatory Commission p g Washington, D. C.
20555
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Attention: Office of Nuclear Reactor Regulation s4h
Reference:
(a) License No. DPR-36 (Docket No. 50-309)
M (b) Letter from MYAPC to USNRC dated 'Trch 9,1981 (FMY 81-37)
(c) Letter from USNRC to MYAPC dated April 20, 1981, Confirmatory Order (d) letter from MYAPC to USNRC dated June 3,1981 (Proposed Change No. 86) (FMY 81-86)
Subject:
Modifications to Maine Yankee Technical Specifications Concerning LWR Primary Coolant System Pressure Isolation Valve Surveillance
Dear Sir:
Pursuant to Section 50.59 of the Commission's Rules and Regulations, Maine Yankee Atomic Power Company hereby proposes the following modifications to Appendix A of the Operating ' License.
FHOPOSED CHANGE Reference is made to the Technical Specifications contained in Appendix A to Operating License No. DPR-36 issued to Maine Yankee Atomic Power Company for the Maine Yankee plant. We propose to modify current Technical Specifications as follows:
Replace pages 4.6-1 through 4.6-4 of Specification 4.6 with the attached revised pages 4.6-1 through 4.6-5.
Replace page 3.19-1 of Specification 3.19 with the attached revised pages 3.19-1 and 3.19-2.
REASON FOR CHANGE This proposed change is submitted as a supplement to R3ference (d) as a result of informal discussions with the NRC staff. This supplement includes a revision to the acceptance criteria used to determine that the ECCS check valve barriers are intact and a 7 day exception to the limiting condition for criticality in T.S. 3.19.
This supplement supercedes the proposed change submitted via Reference (d).
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MAINE YANKEE ATOMIC POWER COMPANY United States W clear Regulatory Commistion Page Two Attn: Office of Wclear Reactor Regulation June 30, 1981 The Reactor Safety Study (WASH 1400) identified an interfacing system LOCA (Event V) as a risk which warranted consideration.
In Reference (c) the EC indicated they had determined that an event V configuration existed in the Maine Yankee design.
In Reference (b) Maine Yankee committed to installing an additional low pressure safety injection check valve between the existing LPSI check valves during the 1981 refueling outage.
That change has eliminated the event V configuration from the Maine Yankee design.
In addition, in Reference (b) Maine Yankee committed to periodic surveillance of the LPSI check valves to ensure that two barriers were intact.
This commitment was included in the confirmatory order Reference (c) which requires Maine Yankee to develop and obtain approval for technical specifications relating to LPSI check valve surveillance. This proposed change is necessary to meet the requirements of the order.
SAFETY CONSIDERATIONS This change is submitted in order to fulfill Maine Yankee's commitment Reference (b) and is not considered to constitute an unreviewed safety question. This change has been reviewed by the Plant Operating Review Committee and Nuclear Safety Audit Review Committee.
FEE DETERMINATION This proposed change requires an approval that involves a single safety issue and is deemed not to involve a significant hazard consideration. For these reasons, Maine Yankee Atomic Power Company proposes this change as a Class III Amendment. A payment of $4,000.00 was submitted with Reference (d).
SCEDULE OF CHANGE In Reference (c), tne EC issued an order requiring Maine Yankee to obtain approval for this proposed change prior to returning to power following spring 1981 Cycle 6 refueling. Maine Yankee is scheduled to return to power on July 5, 1981 t is, therefore, important for the USNRC to expedite its review and e ipr, val of this proposed change in order to eliminate any unnecessary dn 1 time. The changes described in this proposed change will be incorporat " fot) 'he Maine Yankee Technical Specifications upon receipt of your app
.,v, OTER L)NSIDERATIONS Maine Yankee Technical Specification Proposed Change No. 80, affecting Specification 3.19, is currently awaiting T r,al.
Additionally, Amendment No. 56 to the Maine Yankee Technical Specifications provided temporary relief from one aspect of Specification 3.19.
The time period during which this temporary relief was applicable has passed and, therefore, there is no further need for Amendment No. 56. Since both of the above actions affect Specification 3.19, in addition to the change being requested herein, we have taken the liberty of attaching an alternative Specification 3.19 which includes the effects of all three of the aforementioned actions.
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M AINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission Page Three
-Attn: Office of Nuclear Reactor Regulation June 30, 1981 We trust this information is acceptable; however, should you required additional information, please feel free to contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY
- 0 fw J. B. Randazza Vice President Manager of Operations STATE OF MAINE
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)ss COUNTY OF KENNEBEC)
Then personally appeared before..ie, J. B. Randazza, who, being duly sworn, did state that he is a Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.
SLM ha C&
% p tary Public
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. JEANETTE HOPKINS NOTATf PU3LIC-ST Af2 CF MNNE hir COLIMid5.0.'l GPARES MAY 1,1938 I
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