ML20054J584
| ML20054J584 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/25/1982 |
| From: | Frizzle C Maine Yankee |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| TASK-1.A.1.3, TASK-1.C.1, TASK-2.D.1, TASK-2.K.3.30, TASK-2.K.3.31, TASK-3.A.1.2, TASK-3.A.2.2, TASK-3.D.3.4, TASK-TM CDF-82-107, GL-82-10, MN-82-122, NUDOCS 8206290295 | |
| Download: ML20054J584 (4) | |
Text
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June 25,1982 MN-82-122 CDF-82-107 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch #3 Mr. Robert A. Clark, Chief Refemnces:
(a) License No. DRP-36 (Docket No. 50-309)
(b) USNRC Letter to MYAPCo dated May 5,1982 (c) MYAPCo Letter to USNRC dated June 17, 1982, MN-82-ll5
Subject:
Post-TMI Requirements (Generic Letter No. 82-10)
Dear Sir:
Enclosed am responses to Refererce (b) which requested Maine Yankee to furnish the subject information pursuant to 50.54 (f).
We want you to know that we are experiencing some difficulty determining what the Commission wants or requims in the area of certain TMI action items, for example, the emergency preparedness items addressed in SECY 82-111.
The best we can do is inform you of our plans and ask you to advise us if we should change our plans.
Q 8206290295 820625 PDR ADOCK 05000309 F
M AINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission June 25, 1982 Washirr] ton, D. C.
20555 Page 2 We trust the attached information is satisfactoIy.
If you have any further questions, please contact us.
Sincerely, MAINE YANKEE ATOMIC POWER COMPANY w
y Charles D. Frizz'le Manager of Operations J3R:pjp Enclosures - Responses to Request (2 pages)
STATE OF MAINE
)
)ss COUNTY OF KENNEBEC)
Then personally appeared before me, Charles D. Frizzle, who, being duly sworn, did state that he is the Manager of Operations 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.
01/
6 Notary Public MY CoMMISSloN EXPIRES OCTOBER 27,1939
MAINE YANKEE ATOMIC POWER COMPANY ENCLOSURE TO MYAPCo LETTER TO USNRC OATED JUNE 25, 1982 - MN-82-122 I. A. l.3.1 - Limit Overtime Maine Yankee's administrative controls have been revised to limit overtime in accordance with the guidelines issued by Generic Letter No. 82-02 dated February 8,1982.
This was complete as of June 11, 1982.
I. A.l.3.2 - Minimum Shift Crew In a letter dated January 15, 1982, MN-82-04, we stated that we will not be able to fully implement this item until at least July 1, 1983. We have just received a copy of SECY 82-219 along with slides used in the Commission briefing on June 11, 1982 which describes criteria for extension requests. We will address each criteria in our justificiation for the extension which we will submit by July 16, 1982.
I.C.1 - Revise Emergency Procedures Maine Yankee's Emergency procedures will be revised and implemented by the end of the 1982 refueling outage. The committment made via letter dated January 30,1981, FMY-81-ll to perform a " Phase II" involving PRA for completeness has been abandoned due to other workloads imposed.
11.D.1.2 - RV and SV Test Programs In Generic Letter No. 81-36 dated September 29, 1981, the WC revised this TMI item to provide for the following schedule for PWRs:
Plant-specific submittals confirming adequacy of April 1, 1982 a.
safety and relief valves based on licensee preliminary review of generic test program results.
b.
Plant-specific reports for safety and relief valve July 1, 1982 qualification.
c.
Plant-specific submittals for piping and support July 1, 1982 evaluations.
d.
Plant-specific submittals for block valve July 1, 1982 qualification.
Maine Yankee submitted the preliminary evaluation in response to (a) above by letter dated March 30, 1982, MN-82-65. We plan to partially respond to items (b) through (d) above by July 1,1982.
M AINE YANKEE ATOMIC DOWER COMPANY II.D.l.3 - Block Valve Test Program See Item II.D.l.2 above.
II.K.3.30 and 31 - SB LOCA Analysis We will submit revised models for NRC approval by the end of July 1982.
We will submit plant specific analyses within one year after staff approval.
III. A.l.2 - Staf fing Levels for Emergency Situations In a letter dated April 1,1981, FMY-81-52, we responded to Generic Letter 81-10 dated February 18, 1981. We provided a description of our staffing levels and justification for differences from NRC guidelines.
It was understood at the time that these positions were acceptable to the staff. The shift complement as described in the April 1,1981 letter is now in effect except for the "two SR0" requirement which is addressed under Item I. A.1.3.2.
III. A.l.2 - Upgrade Emergency Support Facilities This item was previously addressed in our letter dated January 15, 1982, 44-82-04.
Our plans have not changed since that time.
III.A.2.2 - Meteorological Data We are unable to deteImine what the Commission's position on this subject is, or what the actual requirements are. We can, therefore, make no meaningful commitments at this time concerning measures beyond what we have in place. We will continue to follow the evolution of the Commission's requirements in this area by tracking the progress of SECY 82-111, which as recently as the March 10, 1982 revision said (pg.13) "no changes in existing meterological monitoring systems are necessary if they have historically provided Ieliable indication..."
III.D.3.4 - Control Room Habitability Our letter of JanuaIy 15,1982, MN-82-04 remains current en this subject.
We committed to automating of the control room breathing air supply by January 1,1983.
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