ML20028B205
| ML20028B205 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 11/24/1982 |
| From: | Garrity J Maine Yankee |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20028B206 | List: |
| References | |
| JHG-82-223, MN-82-238, NUDOCS 8211300167 | |
| Download: ML20028B205 (2) | |
Text
9 1671 WORCESTER ROAD FRA MINr; HAM, M ASSACHUSETTS 01701 gErf$7)
ENGINEERING OFFICE 617-872 8100 WJ November 24, 1982 MN-82-238 JHG-82-223 lhited States Ibclear Regulatory Commission Washington, D. C.
20555 At tention:
Mr. Harold R.
Dento n, Director Of fice of Nuclear Reactor Regulation Re f erence s :
(a) License No. DPR-36 (Docket No. 50-309)
(b) Le t te r, USNRC to MYAPC, dated May 19, 1982 (c )
letter, MYAPC to USNRC, MN-82-109, dated June 7,1982 Su bj ec t:
Fire Protection - Safe Shutdown Capability
Dear Sir:
This letter transmits Maine Yankee's design descriptions of alternative or dedicated shutdown systems to comply with Section III.G.3 of 10CFR 50, Appendix R.
This description is submitted in conformance with 10CFR 50.48(c)(5) and the exception to this rule granted Maine Yankee by the Commission on May 19, 1982.
This submittal is as complete a response as is possible at this time.
It may require subsequent revision for various reasons including those described below:
Our request for exemption from the requirements of Section III.0 with respect to the reactor coolant pump lubricating oil system has apparently been or is to be denied. We had been advised by NRC staf f to assume this exemption was to be granted right up until November 18, 1982, at which time we were telecopied a draf t exemption denial. We still have not received a docketed or final ruling.
In any event, it is obvious that this last minute perturbation cannot have bcen factored into our III.G.3 submittal, nor have we even had sufficient opportunity to assess its impact, if any.
There are features and aspecte of the safe shutdown design which make sense from the narrow context of the fire protection requirements. However, we fully expect that if the staf f reviews h
these issues in the broader context of plant safety, further discussion will f ollow.
5
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8211300167 821124 PDR ADOCK 05000309 F
United States Nuclear Regulatory Commission November 24, 1982 At tention:
Mr. Harold R.
Denton, Director Page two MN-82-238 Some aspects of this safe shutdown design may require NRC orders to i
implement. For example, Maine Yankee's technical specifications do raot currently permit realignment of SIAS, CIS, CSAS, AND RAS controls, logic, power supplies, breakers, etc., as described in this design submittal. These NRC actions, and the way in which they will be supported or proposed will require discussion with the staff.
We note that this issue will probably not present a problem if the NRC's proposed rule to allow deviation from limiting conditions for operation under emergency conditions is issued essentially as proposed.
Additional development of the design described in this submittal may result in identification of necessary revisions or clarifications.
Maine Yankee's safe shutdown capability is based on the use of alternate shutdown equipment and cable routing; much of which will require a plant shutdown for final installation. The schedule for the modifications necessary to implement Maine Yankes's safe shutdown capability will be developed following NRC review and approval.
Our staff is available to discuss the enclosed report and schedule with you if any questions arise.
Further, if the NRC Staf f determines that i
additional information is needed to assist in its review, Maine Yankee is prepared to furnish such information as expeditiously as is reasonably possible.
We trust this information is satisfactory.
If you have any questions, however, please contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY ArN
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John H. Garrity, Senior Director Nuclear Engineering & Licensing JHG:pjp cc:
Mr. Ronald C. Haynes Mr. Robert A. Clark Mr. Paul A. Swetland 0193 - AJC
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