ML20065J889
| ML20065J889 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/01/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20065J896 | List: |
| References | |
| 5211-82-239, NUDOCS 8210060228 | |
| Download: ML20065J889 (2) | |
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GPU Nuclear Corporation G
U luclear
"=f=ss48o 8
Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer"s Direct Dial Number:
October 1, 1982 5211-82-239 Mr. Darrell G.
Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Fire Protection This letter transmits updated information which reflects our continuing effort to refine the engineering and implementation phases of Appendix R at TMI-1.
We have included a summary page of revisions made to Attachment 1 of our July 1, 1982 submittal (Letter 5211-82-156) along with the associated changed pages.
Revision bars have been used on the majority of these pages to highlight the updated portions. Also included is additional information regarding the alternate shutdown facility electrical systems.
Table I lists all the power circuits that connect to sources which supply power to alternate shutdown system components. This table is our response to item la of Table II of Attachment 2 of our July 1,1982 submittal.
Table II lists those circuits whose spurious actuation could adversely affect shutdown.
As stated in that table, these circuits shall be either physically separate from the fire area and/or circuit isolation facilities shall be provided to allow control of the components independent of circuit located in the fire area. Table II responds to item lb of Table II of of our July 1,1982 submittal.
Table III is a list of valves whose spurious actuation was evaluated as indicated in Section 3.12 of Attachment 1 of our July 1,1982 submittal and determined to not pose a threat to safe shutdown. Table III also identifies the consequences and correct 4<e,ctions for these valves maloperation or failure as a result of the postulated relay / control room fire.
Evaluation of DH-V1 as listed in Table III responds to Item 2b and 2c of Table II of Attachment 2 of our July 1,1982 submittal.
! 0210060220 821001 i PDR ADOCK 05000289
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PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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Mr. Darrell G. Eisechut 5211-82-239 Table IV, when completed, will identify the associated circuits which share a common enclosure wi'th.11 ternate shetdown facility circuits (Item le of Table II of Attachment 2 of our July 1,1962 submittal). The computer program developing this information is complex cnd work is still in progress debugging software and assembling input data. We will provide this information by December, 1982.
Finally, control of alternate shutdown facility isolation devices solely from the distribution panels, as was proposed in SDD 614B Rev. O has been further reviewed against required plant staffing and time constraints during the postu-lated control room / relay room fire.
It has been concluded that providing circuit breaker control for some critical components at the central areanear the remote shutdown panel will allow a smoother plant shutdown with fewer operating personnel and with less risk of an adverse plant. transient occuring during this postulated fire. The attached " Conceptual System Criteria Document for TMI-l Alternate Shutdown Facility External to Remote Shutdown Panel" provides more information on this change.
Sincerely, H. D.
ukill Director, TMI-l HDH:CJS:vj f Enclosure cc:
R. C. Haynes, w/o attachment R. Conte, w/o attachment R. Jacobs
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