ML20137A533
| ML20137A533 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/31/1985 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 VP-85-0239, VP-85-239, NUDOCS 8601140403 | |
| Download: ML20137A533 (3) | |
Text
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Vce tbctear Operatuxus Detroit Edison n=NorthCtxeHohway g:=_,
6400 December 31, 1985 VP-85-0239 Director of Nuclear Reactor Regulation Attn:
Ms. Elinor G. Adensam, Chief Licensing Branch-No. 1 Division of Licensing U.
S.-Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Ms. Adensam:
Reference:
1)
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 2)
Detroit Edison Letter to NRC, " Response to Supplement 1 of NUREG-0737,
' Requirements for Emergency Response Capability (Generic Letter)'",
EF2-62262, dated April 15, 1983 3)
Detroit Edison Letter to NRC, " Safety Parameter Display System (SPDS) Safety Analysis", EF2-67808, dated April 18, 1984 4)
Detroit Edison Letter to NRC, " Control Room Design Review Program Plan".
EF2-72747, dated August 16, 1984 9
5)
Detroit Edison Letter to NRC,
" Regulatory Guide 1.97 Compliance Report", RC-LG-85-0050, dated September 30, 1985 i
Subject:
Integrated Implementation Plan for NUREG-0737. Sunnlement 1 l
Reference 2 provided Detroit Edison's program that responds to the requirements of NUREG-0737, Supple-ment 1.
The program was identified as the Integrated Implementation Plan and referenced several long-term I
commitments whose schedule would be confirmed prior to December 31, 1985.
t.n (LIAw) 8601140403 851231 C' isE[",3,y i
PDR ADOCK 05000341 Rsa (AC m G) p PDR ros (vAssALu i Ao - c. LAINA5 (Ltr only)
Ms. Elinor G.
Adensam December 31, 1985 VP-85-0239 Page 2 The following presents the current schedule for the various components of the Integrated Implementation Plan.
Safety Parameter Display System (SPDS) - In accordance with license condition 4 in to Operating License NPF-43, the SPDS will be operational by December 31, 1985.
The safety analysis discussed in Reference 2 was submitted via Reference 3.
Detailed Control Room Design Review (DCRDR)
Program - In accordance with license condition 1(a) in Attachment 2 to Operating License NPF-43, a summary report of the DCRDR will be submitted by November 30, 1986.
The DCRDR Program Plan described in Reference 2 was submitted to the NRC via Reference 4.
Regulatory Guide 1.97 Report - Reference 5 provided a description of Detroit Edison's compliance with the requirements of Regulatory Guide 1.97.
Emergency Operating Procedures (EOP) - In accordance with license condition 3(a) in to Operating License NPF-43, Detroit Edison will submit the Procedures Generation Package (PGP) by July 31, 1986.
Subsequent to the submittal of the PGP, the Fermi 2 E0Ps wilt be revised as necessary.
As required by license condition 3(b) in to the Fermi 2 license, training programs will be revised and training completed on the revised EOPs by startup after the first scheduled refueling.
Subsequent to completion of the actions discussed above, and prior to restart from the second refueling outage, Edison will complete the Integrated Implementation Program described in Reference 2.
i
/
. e Ms. Elinor G. Adensam December 31, 1985 VP-85-0239 Page 3 Direct any further questions to Mr. Robert L. Woolley at (313) 586-4211.
Sincerely, 3
l Idb With attachment ec:
Mr.
P.
M.
Byron Mr.
M.
D.
Lynch USNRC Document Control Desk Washington, D.C.
20555 1
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