ML20217M958
| ML20217M958 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/13/1997 |
| From: | Stanley G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-01, GL-96-1, NUDOCS 9708250389 | |
| Download: ML20217M958 (2) | |
Text
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C4mmtonwealth IXiaon Company a
tiraldmd Generating Nation Route 81.11os 81 liratesille, IL (4407 %19 TelHIOn % 2801 August 13,1997 Document Control Desk U. S. Nuclear Regulatoy Commission Washington D.C. 20555
Subject:
Braidwood Station Units 1 and 2 Response to NRC Genetic Letter 96-01:
Testing of Safety-Related Logic Circuits Rocket Nos. 50-456 and 50-457
Reference:
1.
NRC Generic Letter 96-Oi:
Testing of Safety-Related Logic Circuits dated January 10,1996 2.
J. C. Brons letter to the Nuclear Regulatoy Commission (NRC),
" Commonwealth Edisen Company (Comed) Response to NRC l
Generic Letter (GL) 96-01," dated April 19,1996 1
in Reference 1, the NRC transmitted GL 96-01, which requested certain systems be reviewed against their technical specification surveillances to ensure all portions of the logic circuitry are adequately covered to fulfill the technical specification requirements --
and either to revise the surveillances as necessary, or request relief through an amendment to technical specifications. These actions were requested to be accomplished prior to startup from the first refueling outage commencing one year atler the issuance of the generic letter.
In Reference 2, Comed transmitted the 60 day response to the Generic Letter, agreeing that the Braidwood Nuclear Generating Station would implement the actions as described in GL 96-01. Reference 2 also stated it wo'dd confirm completion of the actions requested within 30 days following their completion.
Braidwood Unit i began it's latest refheling outage on March 29,1997, and while this commitment was substantially completed, and subsequent events have indicated that an
. expansion of the original review scope is appropriate. Operating Experience Report OE8435, "SSPS P-11 Not Surveilled Quarterly," was issued in June of 1997, which identified inadequate testing ofinterlock circuitry for the P-1i Permissive at another PWR statien. Upon review of this OE, Braidwood Station personnel found that this condition existed at Braidwood Station, and resulted in issuance of LER 97-005. Subsequently, it was determined that an expanded review of logic circuitry would be required to fully 3
complete the GL 96-01 request. An action plan to perform this review is being developed.
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This expanded review is applicable to Braidwood Unit 2 as well, which has a refueling Cb' outage scheduled to begin in September of 1997.
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PDR ADOCK 05000456 c
A I!nicum Company b
o Document Control Desk 2
Aug'ist 13,1997 The purpose of this letter is to inform the StafTthat the original expected completion dates are bei.1g revised due to the expanded work secpe. Braidwood Station expects to complete the actions associated with GL 96-01 for both Units 1 and 2 by March 15,1998.
If you have any questions regarding this matter, please contact Richard Schliessmann at Braidwood extension 2038.
/er$
Site Vice President Braidwood Nuclear Generating Station A. B. Beach, Regional Administrator, Region 111 cc:
G. F. Dick, Project Manager, NRC l
C. J. Phillips, Resident inspector, Braidwood Station l
Ollice of Nuclear Safety, IDNS
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