ML20211L098
| ML20211L098 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/03/1986 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-1002 2469K, NUDOCS 8612150300 | |
| Download: ML20211L098 (1) | |
Text
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) CORNRORW000th h
_ ;on.r., - C%.im Address Reply to: Post Omco Box 767 s
Checa00. lHinois 60000 0767 December 3, 1986 Mr. Harold R. Denton U.S. Nuclear Regulatory Conunission Office of Nuclear Reactor Regulation Washington, DC. 20555
Subject:
Braidwood Station Unit 1 Preservice Inspection (PSI) Program Revisions and Clarifications NRC Docket No. 50-456
Reference:
(a) September 18, 1986 A.D. Miosi letter to H.R. Denton (b) NUREG-1002 Safety Evaluation Report Supplement No 2, dated October, 1986
Dear Mr. Denton:
Reference (a) provided Commonwealth Edison's commitment to perform augmented Inservice Inspections (ISI) for the Safety Injection, Chemical and Volume Control and Containment Spray systems for Braidwood Unit 1.
Reference (a) also qualified why the Residual Heat Removal (RHR) system did not require this augmented ISI.
Subsequently, this same information was reiterated in reference (b).
Upon reviewing these documents it has been identified that the qualification of the RHR system in this area needs to be clarified and the purpose of this letter is to provide that clarification. Specifically, the RHR system does not include any exempted piping greater than 4" in diameter that would require the augmented ISI.
Examination of RHR piping with a i
diameter greater than 4" is to be included as a part of the Braidwood ISI program.
This information is being forwarded to you so that appropriate corrections can be made in the next Safety Evaluation Report Supplement.
One signed original and fifteen (15) copies of this letter are provided for your review.
Very truly yonrs, fhfg Sb WW PDR S. C. Hunsader E
Nuclear Licensing Administrator
/klj ec:
J. Stevens 2469K d
I/o
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