ML20083C012
| ML20083C012 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/05/1995 |
| From: | Mueller J NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS950111, NUDOCS 9505150070 | |
| Download: ML20083C012 (3) | |
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COOPER NUCLEAR STATION '
H Nebraska Public Power District P.o. Ook 08. BROWNVILLE. NE8RASKA 08321 3
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-i NLS950111 i
May~5, 1995 l
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-U. S. Nuclear: Regulatory Commission Attention: Document Control Desk Washington, D C.
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Subj ect:
Inservice Inspection Interval Revision per 10 CFR 50.55a Cooper Nuclear Station, NRC Docket 50-298, DPR-46 Gentlemen:
The current ten year inservice inspection interval for the Cooper Nuclear Station (CNS) was originally scheduled-to be completed on August 31, 1995.
.Due to the' extended outage of 1994, the end of the interval will be extended to January l' 1996, subject to completion of the fall 1995 refuel outage.
This extension is allowed by the ASME Boiler and Pressure Vessel Code, l
section XI, IWA-2400(c).
10 CFR 50.55a requires all licensees to conduct an augmented volumetric examination of the reactor vessel shell welds specified in Item Bl.10 of Examination Category B-A, " Pressure Retaining Welds in Reactor Vessel," Table IWB-2500-1 of section XI of the ASME Code.
10 CFR 50.55a also revokes all previously approved relief' requests for ASME section XI, Category B-A, reactor vessel weld examinations.
i However, 10 CFR 50.55a(g)(6)(ii)(A)(3) states that " Licensees with fewer than 40 months remaining in the inservice inspection interval in effect on September 8, 1992 may defer the augmented reactor vessel examination specified-i in 10 CFR 30.55a(g)(6)(ii)(A)(2) to the first period of the next inspection interval..."
Also, 10 CFR 50.55a(g)(6)(ii)(A)(3)(iv) states that " Licensees that defer the augmented examination, as permitted herein, may retain all previously granted reliefs that otherwise would be revoked by 10 CFR t
50,55a(g)(6)(ii)(A)(1) for the inspection interval in effect on September 8, i
1992."
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May 5, 1995 Page 2 Since the inservice inspection interval in effect on September 8, 1992 was scheduled to end within the following forty months, CNS has elected to defer the augmented inspection of the reactor pressure vessel until the first period of the next inspection interval.
The existing approved relief request for the i
reactor vessel beltline welds, RI 06, remains in effect for the current i
interval.
If you have any questions or require additional information, please contact 1
me.
Sincerely, l
IJIn^ h John H. Mueller Site Manager cc:
Regional Administrator i
USNRC - Region IV Arlington, Texas NRC Resident inspector Cooper Nuclear Station i
NPG Distribution
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LIST OF NRC COMMITMENTS l ATTACHMENT 3 l Correspondence No:
NLS950111 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District.
They are described to the NRC for the NRC's j
information and are not regulatory commitments.
Please notify the Licensing Manager i
at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE l
COMMITMENT OR OUTAGE I^
None
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