ML18051B463

Forwards Request for Relief from Reactor Vessel Inservice Insp Primary Loop Exam.Basis for Request Included.Request Approved by Plant Mgt & Will Be Incorporated Into 40-yr Master Inservice Insp Plan.Fee Paid

ML18051B463
Person / Time
Site:	Palisades
Issue date:	07/09/1985
From:	JOHNSON B D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8507150031
Download: ML18051B463 (4)

Text

-consumers Power company General Offices: 1945 West Parnell Road, Jackson; Ml 49201 *.{517) 1aa-osso July 9, 1985 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT --REQUEST FOR RELIEF FROM SPECIFIC ASME B&PV CODE REQUIREMENTS Pursuant to 10CFR50.55a(g) and Palisades Technical Specification 4.3.c, relief requests from certain provisions of Section XI of ASME B&PV Code are being submitted for NRC review and approval.

Consumers Power Company submittals dated November 12, 1980 and November 16, 1982 requested relief for the Palisades Plant, from requirements*of ASME Code Section XI which were impractical to perform. The NRC formally approved those requests for relief by letter dated August 23, 1984. Following the 1983 Inservice Inspection and subsequently 10 year Reactor Vessel Inservice Inspection, it has been determined that it is necessary to request additional relief with regard to primary loop examination.

The attachment to this letter identifies the additional relief requested and provides the basis. This relief request has been reviewed and approved by plant management and the PRC and will be incorporated into the Palisades Plant 40 year Master Inservice Inspection Plan upon approval by the NRC. Enclosed is a check for $150 as required by 10CFR170.21.

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNR.C NRC Resident Inspector

-Palisades Attachment OC0685-0221-NL04 8507150031 850709 PDR ADOCK 05000255 G PDR 3 I __ (

\ .... . IC0685-0221-NL04

-ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 RELIEF REQUEST July 9, 1985 2 Pages -

'-" ' '-* .. --PALISADES NUCLEAR PLANT INSERVICE INSPECTION Review and Approval For: Proposed Requsts for the relief from provisions of ASME B&PV Code,Section XI, pursuant to 10CFR50.55a

1. Prepared 2. Technical Review v: v-tir originator

-?luk,-3. Administrative Review 4. PRC Reviewed Note: The attached document is to be incorporated into the Palisades Nuclear Plant 40-Year Master Inservice Inspection Plan upon review/approval.

• . ... . .. --Attachment 1 Arnrnendment to Relief Request #4 (RR-4) RR-4a Item B9.ll, B9.12 (Pressure Retaining Piping) Basis Statement Relief Request #4, included in prior submittals, requested relief from face examination requirements for the affected welds due to inaccessibility.

Relief Request #4 also stated that volumetric examination of these welds could be perfonned from the reactor vessel ID utilizing a mechanized inspection device and committed to the same. During the 1983 Inservice Inspection it was detennined, however, that all of the welds were not accessible due to piping geometry (elbows), weld location, and mechanized equipment design. cessful examinations were performed on 21% of the welds, with the remaining welds being inaccessible for examination.

Remarks Welds successfully examined were: (all nozzle to transition piece) PCS-42-RCL-lH-l PCS-30-RCL-lB-14 PCS-42-RCL-2H-l PCS-30-RCL-lA-16 PCS-30-RCL-2B-15 Welds determined inaccessible for ID volumetric examination were: PCS-42-RCL-lH-2 PCS-42-RCL-2H-2 PCS-30-RCL-lA-15, lSLD-1, lSLD-2, 16LU-l, 16LU-2 PCS-30-RCL-lB-13, 13LD-l, 13LD-2, 14LU-l, 14LU-2 PCS-30-RCL-2A-14, 14LD-l, 14LD-2, lSLU-1, lSLU-2 PCS-30-RCL-2B-14, 14LD-l, 14LD-2, lSLU-1, lSLU-2 I Implementation

& Relief Requested It is requested that additional relief be granted from the ID volumetric examination of the welds determined to be All welds cessible for ID volumetric examination will .continue to be examined visually each outage for evidence of leakage by observing the general area after the four-hour hold time. In addition, welds which were successfully examined from the ID, will continue to be examined by that method.