BECO-86-188, Forwards Rev 3 to Second 10-yr Inservice Insp Program.Rev Necessary Due to Recirculation Pipe Replacement Project Implemented During 1983-1984 Refueling Outage.Program Updated to Reflect Current Plant Configuration

Forwards Rev 3 to Second 10-yr Inservice Insp Program.Rev Necessary Due to Recirculation Pipe Replacement Project Implemented During 1983-1984 Refueling Outage.Program Updated to Reflect Current Plant Configuration

ML20212A088
Person / Time
Site:	Pilgrim
Issue date:	12/12/1986
From:	Lydon J BOSTON EDISON CO.
To:	Zwolinski J Office of Nuclear Reactor Regulation
Shared Package
ML20212A090	List: BECO-86-188, Forwards Rev 3 to Second 10-yr Inservice Insp Program.Rev Necessary Due to Recirculation Pipe Replacement Project Implemented During 1983-1984 Refueling Outage.Program Updated to Reflect Current Plant Configuration ML20212A153
References
BECO-86-188, NUDOCS 8612220277
Download: ML20212A088 (3)

Text

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sosnw anson General Offices 800 Boylston street Boston, Massachusetts 02199 James M. Lydon Chief 0peratingOfficer December 12, 1986 BECo 86-188 Mr. John A. Zwolinski, Olrector BWR Project Directorate #1 Olvision of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 License DPR-35 Docket 50-293 Second 10 Year ISI Program (Revision 3)

References:

a) NRC Letter dated August 13, 1985 (Vassallo to Harrington) b) BECo Letter dated April 15, 1986 (2.86.047) c) BECo Letter dated November 15, 1982 (2.82.296) d) BECo Letter dated December 3, 1962 (2.82.311)

Enclosure:

A) Inservice Inspection Program (Revision #3), Second Ten-Year Interval ASME XI 1980 Edition W 80 Addenda

Dear Sir:

Pursuant to 10CFR 50.55 (g), Boston Edison Company (BECo) by way of Reference (d), submitted it's Second Ten-Year Inservice Inspection Program. Due to the recirculation pipe replacement project, implemented during the 1983-1984 refueling outage, this ISI Program required revision. The program, provided as Enclosure (A), has been updated to reflect the current plant configuration including all modifications made during the 1983-1984 outage.

During the update, six previously submitted relief requests were revised and seven new relief requests were determined to be necessary for implementation of the hydrostatic test program.

A description of each new proposed or revised relief request is provided below:

PRR-1 (Revised)

This relief request was modified to document inaccessible integral attachments t

within the flued head penetrations in addition to the inaccessible circumferential welds.

9612223277 861212 b

gDR /OOCK 05000293  !

PDR I{l

. 80STON EDIS0N COMPANY December 12, 1986 Mr. John A. Zwolinski, Director Page Two PRR-3 (Revised)

This relief request was submitted to obtain relief from the requirement to examine Class 1 valve body internals except when the valves were disassembled for maintenance. For the first ten year interval, 56 Class 1 valves were divided into-20 groups according to manufacturer, manufacturing method, constructional design and function. This grouping was provided to the NRC in Reference (c) and was subsequently used for the Second Ten Year Interval Inservice Inspection Program.

For the second ten year interval, the newer code (1980 W80) eliminates the requirement to group the valves by manufacturer. The valves included in the original 20 categories have been regrouped according to the later code requirements. The number of valve categories has been reduced to seven (7) as follows:

1. gate valves - PCIS (LLRT)

2. globe valves - PCIS (LLRT)

3. check valves - PCIS (LLRT)

4. relief valves

5. safety valves

6. check valves - system isolation

7. gate valves - system isolation Our current approved ISI relief request PRR-3 states that we do not plan to disassemble valves specifically for inspection and that they will be inspected when disassembled for maintenance. The only exception is a commitment to disassemble three check valves for examination once each inspection interval per Reference (c). The valves identified in the letter were 1001-64 (inspected during RF0 #6), 1301-50 and 2301-7. Valves 1001-64 and 1301-50 are 4 inch valves and, as such, are not required to be inspected under ASME Section XI.

The original list of 56 valves, from the first ten year interval, has been reduced to 48 with the deletion of 6 four inch valves and the 2 recirculation equalizing valves (M0-202-6A & 66) removed during RF0 #6. This new listing of valves is provided as part of PRR-3. Thirty-six valves were inspected during RF0 #6, including valves from all seven groups.

Based on the new valve groupings, a separate inspection of 2301-7 should not be required as four other valves in that group have already been examined.

Therefore, the commitment to inspect three check valves has been eliminated by submitting this revised relief request.

PAR-4 (Revised) 4.

This relief request, originally submitted due to the inaccessibility of reactor vessel beltline welds, is being revised to incorporate the recommendations included in Reference (a). PRR-4 now requires that a visual

. BOSTON EDISON COMPANY December 12, 1986 Mr. John A. Zwolinski, Director Page Three examination for leakage in the vessel and shield annulus area be performed during system pressure tests of the reactor vessel.

PRR-6 (Revised)

Relief from performing surface examinations on all Class 1 & 2 welds was not granted by the NRC. Therefore, this request has been withdrawn.

PRR-8 (Revised) l This relief request, submitted in reference (b), has been revised to include surface examination of the reinforcing plate welds as suggested by your technical reviewer in a telephone conversation on August 7, 1986.

PRR-9 (Revised)

This relief request was revised to incorporate into the ISI Program the request for limited examination of the N1B nozzle inner radius section which was previously submitted to the NRC in Reference (b).

PRR-10 through 16 (New)

These relief requests are submitted to document limitations in the implementation of the hydrostatic test program. These requests are identical to the hydro relief requests submitted as Code Relief Requests B through H of Reference (b).

Other Changes It was also determined that BECo had sufficient information to select a weld sample based on the 1980 ASME XI Code including the Winter 80 Addenda rather than the 1974 Code as allowed. Therefore, the newer code will be utilized for weld selection for the second ten year inspection interval.

If you have any questions regarding this submittal, please do not hesitate to contact us.

Ver truly yours, d4** M GGW/ pac Enclosure

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