ML20154P661

SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4)

ML20154P661
Person / Time
Site:	Pilgrim
Issue date:	09/28/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19318G897	List: ML20154P661 ML20154P680
References
NUDOCS 8810030140
Download: ML20154P661 (6)

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SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULAT!g RELATED TO THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM BOSTON _ EDISON COMPANY PILGRIM NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-293 INTRODUCTION The Technical Specifications for the Pilgrim Nuclear Power Station, Unit 1, states that the structural integrity of the primary system boundary shall be maintained at the level required by the ASME Boiler and Pressure Vessel Code,  ;

Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"

Articles IWA, IWB, IWC, IWD, and IWF and mandatory appendices as required by 10 CFR 50, Section 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

Inservice inspection of components shall be performeo in accordance with the Pilgrim Nuclear Power Station, Unit 1, Inservice Inspection Program.

Pursuant tu 10 CFR 50.55a(g)(4), ASME Code Class 1, 2 and 3 components (including supports) shall nvet the requirements, except the design and access provisions dnd the preservice examination requirements, set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, gecretry and materials of ccnstruction of the components. In addition, inservice examination of components and systems pressure tests conducted during successive 120-month inspection intervals shall conply with the requirements in the latest edition and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date 12-month prior to the start of the 120-menth inspection interval, subject to t.5e limitations and modifications listed therein.

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0 Pursuant to 10 CFR 50.55a(g)(5)(iii), if the licensee determines that confonn-ance to an examination requirement of Section XI of the ASME Code is not practical for his facility, information is submitted to the Comission in support of that determination and a request made for relief from the require-ment. After evaluation of the determination, pursuant to 10 CFR 50. ig)(6)

(i), the Commission may grant relief and impose alternative requirements as it determines are authorized by law and will not endanger life or property or the comn.cn defense and security and are otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the require-ments were imposed.

The Boston Edison Company, the licensee, p"epared the Second Ten-Year Interval Inservice Inspection Program, Revision 3 for the Pilgrim Nuclear Power Station, Unit 1, to meet the requirements of the ASME Code,Section XI,1980 Edition, including Winter 1980 Addenda. The second ten-year inspection interval began on Cecember 8,1982, and ends on December 8,1992.

The Second Ten-Year Interval Inservice Inspection Program, Revision 3, submitted December 12, 1986, Amendment ISI 87-02, submitted March 2,1988, and additional information, including requests for relief from ASME Code requirements determined by the licensee to be impractical for the Pilgrim Nuclear Power Station Unit 1, was reviewed by the staff and their contractor, Idaho National Engineering Laboratory. Revision 3 of the Second Ten-Year Interval Inservice Inspection Program reflect the current plant configuration including the recirculation pipe replacement made during the 1983/1984 outage. The licenseo provided an itemized listing of components, isometric drawings, a listing of the ultrasonic calibration blocks used during the second ten-year interval, and clarification of the examination procedures in support of the program. The program was evaluated for a) compliance with the appropriate ASME Code Section XI Edition and Addenda, b) acceptability of the examination sample, c) exclusion criteria, and d) compliance with augmented and/or other examination comitments identified during the licensing process.

EVALUATION The determinations addressed by the licensee in the Second Ten-Year Interval Inservice Inspection Prcgram, Revisicn 3, and to the staff's request for additional information that certain ASME Code requirements were impractical to perform at the Pilgrim Nuclear Power Station, Unit 1, were evaluated. The detailed evaluation is attached in the Technical Evaluation Report (TER) from .

our contractor, Idaho National Engineering Laboratory. The staff concurs with and adopts the evaluaticn with the exception that relief is not granted for category B-A welds in the reactor pressure vessel. The examination procedure for these welds is under staff review at this time. The sumary of our evaluation is shewn in Table 1. As noted in the attached TER, recuiring compliance with all the exact Section XI required inspections would require redesign of a significant number of plant systems, sufficient replacement components to be obtained, installation of the new components, and baseline examination of  ;

these components. The reactor pressure vessel and a number of the piping and component support systems are examples of comoonents that would require redesign te meet the specific inservice examination provisions. Even after the redesign efforts, complete compliance with the Section XI examination requirements prcbably could not be achieved.

Reference is made in this evaluation to the Safety Evaluation Report, August 13.

1985, including the Technical Evaluation Report (SAIC - 84/1656) by Science Application International Corporation, and to the Supplemental Safety Evaluation Report February 6, 1987.

CONCLUSION -

We conclude from our evaluation that the Second Ten-Year Interval Inservice Inspection Prcgram, Revisien 3. for the Pilgrim Nuclear Power Station, Unit 1.

is acceptable and in compliance with 10 CFR 50.55a(g)(41. Pursuant to 10 CFR 50.55a(g)(6)(i), we have determined that certain ASME Code Section XI examination i requirements are impractical to perform at the Pilgrim station, Unit 1, and c

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have granted relief from those requirements and we have imposed alternative  !

requirements, as necessary. This relief is authorized by law and would not endanger life or property or the common defense and security and is in the l public interest giving due consideration to the burden upon the licensee that i would result if the recuircrents were imposed on the facility.

Pursuant to 10 CFR 50.55a(g)(6)(i) and based on the alternatives proposed, relief is granted from ASME Code Section XI requirements for request numbers  :

, PRR-1, Rev. 2 PRR-2, Rev. O, PRR-3, Rev. 1 PRR-7, Rev. 1. PRR-8, Rev. 1, ,

PRR-10, Rev. O, PRR-11 Rev. O PRR-13 Rev. O, and PRR-15, Rev. O. ,

The staff is in prccess of reviewing the examination procedures fnr the reactor l pressure vessel and relief is not granted for request numbers PRR-4, Rev.1 and f

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j PRR-5, Rev. 1 Category B-A welds. Pelief requests number PRR-6, PRR-1?, Rev.0 l and PRR-14, Rev. I were withdrawn and subsequently no action was taken on these  !

requests.

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j Principal Contributor:

i j F. Litton 1

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TABLE 1 STATUS OF RECUESTS FOR RELIEF FROM ASME

_ CODE REQUIREMENT REQUEST EXAMINATION NUMBER _

CATEGCRY DESCRIPTION STATUS PRR-4, B-A Reactor Pressure Vessel Not Granted Rev. 1 Item Bl.11 and Shell Circumferential B-1.12 and Longitudinal Welds i FAR-5, B-A Reactor Pressure Vessel Rev. 1 Item B1.21 and Bottom Head Welds Not Granted 81.22 PRR-9, B-D Reactor Pressure Vessel Granted Rev. 1 Item 03.90 and Nozzle to Vessel Welds 83.100 and Inside Radius Section PRR-1, B-J Class 1 Piping System Pressure Granted Rev. 3 Item 89.11 and 89.21 Retaining and Integrally helced B-K-1 Attachcents within Flued Head Item 810.10 Penetrations PRR-6 B-J Class 1 Piping System Withdrawn Item B9.10 and Pressure Retaining Welds 89.40 PRR-2, B-L-2, Recirculation Pump- Granted Rev. C Item 812.20 Internal Surfaces PRR-3 B-M-2, Class 1 Valve Bodies Granted Rev. 1 Item 212.a0 Internal Surfaces PRR-8, C-8, RHR Heat Exchanges Nozzle-to- Granted Pev. 1 Iten C2.21 Vessel Welds and Inside Radius Sections PRR-6 C.F. Class 2 Pipitig Systems - Withdrawn Item C5.10 and Pressure Retaining Welds C5.32 PRR-7 C-F, Containment Atmospheric Control Granted Rev. 1 Item C5.11 and System-Pressure Petaining Welds C5.12 PRR-12. C-H Hydrostatic Test of the Control Withdrawn Rev. O Rud Drive Hydraulic System

REQUEST EXAMINATION NUMBER CATEGORY DESCRIPTION STATUS PRR-13, C-H Hydrostatic Test of the Granted t Rev. O Class 2 Portions of the Containment Atmospheric Control Syster.

PRR-15, C-H Hydrostatic Test of the Granted Rev. O High Pressure Coolant Injection Turbine Exhaust Drain Line PRR-10, D-B Hydrostatic Test of Two Granted l Ten-liter Shielded Samples Rev. O Chambers  ;.

PRR-11, D-B Pydrostatic Test of the Granted Rev. O Salt Service Water System PRR-14, C-H, 0-A, Hydrostatic Test of Class Withdrawn D-8, D-C 2 and 3 Systems Containing Relief valves and Instru-rentation.

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