ML20216G599

Corrected Safety Evaluation Supporting Amend 182 to License DPR-35,consisting of Corrected Page 1

ML20216G599
Person / Time
Site:	Pilgrim
Issue date:	09/24/1999
From:	NRC (Affiliation Not Assigned)
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ML20216G591	List: ML20216G587 ML20216G599
References
NUDOCS 9910010106
Download: ML20216G599 (1)

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UNITED STATES 2

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NUCLEAR REGULATORY COMMISSION g

WASHINGTON. D.C. 20066-0001 p.,....j

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO; 182 TO FACILITY OPERATING LICENSE NO. DPR-35

' ENTERGY NUCLEAR GENERATION COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293

1.0 INTRODUCTION

By letter dated March 3,1999 [1], Boston Edison Company (BECo), then the licensee for the

' Pilgrim Nuclear Power Station, requested that the Nuclear Regulatory Commission (NRC) review and approve its proposed Technical Specification (TS) change to modify its reactor

. pressure vessel (RPV) surveillance capsule withdrawal schedule. The proposed change would change the date of withdrawal of tha next surveillance capsule in TS Table 4.6-3 from 15 1

. effective full power years (EFPY) of operation to 18 EFPY. BECo's submittal was made in accordance with the provision of Title 10 of the Code of Federal Reaulations. (10 CFR), Section 50.90, which specifies that when license holders desire to amend their license, an amendment application must be filed with the' Commission, as specified in 10 CFR 50.4. This provision is

, invoked since the' facility TSs are incorporated directly as part of the facility's license. Entergy Nuclear Generation Company, which became the licensee for Pilgrim on July 13,1999, adopted all pending amendment requests previously filed by BECo.

2.0 ' REGULATORY REQUIREMENTS AND STAFF POSITIONS I

' Nuclear power plant licensees are required by 10 CFR Part 50,' Appendix H, to implement RPV surveillance programs to " monitor changes in the fracture toughness properties of ferritic yf materials in the reactor vessel beltline region.'..which result from exposure o g{f neutron irradiation and the thermal cnWcnment." Regarding RPV s and specimen testing,10 CFR Part 50,- Appendix H, incorporates by reference the editions of

- the American Society for Testing ~and Materials (ASTM) Standard Practice E 185," Conducting o

R. Surveillance Tests for Ught-Water Cooled Nuclear Power Reactor Vessels," through the 1982 g ' edition. Under 10 CFR Part 50, Appendix H, the licensee's RPV surveillance program design 1

and withdrawal schedule is required to meet the requirements of the edition of ASTM E 185 that is current on the issue date of the American Society of Mechanical Engineers (ASME) Code to L which the RPV was purchased, although later editions may be used, up to and including the I

p 1982 edition. The test procedures and reporting requirements must however meet the E

requirements of the 1982 edition of ASTM E185, to the extent practical for the configuration of j

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! the specimens in the capsules, j

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A LAs referenced in Pilgrim TS 4.6.A., the ( jition of ASTM E 185 to which the Pilgrim RPV l

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• surveillance program was designed was the 1966 edition (ASTM E 185-66). Paragraph 4.6 of '

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the ASTM E 185-66 addresses the withdrawal schedule as follows, "[i]t is recommended that 4

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' sets of specimens be withdrawn at three or more separate times. One of the data' points F

.obtained shall correspond to the neutron exposure of the component near the end of its design k

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