ML20117J363

From kanterella
Jump to navigation Jump to search
Safety Evaluation Supporting Amends 112 & 110 to Licenses DPR-80 & DPR-82,respectively
ML20117J363
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/28/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20117J358 List:
References
NUDOCS 9605310106
Download: ML20117J363 (3)


Text

l p itto p

4 UNITED STATES e

S NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30866-4001 i

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 112 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO.110 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY l

DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-321 l

1.0 INTRODUCTION

By application dated March 13, 1996, Pacific Gas and Electric Company (or the i

licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos. DPR-80 and DPR-82) for the Diablo Canyon Nuclear Power Plant, Units 1 and 2.

The proposed changes would revise TS 4.0.5a to delete the requirement for NRC written approval prior to implementation of relief from ASME Code requirements by deleting

...(g),.except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1)." Also the amenhnts would add ASME Section XI definition of " Biennially or every 2 years - At least once per 731 days," in TS 4.0.5b.

2.0 BACKGROUND

The Commission's final policy statement on technical specifications improvements defines the scope of the technical specifications (IS) and provides a criterion for technical design items to be included in, or relocated out of the TS document. On July 19, 1995 (60 FR 36953), the NRC published the. final rule governing the implementation of this policy via a revision of 10 CFR 50.36, " Technical Specifications," which became effective August 18, 1995. The April 7,1995, revised version of the Standard Technical Specifications (STS) (NUREG-1431, Rev.1), relocates the inservice testing (IST) requirements to the administrative controls section of the Td and deletes a portion of the inservice inspection (ISI) requirements, retaining the reactor coolant pump (RCP) flywheel inspections in the administrative controls section. NUREG-1482, " Guidelines for Inservice Testing Programs at Nuclear Power Plants," Chapter 6, recomends that licensees revise their TSs to incorprete the revised STS for IST programs.

The 10-year interval for the Diablo Canyon Unit 1 IST and ISI programs began January 1,1996, and Unit 2 IST and ISI programs begins on June 1,1996. The TS change will allow the licensee a period of 12 months from the beginning of the intervtl to identify, submit, and obtain approval of relief requests for impractical code requirements in accordance with 10 CFR 50.55a, paragraphs (f)(5) and (g)(5), for IST and ISI respectively.

9605310106 960528 PDR ADOCK 05000275 P

PDR hr a

. l 3.0 EVALUATION The licensee has made a revision to TS 4.0.5a and its Bases deleting the clause requiring written relief from the Commission under all ISI and IST testing deviations. Diablo Canyon Power Plant based these revisions on the guidance of NUREG-1482; NUREG 1431, Revision 0; Generic Letter (GL) 89-04, Supplement 1 " Guidance on Developing Acceptable Inservice Testing Programs;"

and 10 CFR 50.55a.

If an impracticality is determined within the initial interval or within the first 12 months of a new interval, the licensee follows the requirements in 10 CFR 50.55a(f)(5)(iii) and (iv) or (g)(5)(iii) and (iv).

If an impractical requirement is identified during subsequent intervals and not within the first 12 months, the licensee must meet the requirements of 10 CFR 50.55a(f)(5)(iii) or (g)(5)(iii), notify the Commission, submit the information supporting the determination of impracticality, and obtain NRC's approval pursuant to (f)(6)(1) or (g)(6)(i), prior to the time that the next l

test or inspection is required. However, the specification does not allow the i

licensee to implement alternative testing under paragraphs 50.55a(a)(3)(1) and j

(ii) until authorized by the Director of the Office of Nuclear Reactor Regulation.

l j

The licensee further proposes to add the ASME Code Section XI definition of l

biennial in TS 4.0.5b to be consistent with NUREG-1482 recommendations.

a l

These changes to the licensee's TS are consistent with the intent of the revised STS and the regulatory guidance in NUREG-1482. The ISI and IST L

requirements are given in 10 CFR 50.55a, which the licensee documents via its 1

10-year interval program requirements. The change is acceptable since the j

regulatory requirements are delineated in 10 CFR 50.55a, and the change eliminates inconsistencies between the TS and the regulations.

1 i

4.0 STATE CONSULTATION

i i

In accordance with the Commission's regulations, the California State official was notified 'of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIR00 MENTAL CONSIDERATION l

These amendments change a surveillance requirement. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards t

consideration, and there has been no public comment on such #inding (61 FR 18173). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR i

51.22(b) no environmental impact statement or environmental assessment need be l

prepared in connection with the issuance of the amendments.

1 3

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

S. Bloom Date:

May 28, 1996

,