ML18005B115

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Safety Evaluation Supporting Amend 13 to License NPF-63
ML18005B115
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 10/11/1989
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18005B114 List:
References
NUDOCS 8910240338
Download: ML18005B115 (6)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 13 TO FACILITY OPERATING'ICENSE NO. NPF-63 CAROLINA POWER 8 LIGHT COMPANY et al.

SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 1.0

2.0 INTRODUCTION

By letter dated December 17,

1987, as supplemented September 25, 1989, the Carolina Power 5 Light Company submitted a request for changes to the Shearon Harris Nuclear Power Plant, Unit 1, (Harris) Technical Specifica-tions (TS) which would make corrections or clarifications to several sections.

The September 25, 1989, letter provided-clarifying information that did not alter the actions noticed, or change the initial determination of no significant hazards consideration as published in the Federa'I Re ister (54 FR 37042).

Specifically, the following eight correct>ons an c arifica-tions would be made:

(1) establish consistency of nomenclature when a

table or figure is deleted from the TS index; (2) insert omitted brackets to equation in Note 1 of Table 2.2-1 used to calculate the overtemperature trip set points; (3) clarify report submission timing for consistency between TS 3.3.3.6 Action c, 6.9.2, 3.3.3.4a and 3.3.3.9.a; (4) correct spelling of radioactivity in Item 1, Table 4.3-8; (5) improve consistency in nomenclature by deleting brackets enclosing train identifiers for residual heat removal loops in TS 3.4.1.3.d and 3.4.1.3.e; (6) delete references to deleted Table 3.6-1 from TS 4.6.3.2 and 4.6.3.3; (7) revise reference for special reporting in Surveillance Requirement 4.4.5.5.c, bases for Section 3/4.2.4 and TS 6.9.1, and 6.9.2 to refer to TS 6.9.2 or 10 CFR 50.4, as appropriate, for consistency; and (8) add additional information to TS sections where the specifications were relocated to plant procedure PLP-106.

These changes are discussed in the following paragraphs.

EVALUATION The requested changes are all administrative in nature

and, as such, do not affect equipment, system or plant safety.

For example, change (2) inserting omitted brackets to the equation in Note 1 of Table 2.2-1 and (4) correct the spelling of radioactivity are corrections and are, therefore, acceptable.

Changes (1), (3), (5) and (7) are for consistency throughout the TS, which improves clarity and reduces the potential for misinterpretation, and are, therefore, acceptable.

Section 6.9.1.6 was included as a change as part of the request for revised reporting requirements in the licensee's December 17, 1987 submittal.

However, the reporting revision for Section 6.9.1.6 was included in Amendoant No.

7 8910240338 89iOii I'DR ADQCfih. 05000400 issued August 16, 1988 and, therefore, is not included in this amendment.

Change (6), removal of references to a table which has been removed from the TS, reduces the potential for confusion and increases clarity and is, therefore, acceptable.

A major revision in the TS between the low power and full power licenses occurred for Harris.

This modification was part of the TS improvement efforts and resulted in a revision and reissue of the Harris -TS, relocating certain surveillances and technical data related to valves,

snubbers, materials and containment penetration conductor overcurrent protective devices to the Harris plant procedure, PLP-106, Technical Specification Equipment List Program.

The requested changes descr ibe more thoroughly where the relocated material may be found, are clarifications arid are, therefore, acceptable.

This change affects Tables 3.3-2, 3.3-5, 4.4-5, 3.6-1, 3.8-1, and 3.8-2; Surveillance Requireaant 4.4.9.2.2; pages

'/4 7-20 through 3/4 7-23; and Figure 4.7-1.

In surm ary, the staff finds th~ requested chan s to be administrative in nature.

These changes are corrections, amplif cations and clarifications and, therefore, acceptable.

3.0 ENV IRONNENTAL CONSIDERATION This amendment changes a requirement with respect to installation or use of a facility component located within the restricted areas as defined in 10 CFR Part 20 and changes surveillance requirements.

The staff has determined that the amendment involves iio significant iiicrease 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 occupatioiial radiation exposure.

The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration, and there has been no public comment on such findings.

Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth,in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION The Commission made a proposed determination that this amendment involves no significant hazards consideration which was published in the Federal Re ister (54 FR 37042) on September 6, 1989, and consulted with Gi~eHate o

<ort Carolina.

No public comments or requests for hearing were

received, and the State of North Carolina did not have any comments.

The NRC staff has concluded, based on the consideration 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

Richard A. Becker Date:

October ll, 1989

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AMENDMENT40. 13 TO FACILITY OPERATING LICENSE NO.

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