ML20211A661

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Safety Evaluation Supporting Amend 49 to License NPF-12
ML20211A661
Person / Time
Site: Summer 
Issue date: 05/16/1986
From:
Office of Nuclear Reactor Regulation
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Shared Package
ML20211A660 List:
References
NUDOCS 8606110279
Download: ML20211A661 (4)


Text

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UNITED STATES f

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 49 TO FACILITY OPERATING LICENSE NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAD 0 LINA PUBLIC SERVICE AUTHORITY i

I.

INTRODUCTION South Carolina Electric and Gas Company (SCE&G), the licensee of the Virgil C.

Sumer Nuclear Plant, in a letter written to this Comission, dated March 15, I'

1985, proposed changes to the Operating License (NPF-12). These were administrative changes to the Technical Specifications presented as six attachments. As discussed below, attachments 1, 2, 3, 4, 5, and 6 are acceptable.

II. EVALUATION MONTHLY OPERATING REPORT (Section 6.9.10)

Discussion and Evaluation SCE8G proposed to change the addressee of the Monthly Operating Report to the Director, Office of Resource Management, U.S. Nuclear Regulatory Comission.

The proposed change is consistent with current NRC reporting requirements and is purely administrative in nature.

Conclusion The proposed change is accepted as submitted and is incorporated into the Technical Specifications.

FACILITY ORGANIZATION l

(Section6.5.3) l l

Discussion and Evaluation SCE&G proposed to change the organizational title of the Nuclear Engineering Department to the Technical Services Department. This accurately reflects the new title of the department. This proposed change is purely administrative in nature and dnes not effect any of the functions currently perfonned by the department.

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Conclusion The proposed change is accepted as submitted and is incorporated into the Technical Specifications.

SPENT FUEL ASSEMBLY STORAGE (Section 3/4.9-12)

Discussion and Evaluation SCE&G proposed adding Section 3/4.9-12 to the Indices for both the " Limiting Conditions for Operation and Surveillance" and the " Bases" portions of the Technical Specifications. This addition is necessitated due to changes approved in Amendment 27. The proposed changes are administrative in nature.

Conclusion The proposed change is accepted as submitted and is incorporated into the Technical Specifications.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Tables 3.3-3 and 4.3-2)

Discussion and Evaluation SCE&G proposed to clarify the terminology describing reactor building pressure trip setpoints delineated in Tables 3.3-3 and 4.3-2 of the Technical Specifications.

The proposed changes are administrative in nature.

Conclusion The proposed change is accepted as submitted and is incorporated into the Technical Specifications. Also, we have identified two other terminology inconsistencies which shall be reviewed by the licensee for possible future change. They are the following:

Table 3.3-3, Item 3, Containment Isolation, Item b(2) is termed " Reactor Building Pressure High-3." However, the correspondino item in Table 4.3-2, Item 3.b.(2), is termed " Reactor Building Pressure High-High-High."

Table 3.3-3, Item 4, Steam Line Isolation, Item C is termed " Reactor Building Pressure High-2." However, the corresponding item in Table 4.3-2, Item 4.3, is termed " Reactor Building Pressure High-High."

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DESIGN NEGATIVE PRESSURE OF THE REACTOR BUILDING (Section 3/4.6.1.4)

Discussion and Evaluation SCE&G proposed to change the value contained in the Bases for the design negative pressure differential of the reactor building with respect to the outside atmosphere. This change is required to incorporate a value that is consistent with FSAR Sections 3.8.1.3.2.1 and 6.2.1.2.2 values. This change is administrative in nature.

Conclusion The propo' sed change is acceptable as submitted and is incorporated into the Technical Specifications.

RADIATION MONITORING INSTRUMENTATION (Tables 3.3-6 and 4.3-3)

Discussion and Evaluation SCE&G proposed to clarify the required channels currently needed to meet Technical Specification 3.4.6.1.

These changes are administrative in nature.

Conclusion The proposed changes are accepted as submitted and are incorporated into the Technical Specifications.

III. ENVIRONMENTAL CONSIDERATION This amendment involves changes in recordkeeping, reporting or administrative procedures or requirements. This amendment also involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. We have determined that the amendment involves 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 made a proposed determination that the amendment involves no significant hazards considerations and there have been no comments on that proposal. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9) and (10). Pursuant to 10 CFR 951.22(b), no environmental l

impact statement or environmental assessment need be prepared in connection with l

the issuance of this amendment.

IV. CONCLUSION The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (50 FR 31072) on July 31, 1985, and consulted with the state of South Carolina.

No public comments were received, and the state of South Carolina did not have any coninents.

The staff 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, 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 Contributors:

Michael F. Runyan, Region II Jon B. Hopkins, PWR Pro,iect Directorate #2, Division of PWR Licensing-A Dated: May 16,1986

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