ML20212F270

Amend 57 to License NPF-12,revising Qualification Requirements for Individuals Performing Certain Safety Reviews Required by Tech Spec Section 6.5.3.1

ML20212F270
Person / Time
Site:	Summer
Issue date:	12/22/1986
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212F253	List: ML20212F249 ML20212F270 ML20212F284
References
NUDOCS 8701090630
Download: ML20212F270 (4)

Text

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c ua 48 uq'c UNITED STATES 8  % NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D. C. 20555 S

% . . . . . ,o SollTH CAROLINA FLECTRIC & GAS COMPANY SOUTH CAD 0 LINA PilBLIC SEPVICE AUTHORITY DOCKET NO. 50-3q5 VIMIL C. SUMMER NUCLEAD STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-12

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment by South Carolina Electric A Gas Company and South Carolina Public Service Authority (the licenseesi dated August 2, 1985, as supolemented September 11, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; R. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's reaulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; l

and l

l E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordinolv, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(P) of Facility Operating License No. NPF-12 is hereby amended to read as follows:

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8701090630 861222 PDR ADOCK 05000395 P PDR

(2) Technical 5pecifications -

The Technical Specifications contained in Appendix A, as revised through Amendment No. 57 , are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3. This amendment is effective as of its date of issuance, and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION hs['a f ,. tu ma k m . ,

Lester S. Rubenstein, Director PWR Pro,iect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 22, 1986

. ATTACHMENT TO LICENSE AMEN 0 MENT i

AMENDMENT NO. 57 TO FACTLITY OPERATINri LICENSE NO. NPF-19 DnCKET NO. 50-395 -

Replace the followino page of the Appendix "A" Technical Specifications with the enclosed page.

Remove Paaes Insert Pages 6-12 6-12 1

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ADMINISTRATIVE CONTROLS

c. Proposed tests and experiments which affect plant nuclear. safety and are not addressed in the final Safety Analysis Report shall be reviewed by an individual / group other than the individual / group which prepared the proposed test or experiment.

d. Events reportable pursuant to the Technical Specification 6.9 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the event and which provides recom-mendations to prevent recurrence. Such report shall be approved by the Director, Nuclear Plant Operations and forwarded to the Chair-man of the Nuclear Safety Review Committee.

e. Individuals responsible for reviews performed in accordance with 6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall be members of the plant staff that meet or exceed the qualification requirements of Sec-tion 4 of ANSI 18.1, 1971, as previously designated by the Director, l Nuclear Plant Operations. Each such review shall include a determina-tion of whether or not additional, cross-disciplinary, review is ne-cessary. If deemed necessary, such review shall be performed by the -

review personnel of the appropriate discipline. (

f. Each review will include a determination of whether or not an unreviewed safety question is involved.

RECORDS 6.5.3.2 Records of the above activities shall be provided to the Director, Nuclear Plant Operations, PSRC and/or NSRC as necessary for required reviews.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review shall be submitted to the NSRC and the Vice President, Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President, Nuclear Operations and the NSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence,

c. The Safety Limit Violation Report shall be submitted to the Commission, the NSRC and the Vice President, Nuclear Operations within 14 days of the violation.

SUMMER - UNIT 1 6-12 Amendment No. 75,57