ML17256A486

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Amend 56 to License DPR-18,authorizing Tech Spec Changes to Bring Audits of Emergency & Security Plans in Compliance W/ 10CFR50.54 & 73.40(d)
ML17256A486
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/09/1983
From: Crutchfield D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17256A487 List:
References
NUDOCS 8302150629
Download: ML17256A486 (5)


Text

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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.

E.

GINNA NUCLEAR POIJER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 56 License No. 'DPR-18 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Rochester Gas and Electric Corporation (the licensee) notarized December 1,

1982 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; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

D.

E.

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 regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8302i50b29 830209

, PDR ADOCK 05000244' PDR.

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2.

Accordingly, the license is amended by changes. to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-18 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications, contained in Appendix A

as revised through Amendment No. 56, are hereby incorporated in the license.

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

3.

Within 90 days after the effective date of this amendment, or such later time as the Commission may specify, the licensee shall satisfy any applicable requirement of P.L.97-425 related to pursuing an agreement with the Secretary of Energy for the disposal of high-level radioactive waste and spent nuclear fuel.

4.

This license amendment is effective as of the date of its issuance.

Attachment:

Changes to the Technical Specifications Date of Issuance:

,February 9, 1983 FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield Chief Operating Reactors.

B anch 5'5 Division of Licensing

ATTACHMENT TO LICENSE AMENDMENT NO. 56 PROVISIONAL OPERATING LICENSE NO. DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.

The revised page contains the captioned amendment number and marginal lines which indicate the area of changes.

PAGE 6.5-9

REVlEN (Continued) h.

Any indication of an unant,icipated deficiency in some r

aspect of design or operation of safety related structures, 3.

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systems, or components.

Reports and meeting minutes of the Plant Operations Review Committee.

AUDITS

6. 5. 2.8 The NSARB shall direct the establishment of an audit program and evaluate a'udits performed to,ensure safe facility operation.

Audits shall encompa s s:

a

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The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.

b.

C

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The performance, training and qualifications of the operating and technical staff at least once a year.

C The results of all actions ta)zen to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear. safety at least, once per six months.

d ~

The performance of all activities required by the 1

Quality Assurance Program to meet the criteria of Appendix B,

10 CPR 50, at least once per year.

e.

The Radiat'on Emergency Pl at least at the freouency an and implementing pro'cedures required by 10 CFR 50.54(t)

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The Station Security Plan and implementing procedures

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at least at, the frequency reouired by 10 CFR 73.40(d).

6.5-9 Amendment, No.

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, 56