ML17262A490

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Amend 42 to License DPR-18,revising Tech Specs to Modify Method of Locking Valve 856 Open from Removal of Ac Power to Removal of Dc Control Power in Order to Enable Valve Manipulation from Control Room
ML17262A490
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/03/1991
From: Wessman R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17262A491 List:
References
NUDOCS 9106050017
Download: ML17262A490 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 ROCHESTER GAS ANO ELECTRIC CORPORATION DOCKET I'JO. 50-244 R. E.

GINHA NUCLEAR PO>JER PLANT AMENDNEHT TO FACILITY OPERATING LICENSE Amendment Ho.

42 License No.

DPR-18 1.

The Nuclear Regulatory COIIIIIIission (the Commission or the'NRC) has found that'.

The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated February 15,

1991, 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.

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 set forth in 10 CFR Chapter I; D.

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 E.

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.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License Ho. DPR-18 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment Ho. 42, are hereby incorporated in the license.

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

9106050017 910603 PDR ADOCK 05000244 P

PDR

3.

Thislicense amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

0une 3, 1991

'N Richard H. Nessman, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

42 FACILITY OPERATING LICENSE NO.

DPR-18 DOCKET NO. 50-244 Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

Remove 3.3-2 Insert 3.3-2

d.

e.

At or above an RCS temperature of 350'F, two residual heat removal pumps are operable.

At or above an RCS temperature of 350'F, two residual heat removal heat exchangers are operable.

At the conditions required in a through e

above, all valves, interlocks and piping associated with the above components which are required to function during accident g,

conditions are operable.

At or above an RCS temperature of 350'F, A.C. power shall be removed from the following valves with the valves in the open position:

safety injection cold leg injection valves 878B and D.

A.C.

power shall be removed from safety injection hot leg injection valves 878A and C with the valves closed.

D.C. control power shall be removed I

from refueling water storage tank deli@cry valves

896A, 8960 and 856 with the valves open.

h.

At or above an RCS temperature of 350'F, check valves 853A, 853B, 867A, 867B, 878G, and 878J shall be operable with less than 5.0 gpm leakage each.

The leakage requirements of Technical Specif ication

3. 1. 5. 2. 1 are still applicable.

Above a reactor coolant system pressure of 1600 psig, A.C. power shall be removed from accumulator isolation valves 841 and 865 with the valves open.

HPC Order Dated April 20,"'981 3 ~ 3 2

Pmendgent No, 7J, gg, 42,

A%NDNENT ND.

42 TD DPR R.

E.

GLNNA NUCLEAR PURER PLI DATED JUNE 3, 1991 a1 e,

DISTRIBUTION DOCKET File 50-244 0 NRC PDR LOCAL PDR PD I-3 Reading S.

Varga J.

Calvo R.

Messman A. Johnson M. Rushbrook A. Chu OGC 15B18 Dennis Hagan - MNBB 3206 G. 8ill (4) - 'Pl-37 E. Jordan -

MNBB 3701 B. Grimes - 9A2 Wanda Jones - MNBB 7103 C. Grimes - 11F3 ACRS (10)- P-315 GPA/PA -

2G5 OC/LFMB - MNBB 11104 J. Linville, Region I