ML17244A774
| ML17244A774 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/26/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17244A775 | List: |
| References | |
| NUDOCS 7908230072 | |
| Download: ML17244A774 (5) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
/
ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment tIo.
License No.
DPR-18 1.
The Nuclear'egulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated July 17, 1979 (transmitted by letter dated July 19, 1979),'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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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.
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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.
P g are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:JgL,>6 19 26 1979 FOR THE NUCLEAR REGULATORY COMMISSION 0<~~@ signed bY Dooms L Zaemann Dennis L. Ziemann, Chief Operating Reactors Branch 82 Division of Operating Reactors
ATTACHMENT TO LICENSE'AHENDHENT
-NO 2 8 PROYISIONAL 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 a vertical line indicating'the area of change.
~Pa e
3.15-1
O.
3.15 Ove ressure Protection S stem 1
8'1'pplies whenever the temperature of one or more of the RCS cold legs is
< 330'F.
Ob 'ctive To prevent. overpressurization of the reactor coolant system.
S ecification 3.15.1 Except during secondary side hydrostatic tests in which RCS pressure is to be raised above the PORV setpoint, at least one of the following )
overpressure protection systems"shall be operable:
r a.
Two pressurizer power operated relief valves (PORVs) with a lift, setting of < 435 psig, or b.
A reactor coolant system vent of > 1.1 square
~
inches.
3.15.1.1 3.15.1.2 3.15.1.3 With one. PORV inoperable, either restore the inoperable PORV to operable status within 7 days or depressurize and vent the RCS through a 1.1 square inch vent(s) within the next B hours; maintain the RCS in a vented condition until both PORVs have been restored to operable status.
With both PORVs inoperable, depressurize and vent the RCS through a 1.1 square inch vent(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored. to operable status.
Use of the overpressure protection system to mitigate a
RCS pressure transient shall be reported in accordance with 6.9.3.
Basis The operability of two pressurizer PORVs or an RCS vent opening of greater than 1.1 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are
< 330'F.
Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator
< 50'F above the RCS cold leg temperature or (2) the start of p safety injection pump and its injection into a water solid RCS.
References:
(1)
L. D. White, Jr. letter to A. Schwencer, NRC, dated July 29, 1977 3.15-1 Amendment No. gf 2 8