ML17258A509
| ML17258A509 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/13/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17258A508 | List: |
| References | |
| NUDOCS 8202080547 | |
| Download: ML17258A509 (4) | |
Text
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UNITED STATES.
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 No.
47 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) has found that::
A.
The application for amendment by Rochester Gas and Electric Company (the licensee) transmitted by letter dated December 11, 1981, 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 con'formity with the application, the provisions of the Act, and the rules and regulations'of the Commission; C.
D.
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 publi'c; 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 satisfi.ed.
8202080547 820ii3 PDR ADOCK OSQ00244 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment
.to this license amendment and by changing Paragraph 2.C(2) of Provisional Operating License No.
DPR-18 to read as follows:
'2)
'Technical.S ecifications The Technical Specifications contained in Appendix A, as
~
revised through Amendment No. '47, are hereby incorporated in the li.cense.
The licensee shall operate the facil.ity in accordance with the Technical Specifications.
3.
This license amendment is effective 'as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to,the Technical Specifications Date of Issuance:
January 13, 1982 Dennis M. Crutchfield, ief Operating Reactors Branch 85 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO:
47 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
- c'aptioned amendment number and marginal lines which indicate the area of change.
PAGE 3.5-12'
TABLE 3.5-5 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM.INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT 1.
SAFETY INJECTION AND FEEDNATER ISOLATION a.
Manual Initiation b.
High Containment Pressure c.
Low Pressurizer Pressure d.
Low Steam Line Pressure 1
. 2.
Manual Initiation High-High Containment Pressure 3.
CONTAINMENT ISOLATION a.
Containment Isolation 1.
Manual 2.
From Safety Injection Automatic Actuation Logic b.
Containment Ventilation Isolation 1.
Manual 2.
High Containment Radioactivity 3.
From Safety Injection 4.
Manual Spray TRIP SETPOINT Not Applicable
< 4.0 psig 1723 psig 514 psig Not Applicable
< 28 psig Not Applicable Not Applicable Not Applicable Note 3
Not Applicable Not Applicable ALLONABLE VALUES*
.Not Applicable
< 5.0 psig 1715 psig
> 500 psig
..Not Applicable
< 30 psig Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable