ML17265A364
| ML17265A364 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/14/1998 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17265A365 | List: |
| References | |
| NUDOCS 9807210349 | |
| Download: ML17265A364 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.
7~
Ucense No. DPR-18 The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated September 29, 1997, as supplemented February 6, 1998, April 17, 1998, and June 4, 1998, 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 facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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.
Accordingly, the license is amended by changes to the Technical SpeciTications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-18 is hereby amended to read as follows:
98072i0349 9B07i4 PDR ADOCK 05000244 P
PDR 2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENTTO LICENSE AMENDMENTNO. 71 FACILITYOPERATING LICENSE NO. DPR-18 DOCKET NO. 50-244 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove 3.3-26 Insert 3.3-26
0 4 ~
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 3)
Engineered Safety Feature Actuation System Instruaentation FUHCTIOH APPLICABLE HODES OR OTHER SPECIFIED COHD I7 IOHS REQUIRED CHAHHELS SURVEILLAHCE COHDITIOHS REQUIREHEHTS ALLOJABLE VALUE TR IP SETPOIHT
- 4. Steam Line Isolation a.
Hanual Initiation
- b. Automatic Actuation Logic and Actuation Relays 1 2(b) 3(b)
(b) 3(b) 1 per loop 2 trains D,G SR 3.3.2.4 E,G SR 3.3.2.7 HA HA HA HA
- c. Contairgent Pressure High High 2(b) 3(b)
F,G SR 3.3.F 1
< 20 psig SR 3.3.2.2 SR 3.3.2.5
< 18 psig
- d. High Steam Flow 2(b) 3(b) 2 per steam line F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 S 0.66E6 ibm/hr g 1005 psig
< 0.4E6 ibm/hr 9 1005 psig Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
Coincident with T
Low 1,2(
) 3( )
2 per loop F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5
> 543'F
> 545'F
- e. High-High Steam Flow 1,2( <<,3(
)
2 per steam line F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5
< 3.7E6 ibm/hr 9 755 psig
< 3.6E6 ibm/hr 9 755 psig Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(b)
Except when both HSIVs are closed and de-activated.
(cont>nue
)
R.E.
Ginna Nuclear Power Plant 3.3-26 Amendment No. g 71