ML17264B090
| ML17264B090 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/29/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264B091 | List: |
| References | |
| NUDOCS 9711130381 | |
| Download: ML17264B090 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 ROCHESTER GAS AND E ECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
68 License No.
DPR-18 The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
B.
C.
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated August 19,
- 1997, as supplemented September 29,
- 1997, 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 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 will be conducted in compliance with the Commission's regulations; 2.
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.
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 Facility Operating License No.
DPR-18 is hereby amended to read as follows:
97iii3038i 97i029 POR ADOCK 05000244 P.
POR j
3.
(2)
Technical S eci ications The Technical Specifications contained in Appendix A, as revised through Amendment No.
68
, 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
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 29, 1997 S. Singh Bajwa, Director Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO.
68 FACILITY OPERATING 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 3.6-18 Insert 3.6-18 B 3.6-53a
CS, CR
- NaOH, and Containment Post-Ac ent Charcoal Systems 3.6.6 3.6 CONTAINMENT SYSTEHS 3.6.6 Containment Spray (CS), Containment Recirculation Fan Cooler (CRFC),
- NaOH, and Containment Post-Accident Charcoal Systems LCO 3.6.6 Two CS trains, four CRFC units, two post-accident charcoal filter trains, and the NaOH system shall be OPERABLE.
NOTE In HODE 4, both CS pumps may be in pull-stop for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of interlock and valve testing of motor operated valves (HOVs) 857A, 857B, and 857C.
Power may also be restored to MOVs 896A and 896B, and the valves placed in the closed position, for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the purpose of each test.
APPLICABILITY:
MODES I, 2, 3, and 4.
ACTIONS CONDITION RE(VIREO ACTION COMPLETION TIME A.
One CS train inoperable.
A.l.
Restore CS train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
One post-accident charcoal filter train inoperable.
B:I Restore post-accident charcoal filter to OPERABLE status.
7 days C.
Two post-accident charcoal filter trains inoperable.
C.1 Restore one post-accident charcoal filter train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D.
NaOH system inoperable.
D.l Restore NaOH System to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> R.E.
Ginna Nuclear Power Plant
.3.6-18 Amendment No. Pf
~
68
CS, C
- NaOH, and Containment Post-Ac dent Charcoal Systems B 3.6.6 BASES
- LCO, (continued)
The LCO is modified by a Note which states that in MODE 4, both CS pumps may be placed in pull-stop, with power restored to motor operated valves 896A and 896B and the valves placed in the closed position for interlock and valve testing of motor operated valves 857A, 857B, and 857C.
This Note provides 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for each test of each motor operated valve 857A, 857B, and 857C.
The Note is required 'since the installed interlocks on 857A, 857B, and 857C require closure of valves 896A and 896B while other valve testing (e.g.,
differential pressure tests) require a pressurized RHR system.
Performance of these tests in MODEs 5 and 6 would render the RHR system inoperable when it is required for core cooling.
R.E.
Ginna Nuclear Power Plant B 3.6-53a (continued)
Amendment No. 68