ML17264A784
| ML17264A784 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/09/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264A785 | List: |
| References | |
| NUDOCS 9701150247 | |
| Download: ML17264A784 (5) | |
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UNITED STATES UCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20844001 OCH STER GAS AND LECTRIC CORPORATION IL0DET 0-44 G NNA NUC AR OWE P A ENDMENT 0 FACILITY OPERATING LICENSE I
Amendment No.67 I
License No.
DPR-18 The Nuclear R gulatory Commission (the Commission or the NRC) has found that:
A.
The appli,cation for amendment filed by the Rochester Gas and Electric 'Corporation (the licensee) dated October 29,
- 1996, 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; 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; 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 2.
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; 970fiS0247 970i09 PDR ADOCK 05000244 1(
P PDR
3.
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
67
, 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 Q$
c'~ P""
S. Singh Bajwa, Acting Director Project Directorate I-l Division of Reactor Projects I/II Office of. Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 9, 1997
TTACHHENT TO LICENSE AHENDHENT NO. 67 ACILIT 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.
emove 3.3-20 3 ~ 3 27
~Isert 3.3-20 3 ~ 3 27
ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.2-1.
ACTIONS
-NOTE-Separate Condition entry is allowed for each Function, CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more Functions with one channel or train inoperable.
A.I Enter the Condition referenced in Table 3.3.2-1 for the channel or train.
Immediately B.
As required by Required Action A. I and referenced by Table 3.3.2-1.
B. I Restore channel to OPERABLE status.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> C.
Required Action and associated Completion Time of Condition B
not met.
C.l Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (continued R.E. Ginna Nuclear Power Plant 3.3-20 Amendment No. g67
+ I ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)
Engfneered Safety Feature Actwtfon SystI% Instrwentatfon FNICTION APPLICAQLE NLXIES OR OTHER SPECIF IEO C(NOITIONS REGUIRED CHANNELS SLNLVEILLANCE COOITINIS RECAJ IRE%NTS ALLOQSLE VALlK TRIP SETPOINT 5.
Feecheter lsolat fon
~.
Autistic Actwtfon Logfc
~nd Actwtton Relays b.
SG Mater Level -High 1~2(c) 3(c) 2-trains E,G SR 3.3.2.7 1~2(c) 3(c) 3 per SG F,G SR 3.3.2.1 s 94X SR 3.3.2.2 SR 3.3.2.5
~
s II5X c.
Safety lnjectfon 'efer to FIsIctfon 1 (Safety lnjectton) for all fnfttatfon I
fIsIctfons and requireeents.
I=
6.
Auxil fary FeechuIter (AFW) a.
Nanual Initiation AFM StaIxRIy AFM 1,2,3 1,2,3 1 per fxslP 1 per IxsIP N
SR 3.3.2.4 KA NA NA b.
Autoaat fc Actuation Logfc and Actwtfon Relays 1,2,3 2 trains E,G SR 3.3'.7 KA c.
SG Mater Level -Lou Lou 1,2,3 3 per SG D,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 b 16X R 17X d.
Safety Injection (Notor driven pwps only)
Refer to FIxIction 1 (Safety Injection) for atl initiation fIsIctfons and requfreaents.
e.
Undervot tage -Bus 11A and 118 (Turbine driven puap only) 1,2,3 2
pcl'us D,G SR3323 R245OV i257gV Mfth s 3.6 ufth s 3.6 sec tfee sec tfIse delay delay
-f.
Trip of goth Nein Feedwter Pumps (Notor driven pwps only) 2 per NFV puap 4,C SR 3.3.2 4 (c)
Except uhen all Nafn FeedIIatel Regutating and associated bypass valves are closed and de-activated or fsoLated by a closed sslwIL valve.
R.E. Ginna Nuclear Power Plant 3.3-27 Amendment No. Pg, Pg,N,67