ML17258B178
| ML17258B178 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/30/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17258B179 | List: |
| References | |
| NUDOCS 8107130234 | |
| Download: ML17258B178 (8) | |
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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 No. 44 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Rochester Gas and Electric Company (the licensee) dated May 26, 1981 (transmitted by letter dated May 29, 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; 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 com-pliance 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 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. 44, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 30, 1981 Dennis M. Crutc field, ief Operating Reactors Branch 85 Division of Licensing
ATTACHMENT TO LICENSE.AMENDMENT NO. 44 PROVISIONAL OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages contain the captioned amendment number and marginal lines which indicate the area of changes.
REMOVE 3.13-4 3.13~5 3,13-6 INSERT 3.13-4 3.13-5 3.13-6 3.13-7
Table 3.13-1 (Continued)
Safety Related Shock Suppressors (Snubbers)
Snubber ltark No.
Accessibl.e or Inaccessible (A or I)
Iligh Radiation**
Zone I:specially llifficultto Remove AF['J-25 IIAII Aux. Feedwater No AFI'r-26 AFil-27 lip II Ilq II I
Aux. Peedwater Aux. Peedwater Uo No No O
AFL'1-20 IIAII Aux.
Peedvra ter Ho No.
APH-29 "A".Aux. Feedwater No Ho AP"I-31 "A" Aux. Feedwater Uo No APT'l-49 Pitr-30 llp II Aux. Feedcrater Peedsrater No No No I
No P'l-80 "B" Peedlrater No FH-01 FH-82 IID II IIg II Peedwater Feedwater No No No No kk'
Table 3.13-1 (Continued)
Safet Related Shock Suppressors (Snubbers)
Snubber Mark No.
Pi inq S stem Accessible or Inaccessible (A or I)
Especially Hiqh Radiation** Difficultto
'l.one Remove Fll-03 AFN-10 AF'~-13 "B" Feedwater "B" Aux. Feedvater "B" Aux. Feedwater No h7o h7o
'.:7o No "7o Sh7B-265 Stm to TD Aux. Feedczater No No MS-22 IIAll Main Steam No No MS-8 I
hlS-146 (Top)
MS-146 (Bottom)
I "B" h!ain Steam IIB II Main Steam "B" Hain Steam No No Yes No No
Table 3.13-1 (Continued)
Safet Related Shock Su pressors (Snubbers)
Snubber Hark No.
h1G-147 "B" Hain Steam Accessible or Inaccessible (A or I) n No hIo Especially High Radiation** Difficult to Zone Remove
~
MS-148 4) 4J cn HS-159 I
hIS-160 H-1 H-2 "B" hta in Steam "8" h'ain Steam PROB Relief "D" Hain Steam PRZR Relief No No No Yes No No No hEo No H-3 PRZR Relief Yes No II-4 H-5 EI-6 H-7 H-8 PRZR Relief PRZR Relief PRZR Relief PPZR Relief PPZR Relief Yes Yes Yes Yes No No No No
O Table 3.13-1 (Continued)
Safet Related Shock Suppressors (Snubbers)
Snubber Hark No.
pipjnq S stem Accessible or Inaccessible (A or I)
Especially Ifigh Radiation** Difficultto Zone Remove PS-2 PS-4 PS-5 PS-6 PS-0 PS-"9 PS-10 PS-11 PRZR Safety 6 Relief Valve PRZR Safety 6 Relief Valve PPZR Safety 6 Relief Valve PRZR Safety 6 Relief Valve PP.
R Safety f Relief. Valve PRZR."..afety 6 Relief Valve PRZR Safety R Relief Valve PRZR Safety S Relief Valve Yes Yes Yes Yes Yes Yes Yes No No No Nn No No No ISnubbers may be added to or removed from safety related systems without prior License l
Amendment to Table 3.13-1 provided that a proposed revision to Table 3 '3-1 is included
'with the next License Amendment request.
IModifications to this table due to changes in high radiation areas (during shutdown) shall be submitted to the NRC as part of the next. License Amendment request.