ML14175A871
| ML14175A871 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/17/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A872 | List: |
| References | |
| DPR-23-A-092 NUDOCS 8506050402 | |
| Download: ML14175A871 (6) | |
Text
- RPEG UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMIENDtMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power and Light Company (the licensee) dated December 10, 1984, 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 conformity with the application, the provisions of the Act, and the ru-les 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 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.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-23 is hereby amended to read as follows:
0402%~
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-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.92, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION teven A.
arg a V Operating Reactors anch #1 Division of Licens n
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 17, 1985
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
92 FACILITY OPERATING LICENSE NO.
DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 6.2-4 6.2-4 6.4-1 6.4-1 6.5-6 6.5-6
M A N A G E 1H no0n I H SO0 N NIJ C1.
E AR PROJEC T MANAGER MANAGER MANAGE:?
MANAGEn CONTROL &
PROJECT GENERAL pLANNING ADMINISIRATION CONSIIUCTION GINEERIN SCHEDIJLING ADMINISTRATIVE
-CHMSR O A BTENANC E PRONEIATIONSSOECNRICALINEE PORT ENVIRONMEN TAL A
SUPERVISOR 1SUPERIVISORS OPERATIONS 1 SUPERVISORS CUPEMISR
_____________UNIT_012
_________________J___J S
PR IO EMERGENCY 1SHIFT ENGINEER
- 1.
RADIATION CONTROLJ PREPAREDNESS ](STA)
JSUPERV I RE PROTECTION SECURITY
]SPECIALIST OPERATING PE OC GSUPERVISOR SRO Sonior Reactor operator License UNIT #62 SR CO -
Ractor Operator LlconsSlJLG DM SHIFT FOREMAN SROl 3 CONTROL OPERATORS RO(2)/SO(I)
AD S DITIONAL SHIFT MEMBERS H.S.RROBINSON UNIT O2 Carolina 'owe
& L~ight"illopan FINAL SAFETY ANALYSIS REOORT FACILITY ORGAAIZATION 6.2-4 Amendment No.
92 H
ROUINSON NUCLEAR PIOJEC Figure 6.2-2
-HBR-15) 6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant and C&A staff shall be maintained under the direction of the Director - Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the dire::ion of the Manager -
Operations and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except that training sessions shall be conducted at least quarterly.
6.4-1 Amendment No. 92
(HBR-15) 6.5.1.6 Plant Nuclear Safety Committee (PNSC) 6.5.1.6.1
- a. As an effective means for the regular overview, evaluation, and maintenance of plant operational safety, a Plant Nuclear Safety Committee (PNSC) is established.
- b. The committee shall function, through the utilization of subcommittees, audits, investigations, reports, and/or performance of reviews as a group, to advise the General Manacer of all matters related to nuclear safety.
6.5.1. 6. 2 The PNSC shall be composed of the following:
Chairman -
General anager or designated alternate Member -
Manager -
Operations or designated alternate Member
- Manager -
Maintenance or designated alternate Member -
Manager -
Technical Support or designated alternate Member - Director
- Regulatory Compliance or designated alternate Member -
Manager Environmental & Radiation Control or casignated alternate Member -
Director QA/QC or designated alternate 6.5.1.6.3 Alternates shall be appointed in writing by the General Manager or serve on a temporarv basis.
All aLternates shall, as a minimum, meet qualiFication criteria specified in Section 4.4 of ANSI N18.1-1971 for professional-technical personnel, or for those disciplines not listed in Section 4.4, the equivalent of the Section 4.4 requirement.
6.5.1.6.4 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate.
6.5-6 Amendment No.
92