ML14183A116
| ML14183A116 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/28/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A117 | List: |
| References | |
| DPR-23-A-117 NUDOCS 8805170038 | |
| Download: ML14183A116 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO.
50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.
2 AMENDMENT TO FACILITY OPERATTNG LICENSE Amendment No. 117 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power & Light Company (the licensee), dated January 20, 1988, 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 1; B. 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 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:
8805170038 880428 PDR ADOCK 05000261!
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-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 117, are hereby incorporated in the license. Carolina Power-&
Light Company 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 Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/Il
Attachment:
Changes to the Technical Specifications Date of Issuance: April 28, 1988 OFFICIAL RECORD COPY OFC
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ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages, as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 6.5-7 6.5-7 6.7-1 6.7-1
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
a)
The provisions of 10 CFR 50.72 shall be complied with.
b)
The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with.
c)
The safety limit violation shall be reported to the NRC Region II within one hour and the Vice President -
Robinson Nuclear Project and the Manager -
Corporate Nuclear Safety Section within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d)
A Safety Limit Report shall be prepared. The report shall be reviewed in accordance with Specification 6.5.1.6.6. This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems, or structures; and (3) corrective action taken to prevent recurrence.
e)
The Safety -Limit Violation Report shall be submitted to the NRC, Vice President - Robinson Nuclear Project, and the Manager -
Corporate Nuclear Safety Section with 14 days of the violation.
6.7-1 Amendment No. 89 117
6.5.1.6.5 A quorum of the PNSC shall consist of the Chairman, and four members, of which two may be alternates.
6.5.1.6.6 The PNSC activities shall include the following:
a)
Perform an overview of Specifications 6.5.1.1 and 6.5.1.2 to assure that processes are effectively maintained.
b)
Performance of special reviews, investigations, and reports thereon requested by the Manager -
Corporate Nuclear Safety.
c)
Annual review of the Security Plan and Emergency Plan.
d)
Perform reviews of Specifications 6.5.1.1.6, 6.5.1.2.4, 6.5.1.3.1, and 6.5.1.4.1.
e)
Perform review of all reportable events.
f)
Review of facility operations to detect potential nuclear safety hazards.
g)
Review of every unplanned on site release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrences to the Vice President - Robinson Nuclear Project, Manager - Corporate Nuclear Safety, and the Manager - Corporate Quality Assurance.
h)
Review of changes to the Process Control Program and the Offaite Dose Calculation Manual.
i)
Review of major changes to radioactive liquid, gaseous, and solid waste treatment systems.
6.5-7 Amendment No. S, OJ, 117