ML20236S538
| ML20236S538 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/20/1998 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236S542 | List: |
| References | |
| NUDOCS 9807270002 | |
| Download: ML20236S538 (6) | |
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NUCLEAR REGULATORY COMMIS810N p
WAsMINGTON, D.C. 300e54001 l
1 El ORIDA POWER CORPORATION CITY OF ALAQtiUA CITY OF BUSHNELL CITY OF GAINE3VILLE CITY OF KISSIMMEE CITY OF LEESE1)RG, CITY OF NEW SN,.6 CITY OF NEW SMYRIM BEACH CITY OF OCAlf ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO 1
SEMINOLE ELECTRIC COOPERATIVE. INC.
CITY OF TALLAHA!iSEE DOCKET NO. 50-202 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.168 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Pcwer Corporation, et al. (the licensees) dated March 20,1998, as supplerrented May 22,1998, 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 l
Act, and the rules and regulations of the Commission; C.-
There is reasonable assurance (i) that the activiiles authorized by this amendment can be conducted without endangering the hesith and safety of the public, and (ii) that such activities will be conduct $d in compliance with the Commission's regulations; D.
The issuance of this amendmant will not be inimicil 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 v rith 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9807270002 980720
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POR ADOCK 05000302 yi
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- 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-72 is hereby amended to read as follows:
1 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.168, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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f Frederick J. Hebdon, Director Project Directorate ll-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation l
Attacnment:
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Changes to the Technical Specifications Date ofissuance: July 20, 1998 l
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ATTACHMENT TO LICENSE AMENDMENT NO 16R FACILITY OPERATING LICENSE NO. L'?R-72 DOCKET NO. 50-302 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginallines indicating the areas of change.
REMOVE INSERT 2.0-2 2.0-2
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B2.0-11 B2.0-11 1
5.0-2 5.0-2 l
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SLs 2.0 1
2.0 SLs 1
2.2 SL Yiolations (continued) 2.2.3 In MODES 3, 4, and 5,-if SL 2.1.2 is violated, restore compliance within 5 minutes.
j 2.2.4 With any SL violation, within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.5 With any SL violation, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the appropriate
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Nuclear Operations senior management and the offsite reviewers l
specified in the Quality Assurance Plan.
2.2.6 With any SL violation, within 30 days, a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the offsite reviewer: specified in the
'uality Assurance Plan, the Director, Nuclear Plant Operations and the Chief Nuclear Officer.
l 2.2.7 With any SL violation, operation of the plant shall not be resumed until authorized by the NRC.
Crystal River Unit 3 2.0-2 Amendment No.168
B 2.1.2 BASES SAFETY LIMIT 2.2.6 VIOLATIONS (continued)
If the RCS pressure SL is violated, a Licensee Event Report shall be prepared and submitted within 30 days to the NRC in accordance with 10 CFR 50.73 (Ref. 9). A copy of the report shall also be provided to the NGRC, the Director, Nuclear Plant Operations, and the Chief Nuclear Officer.
l The 10 CFR 50.73 part against which a Safety Limit violation would be reported is:
- 1) completion of a plant shutdown required by Technical Specifications, (10 CFR 50.73(a)(2)(1)(A)), 2) an event which resulted in an j
unanalyzed condition that significantly compromised plant safety, (10 CFR 50.73(a)(2)(iv)).
l LL.1 If the RCS pressure SL is violated, operation of the plant shall not be resumed until authorized by the NRC. This requirement ensures the NRC that all necessary reviews, analyses, and actions are completed by establishing limitations on ascending MODES or other specified conditions in the Applicability until the NRC review is complete.
REFERENCES 1.
FSAR, Section 1.4.
2.
ASME Boiler and Pressure Vessel Code,Section III, Article NB-7000.
3.
ASME Boiler and Pressure Vessel Code,Section XI, Articles IWA-5000 and IWB-5000.
4.
BAW-10043, May 1972.
1 5.
FSAR, Section 14.
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6.
ASME USAS B31.7, Code for Pressure Piping, Nuclear Power Piping, February 1968 Draft Edition.
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l (continued) l Crystal River Unit 3 8 2.0-11 Amendment No.168 w-__
5 Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions responsible for activities affecting safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communications shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These shall be documented in the FSAR; b.
The Chief Nuclear Officer shall be an officer of the company and shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. The Chief Nuclear Officer shall be responsible for the overall safe operation of the plant and shall have control over those onsite activities necessary for the safe operation and maintenance of the plant; and c.
The individuals who train the operating staff, carry out health physics or perform quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Unit Staff I
The unit staff organization shall include the following:
a.
One auxiliary nuclear operator shall be assigned to the operating shift any time there is fuel in the reactor and l
(continued)
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Crystal River Unit 3 5.0-2 Amendment No.168 l
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