ML20213F807
| ML20213F807 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/07/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Florida Power Corp, City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, Utilities Commission, City of New Smyrna Beach, FL, City of Ocala, FL, City of Orlando, FL, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative, City of Tallahassee, FL |
| Shared Package | |
| ML20213F809 | List: |
| References | |
| DPR-72-A-094 NUDOCS 8611170191 | |
| Download: ML20213F807 (4) | |
Text
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[s@ Kt Ggs, UNITED STATES o
8 NUCLEAR REGULATORY COMMISSION
~~ o WASHINGTON, D. C. 20555 E
tg.....,o FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET N0. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE ~
Amendment No. 94 License No. DPR-72 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated August 14, 1986, as supplemented October 6, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1986, complies with the standards gnd re, 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 rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health a;id 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.
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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 paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised tnrough Amendment No. 94, 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.
F THE NUCLEAR REG ATORY COMMISSION h
F. Stolz, Direct W Project Directorate #6 vision of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7,1986 55 O
t
l ATTACHMENT TO LICENSE AMENDMENT N0. 94 FACILITY O'ERATING LICENSE NO. OPR-72 P
DOCKET NO. 50-302 Replace the followina page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain documen,t, completeness.
Remove Insert 3/4 4-32 3/4 4-32 J
s I
REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.
APPLICABILITY: All MODES.
ACTION:
With the structural integrity of any ASME Code Class 1 component (s) a.
not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolarit System temperature more than 50*F above the minimum temperature required by NDT considerations.
b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 F.
With the structural integrity of any ASME Code Class 3 compone.nt(s) c.
not conforming to the above requirements, restore the structural integrity of the component (s) to within its limit or isolate the affected component (s) from service.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5:
The reactor coolant pump flywheels shall be inspected per the a.
recommendations of Regulatory Position C.4.b. of Regulatory Guide 1.14, Revision 1 August 1975.
CRYSTAL RIVER - UNIT 3 3/4 4-31 Amendment No. 24
1 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.
Each internals vent valve shall be demonstrated OPERABLE at least once per 18 months during shutdown *, by:
l 1.
Verifying through visual inspection that the valve body and valve disc exhibit no abnormal degradation, 2.
Verifying the valve is not stuck in an open position, and 3.
Verifying through manual actuation that the valve is fully open with a force of < 425 lbs (applied vertically upward).
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a
- For fuel Cycle 6 only, the surveillance may be performed at the next refueling outage, but no later than January 1988.
CRYSTAL RIVER - UNIT 3 3/4 4-32 AmendmentNo.19,jh4f94
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