ML19320B262
| ML19320B262 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/18/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19320B258 | List: |
| References | |
| TAC-13056, NUDOCS 8007100115 | |
| Download: ML19320B262 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION aj WASHINGTON, D. C. 20555 t,, (,, j/
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FLORIDA POWER CORPORATION CITY OF ALACHUA flTY OF BUSHNEi.L 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 SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. DPR-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated November 21, 1977, as revised and supplemented February 15, 1980, and May 14, 1980, complies with the standards and requirements of the Atomic Cnergy Act of 1954, as amended (the Act) and the Comission'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 and safety
- f 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 comon 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 Comission'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. OpR-72 is hereby amended to read as follows:
(2). Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 31, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 18, 1980 O
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ATTACHMENT TO LICENSE AMENDMENT NO.31' FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following page of Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
3/4 6-9 i
CRYSTAL RIVER - UNIT 3 i
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Removing one wire or strand from each of a dome, vertical and hoop tendon checked for lift off force and determining that over the entire length of the removed wire or strand that:
1.
The tendon wires or strands are free of corrosion, cracks and damage, 2.
There are no changes in the presence or physical appearance of the sheathing filler grease, and 3.
A minimum tensile strength value of 240,000 psi (guaranteed ultimate strength of the tendon material) for at least three wire or strand samples (one from each end and one at mid-length) cut from each removed wire or strand.
Failure of any one of the wire or strand samples to meet the minimum tensile strength tests is evidence of abnormal oegradation of the coStainment structure.
1l 4.6.1.6.2 End Anchoraoes and Adjacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to Speci-fication 4.6.1.6.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete crack patterns adjacent to the end anchorages.
4.6.1.b.3 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during the shutdown for each Type A containment leakage rate test (Specification 4.6.1.2) by a visual e inspection of these surfaces.
This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance or other abnormal degradation.
4.5.1.6.4 Containment Dome The containment dome's structural integrity shall be demonstrated at the end of 1 year,18 months, 2 years, 3 years, 40 110 months (coincident with the first periodic integrated containment leak rate test), and 5 years following the initial containment structural integrity test. The dome's structural integrity,shall be demonstrated by:
CRYSTAL RIVER - UNIT 3 3/4 6-9 Amendment No. 2.4, 31 6
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CONTAINMENT SYSTEMS SURVEILLANCEREQUIREMENTS(Continued) a.
Measuring the elevation difference of 7 dome survey points (1 at the apex; 3 at a radius of =29 feet at azimuths 90', 215' and 334*; and 3 at a radius of =49 fest at azimuths 90', 215' and 334') and 3 benchmarks (on Ring Girder at azimuths 90*,
215* and 334') along the respective azimuths. These elevation differences shall be compared to the elevation differences established by the Baseline Survey.
If the containment is in a normal operation / shutdown mode, the acceptable change in elevation differences will be based on consideration of expected movement and survey accuracy-couoled with an acceptable strain level for the radial reinforcement.
Changes of a greater sagnitude shall require en engineering evaluation.
If the containment is in a pressurized mode for a periodic containment integrated leak rate test, the acceptable changes in elevation differences ~ will Ee similar to that for the initial containment structural integrity test applied to the elevation differences during the periodic containment integrated leak rate test.
B.
Measuring crack ~ widths and. plotting crack patterns in the area of the dome 3 feet on either side of azimuths 195* from the apex to the Ring Girder.
Cracks wider than 0.010 inches will be plotted and cracks wider than 0.040 inches shall require an engineering evaluation.
In addition, a general visual inspection of the entire dome surface area shall be performed.
4.6.1.6.5~ Reports Any abnormal degradation of the containment structure detected during the above required tests and inspections shall be reported to the Comnission pursuant to specification 6.9.1.
This report shall include a description of the tendon. condition, the condition of the concrete (especiallyattendonanchorages),theinspectionprocedures, the tolerances on cracking, and the corrective' actions taken.
r-l CRYSTAL RIVER - UNIT 3 3/4 6-9a Amendment No. Z(, 29
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