ML19344D546
| ML19344D546 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/03/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19344D547 | List: |
| References | |
| TAC-13056, NUDOCS 8004250008 | |
| Download: ML19344D546 (7) | |
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UNITED STATES
.,i NUCLEAR REGULATORY COMMISSION i Th) e.
3 WASHINGTON. D. C. 20555
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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 SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated November 21, 1977 as revised February 15, 1980, 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; 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 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.
8004250O@h
. 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:
1 (2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No 29,are hereby incorporated in the license.
F1r;ida 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
//
s Robert W. peid, Chief Operating Reactors Branch 34 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 3,1980 t
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ATTACP. MENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Paaes 3/4 6-8 3/4 6-9a t
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CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION I
3.6.1.5 Primary containment average air temperature shall not exceed 130 F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With the containment average air temperature > 130 F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures at,the following locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
I Location a.
Column RB-320, elevation 100' b.
Column RB-320, elevation 125' c.
Outside secondary; shield wall, elevation 180' d.
Crane access platform, elevation 235' i
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l CRYSTAL RIVER - UNIT,3 3/4 6-7 1
t-
CONTAINMENT SYSTEMS
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CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION 3.6.1.6 The structural integrity of.the containment shall be maintained at a level consistent with. the acceptance criteria in Specification 4.6.1.6.
APPLICABIl.ITY:
MODES 1, 2, 3 and 4.
ACTION:
With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Tendons The containment tendons' structural integrity shall be demonstrated at the end of one, three and five years following the initial containment structural integrity test and at five year intervals thereafter.
The tendons' structural integrity shall be demonstrated by:
Determining that a representative sample
- of at least 21 tendons a.
(5 dome, 6 vertical, and 10 hoop) each have a lif t off force vf between 1,249,000 (minimum) and 1,721,000 (maximum) pounds.
This test shall include an unloading cycle in which one of the tendons from each group (dome, vertical and hoop) is detensioned to determine if any wires or strands are broken or damaged.
If the lift off force of any one tendon in the total sample population is out of the predicted bounds (less than minimum or greater than maximum), an adjacent tendon on each side of the defective tendon shall also be checked for lift off force.
If both of these tendons are found acceptable, the surveillance program may proceed considering the single deficiency as unique and accep'.able.
More than one defective tendon out of the original sample population is evidence of abnonnal degradation of the containment structure.
Unless there is evidence of abnormal degradation of the contain-I ment structure during the first three tests of the tendons, the l
number of tendons checked for lift off force during subsequent tests may be reduced to a representative sample of at least 11 tendons (3 dome, 3 vertical and 5 hoop).
- For each inspection,'the tendons shall be selected on a random but t
representative basis so that the sample group will change somewhat for each inspection; however, to develop a history of tendon perfonnance and to correlate the observed data, one tendon from each group (dome, vertical, and hoop) may be kept unchanged af ter the initial selection.
CRYSTAL RIVER - UNIT 63 3/4 6-8 Amendment No. H, 29
CONTAINMENT SYSTEMS t
SURVEILLANCE REQUIREMENTS (Continued) i b.
Removing one wire or strand from each of a dome, vertical and l
hoop tendon checked for lift off force and determining that over the entire length of the removed wire or strand that:
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The tendon wires or strands are free of corrosion, cracks l
and damage, 2.
There are no changes in the presence or physical appearance I
of the sheathing filler grease, and 3.
A minimum tensile strength value of 240,000 psi (guaranteed l ultimate strength of the tendon material) for at least three
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wire or strand samples (one from each end and one at mid-length) cut from each removed wire or strand. Failure of an one of the wire or strand samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.
4.6.1.6.2 End Anchorages 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.
Inspections of the concrete shall be performed during the Type A containment leakage rate tests (Specifica-tion 4.6.1.2) while tha containment is at'its maximum test pressure.
4.6.1.6.3 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 inspection of these surfaces. This inspection shall be perfonned 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 r.tructural integrity shall be demonstrated at the end of 1 year,18 months, 2 years, 3 years, 40
+10 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. 24
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Contittued) l 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 feet 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 I-a nomal operation / shutdown mode, the acceptable change in elevation differences will be based on consideration of expected
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movement and survey accuracy coupled with an acceptable strain level for the radial reinforcement.
Changes of a greater magnitude shall require an 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 be similar to that for the initial containment structural integrity test applied to the elevation differ 5nces 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 perfomed.
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 Comission pursuant to specification 6.9.1.
This report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective actions taken.
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CRYSTAL RIVER - UNIT 3 3/4 6-9a Amendment No. U, 29