ML20079H071
| ML20079H071 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/30/1991 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079H076 | List: |
| References | |
| NUDOCS 9110100125 | |
| Download: ML20079H071 (5) | |
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UNITED STATES i-w g e,4 iV NUCLEAR e4GULATORY COMMISSION I
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l FLORIDA POWER CORPORATION CITY OF ALACHUA CTTV~0T~MI511Rrri CITY Or GAIntsVTELE
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CITY OF LEE 55UIT~
CITY Or NEW SMYRNA BEACH AND IITILITIES ClRRTISION, CITY Of NEW SMYRNA BEACH i
CITY OT OCALA ORLANDO UTILITIES EURRI5510N AND CITY OF ORLANDO 5TERING UTRITIE5'COMMI55 TON SENTNOLE ELECTRIC 000PrHTTVT INC.
CITY OF TALLAHA5stt DOCKET NO. 50-302
-f CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT r
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.137 License No. DPP-72 i
1.-
The Nuclear Regulatory Comission (the Comission) has found thatt A.
The application for amendment by Florida Power Corporation,- et al.
i (thelicensees)datedJune 20, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; D.
The facility will operate in conformity with the application, the provisions of the Act, and the rules _ and-regulations of the Comission; C.-
-Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 Comission's regulations; D.
-The issuance of tnis amendment will not be~ inimical to the comon defense and security or to the' health and safety of the publict and
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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.
9110100129 910?30 DR.ADOCK 0500 2
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. 2.
Accordingly, the license is amended by changes to the Techt.ical Specifications as indicated in the attachment to this license amendnent, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
i Technical Specifications
-The Technical Specifications contained in-Appendices A and B, as i
revised through Amendment No.137, are hereby incoraorated in the license. Florida Power Corporation shall operate tie facility in accordance with the Technical Specifications.-
1 3.
This license amendnent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j
R(rbertN.Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear heactor Regulation s
Attachment:
Changes to the Technical Specifications
.2 Date of 1ssuance: September 30, 1991 1
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uw w-ATTACHMENT TO LICENSE AMENDMENT NO.137 FACILITY OPERATING LICENSE NO. OPR-72
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DOCKET NO. 50 30P Replace the followino page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by anendment nunber and contains vertical lines indicating the area of change._ The corresponding overleaf page is also provided to maintain document completeness.
Remove Insert T[W3 T[W3
CONTAINMENT SYSTEMS 1 EYIILLANCE Rt0VIRfJiEH11_ R9atinued) b.
If any periodic Type A test fails to meet.75 La the test schedule fcr subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fall to meet.75 La a
Type A test shall be performed at least every 18 months until two consecutive Type A tests meet.75 La at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test whicht 1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La-2.
Had a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
5.
Req 91res the quantity of gas injerted into the containment or bled from the containment during the supplemental test to be equiv)1ent to at least 25 percent of the total measured leakage rate at 2 Pa, 53.3 psig.
d.
Type B at C tests shall be conducted with gas at 2 Pa, 53.3 psig at intervals no greater than 24
- months except for tests involving:
l 1.
Air locks, and 2.
Penetrations using continuous leakage monitoring systems.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
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- The 24 month interval may be extended until the end of Refuel 8 currently scheduled to start in April 30, 1992.
CRYSTAL RIVER UNIT 3 3/4 6 3 Amendment No.17E,137, 1
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Deleted.
g.
All test leakm;pe ntas shall be calculatM using ctearvui data ctmertad to absoluta values.
Error analyses shall be performed to select a balanand integrated leakage==trument syntan, t
IIB CRYSTAL RhER - UNIT 3 3/4 6-4 Amendment No.
JUN 2 21989 r
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