ML20040C103
| ML20040C103 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/07/1982 |
| 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 | |
| ML20040C104 | List: |
| References | |
| TAC 47352, TAC 47353, DPR-72-A-049 NUDOCS 8201270272 | |
| Download: ML20040C103 (5) | |
Text
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[pa Mot,q#e, UNITED STATES 8" 3
'i NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D. C. 20666 s
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FLORIDA POWER CORPORATION CITY OF ALACHUA C_ITY 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 t
I 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. 49 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Comissiol.) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated November 17, 1981, complies with f
the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954,
, 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 trie rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without erdangering 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 Comission's regulations and all applicable requirements have been satisfied, k
8201270272 820107 hDRADOCK 05000302 PDR
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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 o
The Technical Specifications contained in Appendices A ared B, as revised through Amendment No. 49, are j
hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
'l 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (L
J hn F. Stolz, Chief 0 erating Reactors Branch #4
' division of Licensing j
Attachment:
Changes to the Technical Specifications Date of Issuance: January 7,1982
i ATTACHMENT TO LICENSE AMENDMENT NO. 49 I
FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302 o
Replace the following page of Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendnent l
number and contains a vertical line indicating the area of change.
The corresponding overleaf page is also pmvided to maintain document completeness.
3/4 7-35 t
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TABLE 4.7-4 HYDRAULIC SNUBBER INSPECTION SCHEDULE E
NUMBER OF SNUBBERS FOUND INOPERABLE NEXT REQUIRED i
DURING INSPECTION OR DURING INSPECTION INTERVAL
- INSPECTION INTER'!AL**
E 0
18 months + 25" 1
12 months T 25%
2 6 months T 25%
3 or 4 124 days T 25%
5, 6. or 7
$2 days T 25%
>8 31 days T 25%
M b
Y W
T g
Snubbers may be categorized into two groups, " accessible" and " inaccessible". This categorization shall -
ti based upon the snubber's accessibility for inspection during reactor operation. These tw groups g
may be inspected independently according to the above schedule.
.E The required inspection interval shall not be lengthened more than one step at a time. Following the 1981 refueling outage, the required inspection interval for snubbers inside containment is 12 months + 25%.
=
Subsequent intervals shall be determined by the above Table.
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PLANT SYSTEMS 3/4.7.10 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.10.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 micro-curies of removable contamination.
APPLIL.1BILITY: At all times.
ACTIUJ:
a.
Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.10.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Comniission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7.10.1.2 Test Frequencies - Each category of sealed sources shall be tested at the frequency described below, a.
Sources in use (excluding startup sources and fission detectors previously subjected to core flux) - At least once per six months for all sealed sources containing radioactive material:
CRYSTAL RIVER - UNIT 3 3/4 7-36
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