ML20033F352
| ML20033F352 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/13/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033F353 | List: |
| References | |
| NUDOCS 9003200128 | |
| Download: ML20033F352 (6) | |
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NUCLEAR REGULATORY COMMISSION
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I FLORIDA POWER CORPORATION l
CITY OF ALACHJA ClTY OF EU5hNE Cl"Y OF GAINE5v
.LE CITY OF KISSIM ;E C..T Y OF L E.;55URIs CITY OF NEW SMYRNA BEACH AflD U"ILITII;5 C0mISS10t! CITY OF NEW SMYRNA BEACH 0ii) QF QLA.A CRLANDO UTILITIES C0WI55 ION AND CITY OF ORLANDO SEEFII,0 UTILITIES COMISSION SEM1tl0LE ELECTRIC COOPERAT IVE. INC.
_ CITY OF TALLAHASSEE DOCKET NO. 50 302 CRYSTAL RIVER UflIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO F ACILITY OPERAT1HG LICENSE t
Amenenent No.126 License No. DPR-72 1.
The !luclear Regulatory Commission (the Commission) has found that:
A.
The application for anendnent by Florida Power Corporation, et al.
(the licensees) dated December 21, 1969, complies with the standards and requirenants of the Atomic Energy Act of 1954, as amended (the Act),6nd 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 (1) that the activities authorized by this anwnanent can be conductea without endangering the health and safety of the public, and (ii) that such activities will be conaucted in conpliance with the Comission's regulations; D.
The issuance of this amendnent 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 amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requiraments have been satisfied, m
90032
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^1 2.
Accordingly, the license is anended by ch6nges to '.4 lachnical yecifications as indicated in the attachraent to t.'is 'sicense aandnent,
'and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hemby
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annoed to read a5 follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendnent No.126 are hereby incorporated in the license.
Florida Power Corporation shall opsrate the facility in ac:ordance with the Technical Specifications..
3 3.
This license amendnent is effective as of. its date of issuance and shall be iniplenented within 30 days of issuance.
5 FOR THE NUCLEAR REGULATOP,Y COMMISSION l
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Herbert H. Berkow, Dimctor 3
Project Directorate 11-2 j
Division of Reactor Projects - I/II
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Office of i4Jclear Reactor Fagulation
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Attachnent:
Changes to the Technical Specifica tions j
Date of Issuante: March 13,1990
ATTACRMENT TO LICENSE AMENDMENT NO.126 FACILITY OPERATING LICENSE NO. DPR-72 00CKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendnent number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 6-19 6-19 6-20 6-20 L
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ADMINISTRATIVE CONTROLS e.- Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7.-l.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of inservice inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities required by the QA Manual.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of tists and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PRC and NGRC.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
Records of analytical results required by the Operational Radiological m.
Environmental Monitoring Program.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph l
20.203(c) (2) of 10 CFR 20 a High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as-a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with one or more of the following:
a.) A radiation monitoring device which continuously indicates the radiation dose rate in the area, or b.) An integrating alarming dosimeter which alarms when a preset integrated dose or dose rate is received. Entry into such areas with this alarming dosimeter may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them, or l
Ofdd/ d%d. 79/ZH E9 CRYSTAL RIVER - UNIT 3 6-19 Amendment No. 9,EP,99,126
ADMINISTRATIVE CONTROLS e
6.12 HIGH RADIATION AREA (Continued) c.) An individual qualified in Health Physics Procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities in the area and who performs periodic radiation surveillance at the frequency specified by the Radiation Wo'i 's~ o 6.12.2 A High Radiation Area in which the W w iv of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.1 above, and in addition locked doors shall be provided to prevent unauthorized entry into such area.
The keys shall be maintained under the administrative control of the Health Physics Supervisor with one key assigned.to the administrative control of Shift Supervisor on duty.
Individual areas that are accessible to personnel, with radiation
-levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem,** and that are located within large areas such as the Reactor Building where no enclosure exists for purposes of locking and no enclosure can be reasonably constructed around the individual area, shall be roped off and conspicuously posted, and a flashing light shall be activated as a warning device.
6.13 ENVIRONMENTAL OVALIFICATION 6.13.1 By no later than June 30, 1982, all safety-related electrical equipment i
in the facility shall be qualified in accordance with the provisions l-of Division of Operating Reactors
" Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines) or NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December, 1979.
Copies of these documents are attached to Order for Modification of License DPR-72 dated October 24, 1980.
6.13.2 By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the-environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588.
Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
- Measurement made at 18" from source of radioactivity.
0/H f d u. 70/2HB9 CRYSTAL RIVER - UNIT 3 6-20 Amendment No. H,70,126
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6.14 PROCESS CONTROL PROGRAM (PCP)
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6.14.1 The PCP shall be approved by the Commission prior to l
implementation.
6.14.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the Semi-annual Radioactive Effluent Release Report for the 4
period in which the change (s) was made.
I 2.
Shall become effective upon review and acceptance by the Plant Review Committee.
F 6.15 OFFSITE DOSE CALCULATION MANUE (ODCM)_
6.15.1.
The OFFSITE DOSE CECULATION MANUE (ODCM) shall be approved by the Commission prior to implementation.
6.15.2 Licensee initiated changes to the OFFSITE DOSE CALCULATION MANUAL (ODCM):
1.
Shall be submitted to the commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.
2.
Shall become effective upon review and acceptance by the Plant Review Committee.
6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 6.16.1 Licensee initiated major changes
- to the radioactive waste systems (liquid, gaseous and solid):
1.
Shall be reported to the Commission in tihe Semiannual i..
Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Review Committee or be included as part of the annual FSAR update.
2.
May be implemented upon review and acceptance by the Plant Review Committee.
- A major change to a radioactive waste system shall be any change which would alter the ability of the plant or system to meet the-requirements of 10 CFR 50, Appendix I.
CRYSTE RIVER - UNIT 3 6-21
/cendment No. f), 70
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