ML20244C832
| ML20244C832 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/30/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244C836 | List: |
| References | |
| NUDOCS 8906150160 | |
| Download: ML20244C832 (11) | |
Text
_
UNITED STATES o,
[
g NUCLEAR REGULATORY COMMISSION 5
.I WASHINGTON, D. C. 20555
/
FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE CITY OF KISSIMMEE CITY OF LEE 5 BURG CITY OF NEW SMYRNA BEACH AND UTILITIES C011MI5510N,' CITY OF NEW SMYRNA BEACH CITY.OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTIllTIES COMMISSION SEMlh0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENEr,ATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. $16
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License No. DPR-72 1.
The Nuclear Regulatory Commissicn (the Commission) has found that:
-~-
A. ' The application for amendment by Florida Power Corporation, et al.
(the licensees) dated March 31, ISS3, as supplemented June 22, 1983, 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; B.
The facility will operate in ccnformity 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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in t.ompliance with the Comission'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 l-of the Comission's regulations and all applicable requirements have been satisfied.
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l Accordingly, th'e license is amended by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
~
Technical Specifications The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No.116, 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 its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COPMISSION Herbert H. Berkow, Director Project Directorate II-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation Attachme_pt:
Changes.tp the Technical Specifications Date of Issuance: May 30,1989 0
0
1.
3 :c ATTACHMENT"TO LICENSE' AMENDMENT NO.116 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical. Specifications with-the attached pages. The revised pages are identified by amendment; numbers and contain: vertical lines indicating the area of change. -The corresponding overleaf pages'are.also provided to maintan document completeness.
Remove:
Insert.
3/4 3 3/4 3-23' 3/4 3-24~
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TABLE 3.3-6 (CONTINUED)
TABLE NOTATION i
ACTION 14 - With the number of channels OPERABLE less than required by the l
Minimum Channels OPERABLE requirement, perform area surveys of l
the monitored area with portable monitoring instrumentation at l
least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 ACTION 15 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION l
requirements of Specification 3.4.6.1.
ACTION 18 - With the number of channels OPERABLE less than required by the
- Minimum Channels OPERABLE requirement, within I hour initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
ACTION 19 - With the number _ of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, plant operation may continue provided grab samples are collected and analyzed for gross activity
- at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 30 - With the nunber of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements.
- 1) Either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or
- 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
- LLD for noble gas principal gamma emittgrs shall be 5 x 10-5 Ci/cc.
LLD for liquid samples shall be 1 x 10- Ci/ml.
l CRYSTAL RIVER - UNIT 3 3/4 3-24 Amendment No. /f,0,116
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3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/h.3.2 REACTOR PROTECTION SYSTEM (RPS) AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM (ESFAS) INSTRUMENTATION The OPERABILITY of the RPS and E5FA5 instrumentation systems ensure that 1) the associated ESFAS action and/or RPS trip will be iratiated when the parameter monitored by each channel or combination thereof exceeds its se: point,2) the specified coincidence logic is maintained, 3) sufficient redundancy )is maintained to permit a channel to be ou ef service for testing or maintenance, and 4 sufficient system functienal capability is available for RPS and E5FAS purposes from diverse parameters.
The CPERASILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protec ion and mitigation of accident and transient conditions. The integrated opera:!on of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overai system
'unctional capability is maintained comparable to the original design standards. The periodic survel!1ance tests performed at the minimum frequencies are sufficie.: to demonstra:e this capability. The ESFAS Functiona'l Unit CHANNEL FUNCTIONAL TESTS shall be performed in accordance with Regulatory Guide 1.22 (Revision 0,1972).
The measurement of response Ime at the specified frequencies provides assurance that the RPS and ESFAS ac:lon function associated with each channel is completed within the time limit assumed in the safety analyses. No credi: was taken in the analyses for those char.nels with reponse times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping er total cnannel test measurements provided that such test demonstrate the total channe!
response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utill !ng replacement sensors with certified response times.
1 CRYSTAL RIVER - UNIT 3 B 3/4 3-1 Amendment No. 66
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I 3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
The CHANNEL CALIBRATION of the Reactor Building High Radiation Monitor is performed ja gita for at least one decade below 10 rad /hr.
In ljg calibration by n i electronic signal substitution is used for all range decades above 10 rad /hr.
3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor See Bases Figures 3-land 3-2 for examples of acceptable minimum incore detector core.
arrangements.
3/4.3.3.3 SEISMIC INSTRUMENTATION The Ol'ERABILITY of the seismic instrumentation ensures that sufficient capability is availab e to promptly determine the magnitude of a seismic event so that the response of those : eatures important to safety may be evaluated. This capability is required to permi' comparison of the measured response to that used in the design basis for the l
faciray. This instrumentation is consistent with the recommendations of Safety Guide 12 "In trumentation for Earthquakes,"' March 1971.
3,'4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs", February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capabliity is available to permit shutdown and maintenance of CRYSTAL RIVER - UNIT 3 B3/43-2 Amendment No.116 M