ML20092D856
| ML20092D856 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/12/1992 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092D857 | List: |
| References | |
| NUDOCS 9202140314 | |
| Download: ML20092D856 (7) | |
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= UNITED STATES po
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NUCLEAR REGULATORY SOMMISSION W ASHINGioN. D.C. 20666
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i FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEE 181LRQ 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 4
.SEMIN0LE ELECTRIC COOPERATIVE. INC._
CITY OF TALLAHASSEE-DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 MUCLEAR GENERATING PLANT j
AMENDMENT TO FACILITY OPERATIRG LICENSI
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Amendment No. 139 License No,'DPR-72 1,
The Nuclear Regulatory Commission (the Commission) has found that:
A, The = application _ for amendment by F1orida Power. Corporation, et al, (the licensees) dated August 15, 1991, complies with the standards and. requirements of the Atomic Energy Act of 1954, as amended _ (tho Act), and the Comission'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 (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 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 of th_e Commission's' regulations and all applicable requirements have been satisfied-9202140314 920212 POR ADOCK 05000302 P
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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. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in A>pendices A and B, as revised through Amendment No.139, are here)y 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 it..plem nted within 30 days of issuance.
FOR HE NVCLEAR REGULATORY COMMISSION
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bert N. Berkow, irector roject Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes tolthe Technical Specifications Date of Issuance: February 12, 1992 l
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ATTACHMENT TO LICENSE AMENDMENT NO. ])9 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 number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remayn Insert 3/4 1-4
?/4 1-4 6-15 6-15
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7 REACTIVITY CONTROL SYSTEMS
' BORON DILUTION LIMITING CONDITION-FOR OPERATION 3.1~.1.2 ~The flow rate of reactor coolant-through the Reactor Coolant System shall_.be > 2700 gpm whenever a reduction in Reactor Coolant System boron concentration is being made.
APPLICABILITY: All MODES.
ACTION:
With the = flow rate of reactor coolant through the Reactor Coolant System < 2700 gpm, imediately suf pend all operations involving a reduction in boron concentratinn of the Reactor Coolant System.
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SURVEILLANCE-REQUIREMENTS 1
4.1.1 '. 2 The flow rate of reactor coolant through the Reactor Coolant
. System shall be determined to be 1 2700 gpm within one hour prior-to the start of and at'least once per hour during a reduction in the Reactor Coolant System boron concentration by either:
a.
- Verifying at-least one reactor coolant' pump is' in operation,
- or d
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b;
. Verifying that at least one DHR pump is in operation and supplying't:2700 gpm through the Reactor Coolant System.
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1 LCRYSTAliRIVER - UNIT 3 3/4 1-3 0
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- 9-RkACTIVITY CONTILOL $YSTEMS N00ERATOR TDIPERATURE C0EFFICIENI LIMITING C0felTION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MIC) shall be:
Less positive than 0.9 x 10 Ak/k/'F whenever THERMAL POWER is < 95%
a.-
of RATED THERMAL POWER,
- b.
Less positive than 0.0 x 10 Ak/k/'F whenever THERMAL POWER is 2 95%
of RATED THERMAL POWER, and c.
Equal to or less negative than the limit-provided in the CORE OPERATING LIMITS REPORT at RATED THERMAL POWER.
APPLICABILITY: MODES I and 2*#.
ACTION:
With the moderator temperature coefficient outside any of the above limits, be
-in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.1.3.1 The MTC shall be determined-to be.within its limits by confirmatory measurements.
MTC measured values shall be extrapolated and/or compensated to permit direct comparison with tha above limits.
.4.1.1.3.2' The MTC shall be determined at the % iowing frequencies and THERMAL
-POWER Conditions during each fuel cycle.
Prior to initial' operation above 5%'of RATED THERMAL POWER, after 2.
each fuel leading.-
'b.-
At any THERMAL POWER,'within 7 days after reaching a RATED THERMAL POWER equilbrium boron concentration of 300 ppm.
- With K,,, 2 1.0.
- See Special-Test Exception 3.10.2.
CRYSTAL RIVER - UNIT 3 3/4 1-4 AMENOMENT NO. 139,
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--.J ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Office, submitted no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle and any remaining part of a reload cycle for the following:
3.1.1.3.c Negative Moderator Temperature Coefficient Limit l
3.1.3.6 Regulating Rod Insertion Limits 3.1.3.7 Rod Program 3.1.3.9 Axial Power Shaping Rod Insertion limits 3.2.1 AXIAL POWER IMBALANCE 3.2.4 QUADRANT POWER TILT The ::nalytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC, specifically:
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BAW 10122A Rev. 1, " Normal Operating Controls", May 1984 2)
BAW-10116A, " Assembly Calculations and Fitted Nuclear Data",
May 1977 3)
BAW-10ll7P A. " Babcock & Wilcox Version of PDQ User's Manual",
January 1977 4)
BAW 10ll8A, " Core Calculational Techniques and Procedures".
-December 1979 5) 9AW-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core-Reactivity and Power Distributions", August 1976 6)
BAW 10125A, " Verification of Three-Dimensional FLAME Code",
August 1976 7)
BAW-10152A, "N0ODLE - A Multi-Dimensional Two-Group Reactor Simulator", June 1985 8)
BAW-10119, " Power Pa king Nuclear Reliability Factors", June 1977 9)
The methodology for Rod Program received NRC approval in the Safety Evaluation Report dated January 31, 1990.
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS g CRYSTAL RIVER UNIT 3 6-15 Amendment No. 9,$9,90, 777.725, 139,
ADMIWISTRATIVE CONTROLS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CCRE OPERATING LIMITS REPORT. including any mid cycle revision or s ments thereto, shall be provided Document Control Desk with copies to the Regional Administrator and In5pector.
CRYSTAL RIVER - UNIT 3 6-16 Amendment No. 3,25,69,gg, 125 i