ML19260C521
| ML19260C521 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/10/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260C522 | List: |
| References | |
| NUDOCS 8001070338 | |
| Download: ML19260C521 (5) | |
Text
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,'o, UNITED STATES 7,, \\ "( (,E y y'> c g
NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20555
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTR C PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated October 10, 1979, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations se,t forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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 Commission's regulations and all applicable requirements have been satisfied.
1694 179 8001070 3'3,9
., 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. DPR-62 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
's 3
~
homas Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors Attachement:
Changes to the Technical Specifications Date of Issuance:
December 10, 1979 1694 180
ATTACHMENT TO LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Technical Specifications contained in Appendix A of the above indicated license with the attached pages.
~
The changed area of the page is reffe,cted by a marginal line.
Remove Insert 3/4 2-9*
3/4 2-9*
3/4 2-10 3/4 2-10
- 0verleaf pages - no changes 1694 181
POWER DISTRIBUTION LIMITS 3/4.2.2 / RM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The flow biased APRM scram trip setpoint (S) and rod block trip set-point (SRB) shall be established according to the following relationships:
S 1(0.66W+54%)T
~
S i (0.66W + 42%) T RB where: S and S are in percent of RATED THERMAL POWER, oB W = Loop recirculation flow in percent of rated flow, T = Lowest value of the ratio of design TPF divided by the MTPF obtained for any class of fuel in the core (T 1 1.0), and Design TPF for: 8 x BR fuel = 2.48 7x7 fuel = 2.60 8x8 fuel = 2.45 APPLICABILITY: CONDITION 1, when THERMAL POWER > 25% of RATED THERMAL POWER.
ACTION:
With 5 or S exceeding the allowable value, initiate corrective action pp within 15 mTnutes and continue corrective ac' tion so that S and S are withintherequiredlimitswithin4hoursorreduceTHERMALPOWEkBto less than 25% of RATED THERMAL NWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.2 The MTPF for each class of fuel shall be detennined, the value of T calculated, and the flow biased APRM trip setpoint adjusted, as required:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, and c.
Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL ROC PATTERN for MTPF.
BRUNSWICK - UNIT 2 3/4 2-9 Amendment No. 48 1694 182
POWER DISTRIBUTION LIMITS 324.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL, POWER RATIO (MCPR), as a function of core shown in flow..shalllbe equal to or greater than MCPR times the Kf Figure 3.2.3-1, for Beginning-of-cycle (B0C) to end-of-cycle (EOC) $ninus a.
2000 MWD /t, with:
1.
MCPR for 7'x7 fuel = 1.20,*
2.
MCPR for 8x8 f'iel = 1.21, 3.
MCPR for 8x8R fuel = 1.26.
b.
E0C minus 2000 MWD /t to EOC, with:
1.
MCPR for 7x7 fuel = 1.22.*
2.
MCPR for 8x8 and 8x8R fuel = 1.29.
APPLICABILITY:
CONDITION 1, when THERMAL POWER > 25% RATED THERMAL. POWER.
ACTION:
With MCPR less than the applicable limit determined from Figure 3.2.3-1, initiate corrective action within 15 minutes and continue corrective action so that MCPR is equal to or greater than the applicable limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER to less than-25% of RATED THERMAL POWER within the.next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.3 MCPR shall be determined to be equal to or greater than the applicable limit determined from Figure 3.2.3-1:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, and Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is c.
operating with a LIMITING CONTROL R0D PATTERN for MCPR.
- For 7x7 fuel assemblies, the facter is based on the 112% flow curve of Figure 3.2.3-1 rather than the settoint of 102.5%.
BRUNSWICK - UNIT 2.
3/4 2-10 Amendment No. 48, 49 1694 183