ML19261A656
| ML19261A656 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/19/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19261A657 | List: |
| References | |
| NUDOCS 7902060003 | |
| Download: ML19261A656 (6) | |
Text
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9 4
UNITED STATES j
NUCLEAR REGULATORY COMMISSION g-WASHINGTON, D. C. 20556 as...../
CAROLINA POWER & LIGHT COMPANY 00CKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No. 18 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated January 18, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the
. 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 (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 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 the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Fccility Operating License '6. DPR-71 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.18, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
7902060003
n 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas A.
polito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 19, 1979
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE N0. DPR-71 DOCKET N0. 50-325 Revise Appendix A as follows:
At pages 3/410-5, 3/410-6 and 3/410-7
SPECIAL TEST EXCEPTIONS 3/4.10.5 REACTOR VESSEL DRAINING LIfilTING CONDITION FOR OPEFATION 3.10.5 The provisions of Specification 3.3.2 may be suspended to permit the Table 3.3.2-1, Shutdowr; Cooling System Isolation Reactor Vessel Water-Low, Level 1 instrumeritation to be inoperable to permit lowering of the reactor vessel water level to > 45 inches above the top of the (active fuel) for inspection, maintenance and repair of core r ; ray system, control rod drive system and other piping, provided that ;ne:
a.
LPCI mode of the RHR system is OPERABLE p<.e Specification 3.S.3.2.
b.
LPCI mode of the RHR system actuation instrumentation is OPERABLE per Specification 3.3.3.
c.
Temporary reactor vessel water level monitoring and alarm system is OPERABLE with a low water level alarm setpoint
> 45 inches above the top of the (active fuel).
d.
Two control rod drive pumps are OPERABLE. The standby pump shall have an independent emergency' power supply.
e.
The Demineralizer Water System is OPERABLE as a backup makeup water system.
f.
No other operations with a potential for draining the reactor vessel are in progress.
APPLICABILITY:
CONDITION 5, during the shutdown between Cycles 1 and 2.
ACTION With the reactor vessel water level less than 45 inches above a.
the top of the (active fuel), immediately:
1.
Close the shutdown cooling system suction isolation valves, and 2.
Evacuate the reactor vessel.
~
3/4 10-5 amendment no 18
SPECIAL TEST EXCEPTIONS 3/4.10.5 REACTOR VESSEL DRAINING LIMITING CONDITION FOR OPERATION ACTION (Continued) b.
With the temporary reactor vessel water level monitoring and alarm system inoperable, Operation with the Reactor Vessel Water-Low, Level 1 instrumentation bypassed may continue for up to two (2) hours, provided:
1.
The reactor vessel water level is immediately verified to be stable and >45 inches above the top of the (active fuel),
2.
An operator is posted to monitor water level continuously during the period, and 3.
If conditions 1 and 2 above cannot be met, satisfy the requirements of ACTION a. above, c.
With one control rod drive (CRD) pump inoperable, restore the inoperable control rod drive pump to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or close the shutdown cooling system suction isolation valves within the next hour.
d.
With both control rod drive (CRD) pumps inoperable, close the shutdown cooling system suction isolation valves.
e.
With the Demineralized Water System inoperable as a backup makeup water system, provided that both CRD pumps are OPERABLE, restore the backup makeup water system to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or close the shutdown cooling system suction isolation valves.
SURVEILLANCE REQUIREMENTS 4.10.5 The temporary reactor vessel water level monitoring and alam system shall t,e demonstrated OPERABLE:
a.
By perfomance of a CHANNEL CALIBRATION prior to making the Shutdown Cooling System Reactor Vessel Water - Low, Level 1 instrumentation inoperable.
b.
At least once per 7 days while the Shutdown Cooling System Reactor Vessel Water - Low, Level i instrumentatior, is inoperable by performance of a CHANNEL FUNCTIONAL TEST.
amendment no. 18 3/4 10-6
SPECIAL TEST EXCEPTIONS SURVEILLANCE REQUIREMENTS (Continued) c.
Each CRD pump shall be verified OPERABLE by:
1.
Starting the pump, if riot operating, at least once per 7 days, and 2.
Verifying an independent emergency power supply at least once per 7 days by verifying correct breaker alignment and indicated power availability for the standby pump, d.
The Demineralized Water System shall be demonstrated OPERABLE as a backup makeup water system at least once per 7 days by verifying flow from the Demineralized Water System on the refueling floor.
e.
The reactor vessel "2/3 core height" water level indication channel shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by a CHANNEL CHECK.
/4 10-7 amendment no. 18