ML20248L086
| ML20248L086 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/05/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248L088 | List: |
| References | |
| NUDOCS 9806100413 | |
| Download: ML20248L086 (10) | |
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't UNITED STATES j
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 30006 OeM j
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L CAROLINA POWER & LIGHT COMPANY. et at b
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DOLXET NO. 50-325 l
BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 I
i AMENDMENT TO FAOlLITY OPERATING LICENSE Amendment No. 202 License No. DPR-71 l'
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated April 3,1998, 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 Cliapter I; B.
The facility will operate in conformity with ti)e 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.
2.
Accordingly, the license is amended by changas to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility
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Operating License No. DPR-71 is hereby amended to read as follows:
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9906100413 990605 POR ADOCK 05000324 i
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Technical Specifications The Technical Specifications contained in Appen'Jices A and B, as revised through Amendment No. 202, are hereby incorporated in the license. Carolina Power & Ught Company shall operate the facility in accordance with the Techrdcal Specifications.
, 3..
This license amendment is effective as of tha date of its issuance and shall be l
. Implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION J
(A, Pao Tsin Kuo, Actirig Director 1
Project Directorate 11-1
. Division of Reactor Projects - t/11 Office of Nuclear Reactor Hegulation
Attachment:
Changes to the Technical Specifications Date ofissuance:
June 5, 1998
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ATTACHMENTTO LICENSE AMENDMENT NO. 202 FACILITY OPERATING LICENSE NO. DPR-71
, DOCKET NO.60-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.
Remove Paoes insert Pages 3/4 5-4 3/4 5-4 8 3/4 5-2 B 3/4 5-2 4
~ EMERGENCY CORE COOLING SYSTEMS 3/4 5.3 LOW PRESSURE COOLING SYSTEMS CORE SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:
a.
One pump, and b.
An OPERABLE flow sath capable of taking suction from at least one of the following OPEMBLE sources and transferring the water through the spray sparger to the reactor vessel:
1.
In OPERATIONAL CONDITION 1. 2 or 3. from the suppression pool.
2.,
In OPERATIONAL CONDITION 4 or 5*:
a)
From the suppression pool. or b)
When the suppression pool is inoperable, from the condensate storage tank containing at least 228.200 gallons of water.
. I APPLICABILITY:
OPERATIONAL CONDITIONS 1. 2. 3. 4. and 5*
ACTION:
a.
In OPERATIONAL CONDITION 1. 2. or 3:
1.
With one CSS subsystem inoperable. POWER OPERATION may continue provided both LPCI subsysterns are OPERABLE: restore the inoperable CSS subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With both CSS subsystems inoperable, be in at'least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The core spray system is not required to be OPERABLE provided that the reactor vessel head is removed and the cavity is flooded, the spent fuel pool gates are removed, and the water level is maintained within the limits
, of Specifications 3.9.8 ard 3.9.9.
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EMERGENCY CORE COOLING SYSTEMS BASES.
i AUTOMA. TIC DEPRESSURIZATION SYSTEM (Continued)
ADS automatically controls 7 safety-relief valves, although the hazards analysis only takes credit for 6.
It is therefore appropriate to permit one valve.to'be out-of-service indefinitely without materially reducing system reliability.
Reactor operation is permitted to continue for up to 7 days with I
- 2 safety-relief valves inoserable except that HPCI is required to be
- demonstrated to be OPERABLE.-
The surveillance requirements provide adequate assurance that ADS will be OPERABLE when required.
Although all active components are testable during reactor operation, a complete functional test results in reactor blewdown'and therefore is. scheduled around shutdowns.
1 3/4 5 3 : LOW PRESSURE COOLING SYSTEMS-i3/4 5 3 1 ' CORE SPRAY SYSTEM (CSS)
-The CSS is provided to assure that the core is adequately cooled following a loss-of-coolant accident.
Two redundant loops each provide adequate core 2
cooling capacity for all break sizes from 0.2 ft up to and including the double ended reactor recirculation line break, and for smaller breaks foriowing depressurization by the ADS.
The CSS specifications are applicable during CONDITIONS 1. 7. and 3 because CSh ha primary source of emergency core cooling after the rcJctor vessel is depressurized.
When in C 'NDITIONS '1. 2. or 3 with one CSS loop inoperable. the demonstrated OPERABILITY of the redundant full capacity CSS loop and the full capacity Lcw Pressure Coolant Injection System provides assurance of adequate core cooling and' justifies the specified 7 day out-of-service period.
.The CSS specifications.are applicable in CONDITIONS 4 and 5 to provide a source for flooding of the core in case of accidental draining.
volumes,pecified total volume, which includes both usable and unusable The s of =228.200 gallons of water in the condensate storage tank-(CST) ensures the CSS can supply at least 50.000 gallons of makeup water to the reactor pressure vessel'.
CSS air. ingestien is expected to occur at the level which corresponds to a CST volume of 178.200 gallons.
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UN11ED STATES g
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WASHINGTON, D.C. 3066H1001 o
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C/ROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 232 License No. DPR-62 1.
The Nuclear Regulatory Commisden (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated April 3,1998, complies with the standards and requirernents 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 conformity 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 hesith and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance ci 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 beea satisfied.
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 Ope. rating Ucense No. DPR 62 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised ~
through Amendment No. 232, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Pao-Tsin Kuo, Acting Director Project Directorate Il-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
June 5,1998 1
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ATTACHMENT TO LICENSE AMENDMENT NO. M7 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paoes Insert Pages 3/4 5-4 3/4 5-4 8 3/4 5-2 B 3/4 5-2 l
EMERGENCY CORE COOLING SYSTEMS 3/4.5 3 LOW PRESSURE COOLING SYSTEMS CORE SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:
a.
One pump, and b.
An OPERABLE flow sath capable of taking suction from at least one of the following OPEMBLE sources and transferring the water through the spray sparger to the reactor vessel:
1.
In OPERATIONAL CONDITION 1, 2. or 3. from the suppression pool.
2.,
In OPERATIONAL CONDITION 4 or 5*:
a)
From the suppression pool, or b)
When the suppression pool is inoperable, from the condensate storage tank containing at least 228.200 gallons of water.
I APPLICABILITY:
OPERATIONAL CONDITIONS 1. 2. 3. 4. and 5".
ACTION:
a.
In OPERATIONAL CONDITION 1. 2. or 3:
1.
With one CSS subsystem inoperable. POWER OPERATION may continue provided both LPCI subsystems are OPERABLE: restore the inoperable CSS subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With both CSS subsystems inoperable. be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN withi i +he next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The core spray system is not required to be OPERABLE provided that the reactor vessel head is removed and the cavity is flooded. the spent fuel pool gates are removed, and the water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.
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EMERGENCY CORE COOLING SYSTEMS BASES AUTOMATIC DEPRESSURIZATION SYSTEM (Continued)
ADS automatically controls 7 safety-relief valves, although the hazards analysis only takes credit for 6.
It is therefore appropriate to permit one valve to be out-of-service indefinitely without materially reducing system reliability. Reactor operation is permitted to continue for up to 7 days with 2 safety-relief valves inoperable except that HPCI is required to be demonstrated to be OPERABLE.
The surveillance requirements provide adequate assurance that ADS will be OPERABLE when required. Although all active components are testable during reactor operation, a complete functional test results in' reactor blowdown and, therefore, is scheduled around shutdowns.
3/4.5.3 LOW PRESSURE C00 LING SYSTEMS 3/4.5 3.1 CORE SPRAY SYSTEM (CSS)
The CSS is provided to assure that the core is adequately cooled following a loss-of-coolant accident.
Two redundant loops cooling capacity for all break sizes from 0.2 ft,each provide adequate core up to and' including the double-ended reactor recirculation line break, and for smaller breaks following depressurization by the ADS.
The CSS specifications are applicable during CONDITIONS 1, 2 and 3 because CSS is a primary source of emergency core cooling after the reactor vessel is depressurized.
When in CONDITIONS 1. 2. or 3 with one CSS loop inoperable. the demonstrated OPERABILITY of the redundant full capacity CSS loop and the full cap 5 city Low Pressure Coolant Injection System provides assurance of adequate core cooling and justifies the specified 7 day out-of-service period.
The CSS specifications are applicable in CONDITIONS 4 and 5 to provide a source for flooding of the core in case of accidental draining.
The s I
volumes,pecified total volume, which includes both usable and unusable of 2228,200 gallons of water in the condensate storage tank (CST) ensures the CSS can supply at least 50,000 gallons of makeup water to the reactor pressure vessel.
CSS air ingestion is expected to occur at the level which corresponds to a CST volume of 178.200 gallons.
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