ML20237G438
| ML20237G438 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/20/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G442 | List: |
| References | |
| NUDOCS 8709020255 | |
| Download: ML20237G438 (14) | |
Text
..
.y UNITED STATES f
g NUCLEAR REGULATORY COMMISSION r,
j WASHINGTON, D. C. 20555
%,....+/
l CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1
)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendmerit by Carolina Power & Light Company (thelicensee),datedMarch 27, 1987, 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 Commission; C.
Thereisreasonableassurance(1)thatthe'activitiesauthorized by this amendment can be conducted witnout 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 comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is 'n accordance with 10 CFR Part 51 of the Comission's regulations ano all applicable requirements have been 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 Operating License No. DPR-71 is hereby amended to read as follows:
8709020255 B70820 PDR ADOCK 05000324
o (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. lill, 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 and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: August 20, 1987 Nef
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LA:PD21:DDPR PM:PD21:DPRP D:PD21:DRPR 0GC-PAnderson ESylvester 85 EAdensam l
7/31/87 74A/87 7/p/87
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ATTACHMENT T0 LICENSE AMENDMENT NO. 111 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 6-20 3/4 6-20 3/4 6-20a B 3/4 6-5 8 3/4 6-5 B 3/4 6-5a l
l s
(BSEP-1-103) 3 s
CONTAINMENT SYSTEMS l
SUPPRESSION POOL - REACTOR BUILDING VACUUM BREAKERS 1
LIMITING CONDITION FOR OPERATION 3.6.4.2 All suppression pool-Reactor Building vacuum breakers shall be OPERABLE with:
l an opening setpoint of less than or equst to 0.5 psid a.
b.
an OPERABLE Nitrogen Backup System consisting of two independent subsystems (one nbsystem for each vacuun breaker).
APPLICABILITY: OPERATIONAL CONDITIONS *1, 2, and 3.
ACTION:
l(ith one suppression pool-Reactor Building vacuum breaker inoperable for a.
opening but known to b'e in the closed position, restore the inoperable vacuum breaker to OPERABLE status vtthin 7 days or be in at least HOT SHUTDOWN within the next 12 hou'es 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 />.
b.
With one Nitrogen Backup System subsystem inoperable, verify the remaining subsystem is OPERABLE and restore the inoperable subsystem to OPERABLE status within 31 days or be in at least HOT SHUT.X)WN vithin 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 withia the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With both Nitrogen Backup System subsystems inoperable, restore at least one inoperable subsystem to OPERABLE status within 7 daysi 'othervi.se, 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 />.
SURVEILLANCE REQUIREMENTS
.'4.6.4.2.1 Each suppression pool-Reactor Building vacuunrbreaker shall be l
-demonstrated OPERABLE 1 a.
At least once per 92 days by:
1.
Manually verifying that each vacuum breaker check valve is free to open, and 2.
Cycling each vacuum breaker butterfly valve through at least one complete cycle of full travel.
b.
At least once per 18 months by:
1.
Demonstrating that the force regtired to open each vacuum breaker check valve does not exceed 0,5 psid.
I BRUNSWICK - UNIT 1 3/4 6-20 Amendment No. 16, 111
(BSEP-1-103)
=
SURVEILLANCE REQUIREMENTS (Continued) 2.
Demonstrating that the vacuum breaker butterfly valve opens at -0.45
+ 0.05 psid, dryvell pressure going negative relative to Reactor Building pressure.
3.
Visual inspections.
l a
4.6.4.2.2 The Nitrogen Backup System shall be demonstrated OPERABLE:
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 /> by verifying that each subsystem is pressurized to greater than or equal to 1130 psig, b.
At least once per 18 months by verifying that each subsystem maintains system pressure with a leakage rate of less than or equal to.65 SCFM at a
starting pressure greater than or equal to 1130 psig.
At least once per 18 months by performing a logic system functional test c.
to ensure actuation of the nitrogen backup system.
1 I
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I BRUNSWICK - UNIT l' 3/4 6420a Amendment No. 111 i
(BSEP-A-103)
I
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CONTAINMENT SYSTEMS BASES 3/4.6.4 VACUUM RELIEF Vacuum relief breakers are provided to equalize the pressure between the drywell and suppression pool and the suppression pool and reactor building..
This system will maintain the structural integrity of the containment under conditions of-large differential pressures.
1 The vacuum breakers between the drywell and the suppression pool must not be j
inoperable in the open position since this would allow bypassing of the I
i suppression pool in case of'an accident. There are an adequate number of valves to provide some redundancy so that operation may continue with no more than 2 vacuum breakers inoperable and secured in the closed position.
Each set of vacuum relief valves between the suppression chamber and reactor building provides 100% relief, which may by required in the unlikely event that* negative pressures develop in the primary containment.
The Nitrogen Backup System provides backup motive power for these suppression pool-reactor building vacuum breakers on a loss of instrument air.
The normal non-interruptible instrument air system for these vacuum breakers is designed as s'Setemic Class I system supplied by air compressors powered from the emergency buses. The Nitrogen System serves as a backup to that air system and thus the loss of the Nitrogen System, or portions thereof, does'not make the vacuum breakers inoperable. The design allows for the out of service times in Actions b and c.
The Nitrogen Backup System is added to the Suppression Pool-Reactor-Building Vacuum Breaker specification to satisfy NRC concerns relative to 10 CFR 50.44(c)(3) as addressed in the Brunswick. Safety Evaluation Report dated October 30, 1986 concerning Generic Letter 84-09.
Pressurization to 1130 psig assures sufficient system capacity to provide 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation with design valve actuation.and' system leakage.
3/4.6.5 SECONDARY CONTAINMENT Secondary containment is designed to minimize any ground level rett h e of radioactive-material which may result from an accident. The reactu building rprovi-des secondary containment during. normal operation when the drywell is sealed and.in service. When the reactor is shut down, or during refueling, the.drywell may be open and the reactar building then becomes the primary containment.
Establishing and maintaining a vacuum in the building with the standby gas treatment system, once per 18 months, along wit.h the surveillance of the valves, is adequate to ensure that there are no violations of the integrity of the secondary containment.
3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL The OPERABILITY of the containment iodine filter trains ensures that sufficient icdine removal capability will be available in the event of a LOCA. The reduction in containment iodinn inventory reduces the resulting l
BRUNSWICK - UNIT l '
B 3/4 6-5 Amendment No. 7%,111
' ~ ~ - ~
($$EP-1-103)
,1s l
CONTAINMENT SYSTEMS BASES (Continued)
I l-site boundary radiation doses associated with containment leakage.
the operation of this system and resultant iodine removal capacity are consistent with the assumptions used in the LOCA. analyses.
i i
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i BRUNSWICK - UNIT I B 3/4 6-Sa Amendment No. 111 l
UNITED STATES l
[
g NUCLEAR REGULATORY COMMISSION 5
"j WASHINGTON, D. C. 20655 m
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CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-324 BRUNSWICK STEAM ELECTRIC PL, ANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.138 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee),datedMarch 27, 1987, 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.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and parc. graph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
4
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.138, 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 and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
l l
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________J
v ATTACHMENT TO LICENSE AMENDMENT NO. 138 FACILITY OPERATING LICENSE NO. DPR-62 j
l 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 Pages Insert Pages 3/4 6-20 3/4 6-20 3/4 6-20a B 3/4 6-5 B 3/4 6-5 B 3/4 6-5a A
(BSEP-2-104)
CONTAINMENT SYSTEMS SUPPRESSION POOL - REACTOR BUILDINC VACUUM BREAKERS l
LIMITING CONDITION FOR OPERATION l
3.6.4.2 All suppression pool-Reactor Building vacuum breakers shall be l
OPERABLE with an opening setpoint of less than or equal to 0.5 psid a.
b.
an OPERABLE Nitrogen Backup System consisting of two independent subsystems (cne subsystem for each vacuum breaker).
APPLICABILITY: OPERATIONAL CONDIIIONS,1, 2, and 3.
ACTION:
With one suppression pool-Reactor Building vacuum breaker inoperable for
\\
a.
opening but known to be in the closed position, restore the inoperable vacuum breaker 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 />.
b.
With one Nitrogen Backup System subsystem inoperable, verify the remaining subsystem is OPERABLE and restore the inoperable subsystem to OPERABLE status within 31 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 />.
With both Nitrogen Backup System subsystems inoperable, restore at least c.
one inoperable subsystem to OPERABLE status within 7 days; otherwise, be in at least HOT SHUTDOWN within the next 12 bours 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 />.
SURVEILLANCE REQUIREMENTS 4.6.4.2.1 Each suppression pool-Reactor Building vacuum breaker shall be l
demonstrated OPERABLE:
a.
At least once per 92 days by:
1.
Manually verifying that each vacuum breaker check valve is free to open, and 2.
Cycling each vacuum breaker butterfly valve through at least one complete cycle of full travel.
b.
At least once per 18 months by:
1.
Demonstrating that the force required to open each vacuum breaker check valve does not exceed 0.5 paid.
I BRUNSWICK - UNIT 2' 3/4 6-20 Amendment No. 77, 73,138
(BSEP-2-104)
~:.
SURVEILLANCE REQUIREMENTS (Continued) 2.
Demonstrating that the vacuum breaker butterfly valve opens at -0.45 1 0.05 paid, dryvell pressure going negative relative to Reactor Building pressure.
3.
Visual inspections.
4.6.4.2.2 The Nitrogen Backup System shall be demonstrated OPERABLE:
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that each subsystem is pressurized
- a..to greater than or equal to 1130 psig.
b.
At least once per 18 months by verifying that each subsystem maintains system pressure with a leakage rate of less than or equal to.65 SCFM at a starting pressure greater than or equal ta 1130 psig.
At least once per 18 months by performing a logic system functional test c.
to ensure actuation of the nitrogen backup system.
i l
)
1 1
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l BROW 5 WICK - UNIT 2 3/4 o-20a Amendment No. 138
_n
(BSEP-2-1GO a
CONTAINMENT SYSTEMS SASES 3/4.6.4 VACUUM RELIEF Vacuum relief breakers are 3rovided to equalize the pressure between the drywell and suppression pool and the suppression pool and reactor building.
This system will maintain the structural integrity of the containment under conditions of large differential pressures.
The vacuum breakers between the drywell and the suppression pool must not be inoperable in the open position since this would allow bypassi,of the suppression pool in care of an accident. There are an edequate number of valves to provide some redundancy so that operation may continue with no more than 2 vacuum breakers inoperable and secured in the closed position.
Each set of vacuum relief valves between the suppression chamber and reactor building provides 100% relief, which may be required in the unlikely event
)
'that negative pressures develop in the primary containment.
The Nitrogen Backup System provides backup motive power for these suppression pool-reactor building vacuum breakers on a loss of instrument air. The normal non-interruptible instrument air system for these vacuum breakers is designed as a Seismic Class I system supplied by air compressors powered from the emergency buses. The Nitrogen System serves as a backup to the air system and thus the loss of the Nitrogen System,or portions thereof, does not make the vacuum breakers inoperable. This design allows for the out of service times in Actions b and c.
The Nitrogen Backup System is added to the Suppression Pool-Raactor Building Vacuum Breaker specification to satisfy NRC concerns relative to 10 CFR 50.44(c)(3) as addressed in the Brunswick Safety Evalut. tion Report dated October 30, 1986 concerning Generic Letter 84-09.
Pressurization to 1130 psig assures sufficient system capacity to provide 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of 4
l operation with design valve actuation and system leakage.
l 3/4.6.5 SECONDARY CONTAINMENT
)
Se$ondarycontainmentisdesignedtominimizeanygroundlevelreleaseof radioactive material which may result from an accident. The reactor building provides secondary containment during normal operation when the drywell i.s sealed and in service. When the reactor is shut down or during refueling the drywell may be open and the reactor building then becomes the primary containment.
Establishing and maintaining a vacuum in the building with the trdby gas treatment system, once per 18 months, along with the surveillance of &
valves, is adequate to ensure that there are no violations of the integrity of the secondary containment.
3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL The OPERABILITY of the containment iodine filter trains ensures that j
sufficient iodine removal capability will be available in the event o! a LOCA. The reduction of containment iodine inventory reduces the resulting BRUNSWICK - UNIT 2 B 3/4 6-5 Amendment No. 97,138
(BSEP-2-Aus)
- f'.
e e
CONTAINMENT SYSTEMS BASES-(Continoed) site boundary radiation doses associated with containment leakage. The c,peration of this system and resultant iodine removal capar.ity are consistent with the assumptions used in the LOCA analyses.
a 1
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l BRUNSWICK - UNIT 2' B 3/4 6-Sa Amendment No. 138
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