ML20073L410
| ML20073L410 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/05/1994 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073L416 | List: |
| References | |
| NUDOCS 9410130084 | |
| Download: ML20073L410 (12) | |
Text
_ _ _
pn necu g
-t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
'+9.....,o CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 172 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated September 9,1994, 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 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 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 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:
9410130004 941005 PDR ADOCK 05000324 P
O
. _(2)
Technical-Specifications
~
.The Technical Specifications contai'ned in Appendices A and B, as revised through Amendment No.172, 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 7 days of issuance.
~
FOR THE NUCLEAR REGULATORY COMMISSION William H. Batenan, Director Project Directorate II-I 1
Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 5, 1994 i
i
ATTACHMENT TO LICENSE AMENDMENT NO. 172-FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 l
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 6-18 3/4 6-18 3/4 6-19 3/4 6-19 8 3/4 6-5 B 3/4 6-5 i
l J.
l l
l i
I I
e--
--c--
e
,,---w
-,-,--*=r+vw e-w-wr=
v--w++-,w-~-
3,w, s-gr--
CONTAINMENT SYSTEMS 3/4.6.4 VACUUM RELIEF DRYWELL - SUPPRESSION CHAMBER VACUUM BREAKERS i
LIMITING CONDITION FOR OPERATION
=
3.6.4.1 All drywell-suppression chamber vacuum breakers shall be OPERABLE and in the closed position with:
I a.
The position indicator OPERABLE, and b.
An opening setpoint of less than or equal to 0.5 psid.
l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2. and 3.
ACTION:
a.
With no more than 2 drywell-suppression chamber vacuum breakers inoperable for opening but known to be in the closed position, the provisions of Specification 3.0.4 are not applicable and operation may continue until the next COLD SHUTDOWN provided the surveillance requirements of Specification 4.6.4.1.b are performed I on the OPERABLE vacuum breakers within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 15 days thereafter, until the inoperable vacuum breakers are restored to OPERABLE status; otherwise, 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 drywell-suppression chamber vacuum breaker in the open position, as indicated by the position indicating system. the provisions of Specification 3.0.4 are not applicable and operation may continue provided the surveillance requirements of l
Specification 4.6.4.1.b are performed on the OPERABLE vacuum I
j breakers and the surveillance requirements of Specification 1
4.6.4.1.c are performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 72 i
j hours thereafter until the inoperable vacuum breaker is restored to the closed position: otherwise, 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 t
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l c.
With the position indicator of any drywell-suppression chamber vacuum breaker inoperable, the provisions of Specification 3.0.4 i
are not applicable and operation may continue, provided the l
surveillance requirements of Specification 4.6.4.1.c are performed I within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 14 days thereafter until the I inoperable Josition indicator is returned to OPERABLE status; otherwise Je 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 />.
i BRUNSWICK - UNIT 1 3/4 6-18 Amendment No. 85,I29,172 l
CONTAINMENT SYSTEMS
~
SURVEILLANCE REQUIREMENTS 4.6.4.1 Each drywell-suppression chamber vacuum breaker shall be demonstrated OPERABLE:
At least once per 14 days and within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after any discharge a.
of steam to the suppression chamber from any source. verify each vacuum breaker is closed as indicated by the position indicating system.
b.
At least once per 31 days and after any discharge of steam to the l suppression chamber from any source, by exercising each vacuum
. breaker through one complete cycle and verifying that each vacuum breaker is closed as indicated by the position indication system.
I c.
Whenever a vacuum breaker is in the open position, as indicated by I the position indication system, by conducting a test that verifies that the differential pressure is maintained greater than 1/2 the initial delta P for one hour without N makeup.
2 d.
At least once per 18 months during shutdown by:
I' 1.
Verifying the opening setpoint. from the closed position, to be less than or equal to 0.5 psid, 2.
Performance of a CHANNEL CALIBRATION that each position indicator indicates the vacuum breaker to be open if the vacuum breaker does not satisfy the delta P test in 4.6.4.1.c.
I BRUNSWICK - UNIT 1 3/4 6-19 Amendment No. 85,172 1
l CONTAINMENT SYSTEMS BASES 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES (CONTINUED)
A list of automatic closing primary containment isolation valves and their associated closure times shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The addition and deletion or primary containment isolation valves shall be made in accordance with Section 50.59 of 10 CFR Part 50.
3/4.6.4 VACUUM RELIEF i
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.
The vacuum breakers between the drywell and the suppression pool must not be inoperable in the open position since this would allow bypassing of the suppression pool in case of an accident.
There are an adequate number of i
valves to provide some redundancy so that operation may cnntinue with no more than 2 vacuum breakers inoperable and secured in the closed position.
The 14 day frequency stated in Specification 3.6.4.1, ACTION c and Specification 4.6.4.1 is based on engineering judgment, is considered adequate in view of other indications of vacuum breaker status available to operations i
personnel, and has been shown to be acceptable through operational experience.
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 sup3ression pool-reactor building vacuum breakers on a loss of instrument air. T1e 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 i
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-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 I
Secondary containment is designed to minimize any ground level release of radioactive material which may result from an accident. The reactor building l
provides secondary containment during normal operation when the drywell is sealed and in service. K;en the reactor is shut down or during refueling the i
drywell may be open and the reactor building then becomes the primary l
containment.
BRUNSWICK - UNIT 1 B 3/4 6-5 Amendment No.I6,III,IH,172
i*
t@ MCUg y-t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2055!K)001
,o CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 l
BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
l Amendment No.203 l
License No. DPR-62 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment filed by Carolina Power & Light l
Company (the licensee), dated September 9,1994, 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 Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
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 i
i E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission'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 paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to rea( as follows:
. l (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 203, 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 l
shall be implemented within 7 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
William H. Bate n, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 5, 1994
ATTACHMENT TO LICENSE AMENDMENT NO 203 FACILITY OPERATING LICENSE NO. OPR-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 Paaes Insert Paaes 3/4 6-18 3/4 6-18 3/4 6-19 3/4 6-19 B 3/4 6-5 B 3/4 6-5
/
l l
I o
l
{
l
CONTAINMENT SYSTEMS
~
3/4.6.4 VACUUM RELIEF DRYWELL - SUPPRESSION CHAMBER VACUUM BREAKERS LIMITING CONDITION FOR OPERATION 3.6.4.1 All drywell-suppression chamber vacuum breakers shall be OPERABLE and in the closed position with:
a.
The position indicator OPERABLE. and I
b.
An opening setpoint of less than or equal to 0.5 psid.
l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With no more than 2 drywell-suppression chamber vacuum breakers inoperable for opening but known to be in the closed position, the provisions of Specification 3.0.4 are not applicable and operation may continue until the next COLD SHUTDOWN provided the surveillance requirements of Specification 4.6.4.1.b are performed I on the OPERABLE vacuum breakers within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 15 days thereafter until the inoperable vacuum breakers are restored to OPERABLE status; otherwise, 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 drywell-suppression chamber vacuum breaker in the open position as indicated by the position indicating system, the provisions of Specification 3.0.4 are not applicable and operation may continue provided the surveillance requirements of Specification 4.6.4.1.b are performed on the OPERABLE vacuum I
l breakers and the surveillance requirements of Specification l
j 4.6.4.1.c are performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 72 I
i hours thereafter until the inoperable vacuum breaker is restored l
to the closed position; otherwise. 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 />.
c.
With the position indicator of any drywell-suppression chamber vacuum breaker inoperable, the provisions of Specification 3.0.4 are not applicable and operation may continue, provided the surveillance requirements of Specification 4.6.4.1.c are performed I within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 14 days hours thereafter I
until the inoperable position indicator is returned to OPERABLE status; otherwise, be in at least HOT SHUTDOWN within the next 12 j
hours 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 />.
l l
[
BRUNSWICK - UNIT 2 3/4 6-18 Amendment No. 103,IH,203 I
t
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.4.1 Each drywell-suppression chamber vacuum breaker shall be demonstrated OPERABLE:
a.
At least once per 14 days and within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after any discharge of steam to the suppression chamber from any source, verify each vacuum breaker is closed as indicated by the position indicating system.
b.
At least once per 31 days and after any discharge of steam to the I suppression chamber from any source, by exercising each vacuum breaker through one complete cycle and verifying that each vacuum breaker is closed as indicated by the position indication system, c.
Whenever a vacuum breaker is in the open position, as indicated by I the position indication system, by conducting a test that verifies that the differential pressure is maintained greater than 1/2 the initial delta P for one hour without N makeup.
2 d.
At least once per 18 months during shutdown by:
I 1.
Verifying the opening setpoint, from the closed position, to be less than or equal to 0.5 psid.
2.
Performance of a CHANNEL CALIBRATION that each position indicator indicates the vacuum breaker to be open if the vacuum breaker does not satisfy the delta P test in 4.6.4.1.c.
I BRUNSWICK - UNIT 2 3/4 6-19 Amendment No. 103,203
CONTAINMENT SYSTEMS BASES 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES (Continued)
A list of automatic closing primary containment isolation valves and their associated closure times shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The addition and deletion of primary containment isolation valves shall be made in accordance with Section 50.59 of 10 CFR Part 50.
3/4.6.4 VACUUM RELIEF l
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.
The vacuum breakers between the drywell and the suppression pool must not be inoperable in the open position since this would allow bypassing of the 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.
The 14 day frequency stated in Specification 3.6.4.1. ACTION c and Specification 4.6.4.1 is based on engineering judgment, is considered adequate in view of other indications of vacuum breaker status available to operations l
personnel, and has been shown to be acceptable through operational experience.
I 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 sup3ression pool-reactor building vacuum breakers on a loss of instrument air.
T1e 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 l
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 i
operation with design valve actuation and system leakage.
l 3/4.6.5 SECONDARY CONTAINMENT l
Secondary containment is designed to minimize any ground level release of l
radioactive material which may result from an accident. The reactor building l
provides secondary containment during normal operation when the drywell is sealed and in service. When the reactor is shut down or during refueling the l
i drywell may be open and the reactor building then becomes the primary containment.
BRUNSWICK - UNIT 2 B 3/4 6-5 Amendment No. (I,I28,I79,203
!