ML20206M255
| ML20206M255 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/12/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20206M261 | List: |
| References | |
| DPR-62-A-128, DPR-71-A-099 NUDOCS 8608200515 | |
| Download: ML20206M255 (10) | |
Text
'o, UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
t E
WASHINGTON, D. C. 20555
\\...../
CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No. 99 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 March 5, 1986, as supplemented March 28, 1986, complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy 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 Comission'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 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, andparagraph2.C.(2)ofFacilityOperatingLicenseNo.DPR-71is hereby amended to read as follows:
8608200515 860812 PDR ADOCK 05000324 P
i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, 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 COMM ION ff p dk Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 12, 1986 l
l
1 ATTACHMENT TO LICENSE AMENDMENT N0. og FACILITY OPERATING LICENSE NO. DPR-71 DOCKET N0. 50-325 1
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3/4 3-54 B3/4 3-3 1
0 f
i 4
_,e
(BSEP-1-77)
INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMIT _ING CONDITION FOR OPERATION 3.3.5.5 A chlorine detection system, with one detection subsystem located at the Control Room air intake (1-AT-2977, 2-AT-2977) and one detection subsystem located near the chlorine tank car siding (1-AT-2979, 2-AT-2979), shall be OPERABLE with the alarm / trip setpoint adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm.
APPLICABILITY:
OPERATIONAL CONDITIONS 1*,
2*, and 3*.
ACTION:
With one chlorine detecter of either or both subsystem (s) inoperable, 1.
restore the inoperaoie detection subsystem to OPERABLE status within 7 days or, within t'he next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, isolate the Control Room and operate in the recirculation mode.
b.
With both chlorine detectors of either subsystem inoperable, within one hour isolate the Control Room and operate in the recirculation mode.
The provisions of Specification 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.5.5 Each of the above required chlorine detection system subsystems shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
- With the chlorine tank car within the Exclusion Area.
BRUNSWICK - UNIT 1 3/4 3-54 Amendment No. 73, 99
(BSEP-A-77) s INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.5.2 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room. This capaoility is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of CFR 50.
3/4.3.5.3 ACCIDENT MONITORINC INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient informaticn i s avail;ble gn selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation l
for Light Water-Cooled Nuclear' Power Plants to Assess Plant Conditions During and Fellowing an Accident," December 1975 and NUREC-0578, "TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations."
The suppression chamber water temperature monitoring system performs a dual function.
It provides for accident monitoring as recommended by Regulatory Guide 1.97.
This system is also designed to meet the acceptance criteria of NUREC-0661, Appendix A in monitoring average suppression chamber water temperature during normal operating conditions.
Refer to j
Sections 3/4.3.5.3 and 3/4.6.2.1 for Limiting Conditions for Operation and Surveillance Requirements pertaining to each function.
3/4.3.5.4 SOURCE RANCE MONITORS I
The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during start-up.
At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
3/4.3.5.5 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection system ensures that an l
accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for Control Room personnel. Upon detection of a high concentration of chlorine, the Control Room emergency ventilation system will automatically isolate the Control Room and operation will be initiated in the recirculation mode to provide the required protection. The detection system required by this specification is consistent with the Brunswick Steam Electric Plant's position l
on NRC TMI ACTION PLAN ITEM III.D.3.4, Control Room Habitability.
Regulatory Guide 1.95 " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release" was used as a source of guidance regarding the detection system design.
BRUNSWICK - UNIT 1 B 3/4 3-3 Amendment No. gg, 99 l
p aatro UNITED STATES
[
o,h NUCLEAR REGULATORY COMMISSION O
E WASHINGTON, D. C. 20555
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]
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No. DPR-62 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated March 5, 1986, as supplemented March 28, 1986, complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy 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 (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 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-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.128, 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 COMM SSION fw g
G Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 12, 1986 l
i s
ATTACHMENT TO LICENSE AMENDMENT NO. 128 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 ReplacethefollowingpagesoftheAppendixATechnicalShecificationswith the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3/4 3-54 83/4 3-3 t
i 4
4 i
I I
I
.o (BSEP-2-75)
INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMITING CONDITION FOR OPERATION
~
3.3.5.5 A chlorine detecticn system, with one detection subsystem located at the Control Room air intake (1-AT-2977, 2-AT-2977) and one detection subsystem located near the chlorine tank car siding (1-AT-2979, 2-AT-2979), shall be OPERABLE with the alarm / trip setpoint adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm.
APPLICABILITY: OPERATIONAL CONDITIONS 1*,
2*, and 3*.
ACTION:
With one chlorine detector of either or both subsystem (s) inoperable, a.
estore the i.coerabie detection subsystem to OPERAB'E status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, isolate the Control Room and operate in the recirculation mode.
I b.
With both chlorine de' rectors of either subsystem inoperable, within one hour isolate the Control Room and operate in the' recirculation mode.
The provisions of Specification 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.5.5 Each of the above required chlorine detection system subsystems shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
w
- With the chlorine tank car within the Exclusion Area.
i BRUNSWICK - UNIT 2 3/4 3-54 Amendment No.99, 128 i
e (BSEP-2-75)
INSTRUMENTATION BASES MONITORINC INSTRUMENTATION (Continued) 3/4.3.5.2 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of l
HOT SHUTDOWN of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost, and is j
consistent with Ceneral Design Criterion 19 of CFR 50.
3/4.3.5.3 ACCIDENT MONITORING INSTRUMENTATION l
The OPERASILITY of the post-accident monitoring instrumentation ensures tha. sufficient Indormation is availaole on selected plant : parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97,
" Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREC-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
The suppression chamber water temperature monitoring system performs a dual function.
It provides for post-accident monitoring as recommended by Regulatory Guide 1.97.
This system is also designed to meet the acceptance criteria of NUREC-0661, Appendix A in monitoring average suppression chamber water temperature during normal operating conditions. Refer to Sections 3/4.3.5.3 and 3/4.6.2.1 for Limiting Conditions for Operation and Surveillance Requirements pertaining to each function.
3/4.3.5.4 SOURCE RANCE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during start-up.
At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
~
3/4.3.5.5 CHLORINE DETECTION SYSTEM
}
The OPERABILITY of the chlorine detection system ensures that an l
accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for Control Room personnel. Upon detection of a high concentration of chlorine, the Control Room emergency ventilation system will automatically isolate the Control Room and operation will be initiated in the recirculation mode to provide the required protection. The detection system required by this specification is consistent with the Brunswick Steam Electric Plant's position on NRC TMI ACTION PLAN ITEM III.D.3.4, Control Room Habitability. Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release" was used as a source of guidance regarding the detection system design.
~
ggy, 128 BRUNSWICK - UNIT 2 8 3/4 3-3 Amendment No.
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