ML20079G283
| ML20079G283 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/28/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20079G285 | List: |
| References | |
| DPR-62-A-089, DPR-71-A-064 NUDOCS 8401200020 | |
| Download: ML20079G283 (9) | |
Text
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UNITED STATES 8j 3 c Ij NUCLEAR REGULATORY COMMISSION 5.]
.. C WASHINGTON. D. C. 20555
+....
CAROLINA POWER & LIGHT COMPANY D0CKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.64 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 August 16, 1982 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 provieions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authori::ed 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 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 paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
8401200020 831228 PDR ADDCK 05000324 P
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, 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 COM11SSION
& k-omenic.B. Vassallo, Chief
[0perating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1983
I.
ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-235 Revise the Appendix A Technical Specifications as follows:
Remove Insert VIII' VIII 3/4 8-12 3/4 8-12 S
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...................
3/4 7-7 3/4.7.5 HYDRAULIC SNUBBERS......................................
3/4 7-9 3/4.7.6 SEALED SOURCE CONTAMINATION.............................
3/4 7-32 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire. Suppression Water System...........................
3/4 7-34 Spray and/or Sprinkler Systems..........................
3/4 7-38 High Pressure.CO2 Sys t ems............. '..................
3/4 7-40 Fire Hose Stations......................................
3/4 7-41 Foam Systems............................................
3/4 7-44 3/4.7.8 FIRE BARRIER PENETRATIONS...............................
3/4 7-46 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operation of one or Both Units..........................
3/4 8-1 Shutdown of Both Units..................................
3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operation of One or Both Units.........................................
3/4 8-6 A.C Distribution - Shutdown of Both Units...............
3/4 8-7 D.C. Distribution -
Operating...........................
3/4 d-8 D.C. Distribution - Shutdown............................
3/4 8-11 RPS Electric Power Monitoring...........................
3/4 8-12 i,
3/4.9 REFUELING OPERATIONS l
3/4.9.1 REACTOR MODE SWITCH.....................................
3/4 9-1 i
3/4.9.2 INSTRUMENTATION.........................................
3/4.9-3 l
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I BRUNSWICK - UNIT 1 VIII Amendment No.
64 i
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ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING LIMITING CONDITION FOR OPERATION 3.8.2.5 Two RPS electric power monitoring channels for each inservice RPS MG set or alternate source shall be OPERABLE.
APPLICABILITY: Whenever the respective power supply is supplying power to a RPS bus.
ACTION:
~
a.
With one RPS electric power monitoring channel for an inservice RPS MG set or alternate power supply inoperable, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service.
b.
With both RPS electric power monitoring channels for an inservice RPS MG set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS MG set j
or alternate power supply frca service.
}.
SURVEILLANCE REQUIREMENTS o
4.8.2.5 The above specified RPS power monitoring system instrumentation shall be determined OPERABLE:
a.
At least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST, and b.
At least once per 18 months by demonstrating the OPERABILITY of I
over-voltage, under-voltage, and under-frequency protective instrumentation by performance of a CHANNEL CALIBRATION including
}
simulated automatic actuation of the protective relays, tripping logic, and output circuit breakers and verifying the following setpoints:
1.
Over-voltage
< 129 VAC
< 132 VAC 2.
Under-voltage
> 105 VAC
> 108 VAC 3.
Under-frequency
> 57 Hz
> 57 Hz I
BRUNSWICK - UNIT 1 3/4 8-12 Amendment No. 64
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 5.
' ' C WASHINGTON. D. C. 20555 r a o.
y %.,,/
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment.by Carolina Power & f.ight Company (the licensee) dated August 16, 1982 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 emended 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 -
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89, are he'reby 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 COMMISSION 0-bDomenicB.Vassallo, Chief U
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1983 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY'0PERATING LICENSE NO. DPR-71 DOCKET N0. 50-235 1
Revise the Appendix A Technical Specifications as follows:
Remove Insert VIII VIII 3/4 8-12 3/4 8-12
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INDEX
. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
(
SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM ENERGENCY FILTRATION SYSTEM.................
3/4 7-3 3/4.7.3 FLOOD PROTECTION.........................................
3/4 7-6 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM....................
3/4 7-7 3/4.7.5 EYDRAULIC SNUBBERS.......................................
3/4 7-9 3/4.7.6' SEALED' SOURCE CONTAMINATION..............................
3,/4 7-37 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................
3/4 7-39 Spray and/or Sprinkler Systems...........................
3/4 7-43 Righ Pressure CO2 Systems................................
3/4 7-45 Fire Hose Stations.......................................
3/4 7-46
~
Foam Systems.............................................
3/4 7-49 3/4.7.8 FIRE BARRIER PENETRATIONS................................
3/4 7-51
~
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operation of one or Both Units...........................
3/4 8-1 Shutdown of Both Un1ts...................................
3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operation of One or Both Units.......
3/4 8-6 A.C. Distribution - Shutdown of Bo th Units...............
3/4 8-7 D.C. Distribution - Operating............................
3/4 8-8 D.C. Distribution - Shutdown.............................
3/4 8-11 RPS Electric Power Monitoring............................
3/4 8-12 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTO R MOD E SWITCH...................................... 3/4 9-1
(
BRUNSWICK - UNIT 2 VIII Amendment No. 89
e.
ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING LIMITING CONDITION FOR OPERATION 3.8.2.5 Two RPS electric power monitoring channels for each inservice RPS MG set or alternate source shall be OPERABLE.
APPLICABILITY: Whenever the respective power supply is supplying power to a RPS bus.
ACTION:
a.
With one RPS electric power monitoring channel for an inservice RPS MG set or alternate power supply inoperable, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service, b.
With both RPS electric power monitoring channels for an inservice RPS MG set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS MG set or alternate power supply from service.
SURVEILLANCE REQUIREMENTS 4.8.2.5 The,above specified RPS power monitoring system instrumentation shall be determined OPERABLE:
a.
At least once per 6 months by performance of a CHANNEL FUNCTIONAL t
TEST, and b.
At least once per 18 months by demonstrating the OPERABILITY of over-voltage, under-voltage, and under-frequency protective instrumentation by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping logic, and output circuit breakers and verifying the following setpoints:
RPS MG SET ALTERNATE SOURCE 1.
Over-voltage
< 129 VAC
< 132 VAC 2.
Under-voltage
> 105 VAC
> 108 VAC 3.
Under-frequency
)_ 57 Hz
)_ 57 Hz t
l l
BRUNSWICK - UNIT 2 3/4 8-12 Amendment No.
_ _ _ _.. _ _ _, _. _. _,.. _ _ _.