ML20248C918
| ML20248C918 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/29/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248C923 | List: |
| References | |
| NUDOCS 9806020276 | |
| Download: ML20248C918 (12) | |
Text
_ _ _ - _ _ - _ _ - _ _ _ _ _ - _ _
$a cro g
- i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 BRUNSWlCK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.198 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 November 15,1995, 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:
9806020276 980529 PDR ADOCK 05000324
)
l (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised i
through Amendment No.198, 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 of issuance.
1 f
FOR THE NUCLEAR REGULATORY COMMISSION I
kS
~
n Pao-Tsin Kuo, Acting Directo Project Directorate ll-1
{
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of issuance: May 29, 1998 i
i l
ATTACHMENT TO LICENSE AMENDMENT NO.198 FACILITY OPERATING LICENSE NO. DPR-71 l
DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.
Remove Paoes insert Paoes Xil Xil 3/4 8-15 3/4 8-15 B 3/4 8-2 1
c j
c
-o ME BASES SECTION M
3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION........................................
B 3/4 7-lh 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...................
B 3/4 7-lh 3/4.7.5 SNUBBERS................................................
B 3/4 7-2 t
3/4.7.6 SEALED SOURCE CONTAMINATION.............................
B 3/4 7-3
{
3/4.7.7 FIRE SUPPRESSION SYSTEMS (Del eted)...................... B 3/4 7-4 f
3/4.7.8 FIRE BARRIER PENETRATIONS (Deleted).....................
B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS..................................
B 3/4 8-1 1
3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING.....B 3/4 8-2 l
3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.....................................
B 3/4 9-1 1
3/4.9.2 INSTRUMENTATION.........................................
B 3/4 9-1 3/4.9.3 CONTROL R0D P0SITION....................................
B 3/4 9-1 3/4.9.4 DECAY TIME..............................................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS..........................................
B 3/4 9-1 3/4.9.6 CRANE AND HOIST OPERABILITY.............................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L....................
B 3/4 9-2
{
)
3/4.9.8 WATER LEVEL-REACTOR VESSEL, and
{
3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L...................
B 3/4 9-2
-3/4.9.10 CONTROL ROD REM 0 VAL.....................................
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY...........................
B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)...................
B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS..........................
B3/410-1 3/4.10.4 RECIRCULATION L00PS.....................................
B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER.....................................
B 3/4 10-1 BRUNSWICK - UNIT 1 XII Amendment No.198 l
I i
ELECTRICAL POWER SYSTEMI 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 abuve specified RPS power monitoring system instrumentation shall be determined OPERABLE:
- a. By performance of a CHANNEL FUNCTIONAL TEST each time the plant is in COLD SHUTDOWN for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed in the previous 6 months, 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 l
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 s 129 VAC s 132 VAC 2.
Under-voltage a 105 VAC
= 108 VAC 3.
Under-frequency a 57 Hz a 57 Hz BRUNSWICK - UNIT 1 3/4 8-15 Amendment No.198 l
l i
5 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING The CHANNEL FUNCTIONAL TEST is only required to be performed while the plant is in a condition in which the loss of the RPS bus will not jeopardize steady state power operation (the design of the system is such that the power source must be removed from service to conduct the surveillance). The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is intended to indicate an outage of sufficient duration to allow scheduling and proper performance of the surveillance.
The above requirements of the surveillance frequency are based on guidance provided in Generic Letter 91-09.
l l
BRUNSWICX - UNIT I B 3/4 8-2 Amendment No.198 l
i
p Rig,
y p
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665 4001
\\..... /
CAROLINA POWER & LIGHT COMPANY. et al.
3 DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERAT!NG LICENSE i
Amendment No. 228 License No. DPR-62 1.
The Nucleur Regulatory Commission (the Commission) has found that:
g A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated November 15,1995, compiics 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 we 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
- mendment 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 pub lic; 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 arnendad 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. CPR-62 s hereby amended to read as follows:
i
i (2)
Technitd Specifications l
The Technical Specifications contained in Appendices A and B, as revised i
through Amendment No. 228, are hereby incorporated in the license. Carolina l
Power & Light Company shall operate the facility in accordance with the Technict) Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISS!ON
~
Pao-Tsin Kuo, Acting Directo l
Project Directorate 11-1 i
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical J
Specifications Date of issuarice: May 29,1998 i
i ATTACHMENTTO LICENSE AMENDMENT NO. 223 FACILITY OPERATING LICENSE NO. DPR-62 i
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 Paoes insert Paoes XII XII 3/4 8-15 3/4 8-15 B 3/4 8-2 l
4 k
a
lEQEE BASES SECTION MQ1 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION........................................
B 3/4 7-lh 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...................
B 3/4 7-lh 3/4.7.5 SNUBBERS................................................
B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION.............................
B 3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS (Deleted).......................B 3/4 7-4 3/4.7.8 FIRE BARRIER PENETRATIONS (Deleted).....................
B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS.................................
B 3/4 8-1 1
3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING... 3 3/4 8-2 1
3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.....................................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................
B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION....................................
B 3/4 9-1 3/4.9.4 DECAY TIME..............................................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS..........................................
B 3/4 9-1 3/4.9.6 CRANE AND HOIST OPERABILITY.............................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L....................
B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L...................
B 3/4 9-2 3/4.9.10 CONTROL R0D REM 0 VAL.....................................
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIriARY CONTAINMENT INTEGRITY...........................
B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)...................
B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS..........................
B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS.....................................
B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER.....................................
B 3/4 10-1 BRUNSWICK - UNIT 2 XII Amendment No. 228 I
' f1ECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING l
LIMITING CONDITION FOR OPERATION 3.8.2.5 Two RPS ele.ctric 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 char.nels for an inservice RPS MG set or alternate power supply ir. operable, 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. By performance of a CHANNEL FUNCTIONAL TEST each time the plant is in COLD SHUTDOWN for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless
' er#;;mied in the previous 6 months, 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 s 129 VAC s 132 VAC 2.
Under-voltage a 105 VAC m 108 VAC 3.
Under-frequency a 57 Hz a 57 Hz BRUNSWICK - UNIT 2 3/4 8-15 Amendment No. 228 l
3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING The CHANNEL FUNCTIONAL TEST is only required to be performed while the plant is in a condition in which the loss of the RPS bus will not jeopardize steady state power operation (the design of the system is such that the power source must be removed from service to conduct the surveillance). The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is intended to indicate an outage of sufficient duration to allow scheduling and proper performance of the surveillance.
The above requirements of the surveillance frequency are based on guidance provided in Generic Letter 91-09.
i l
BRUNSWICK - UNIT 2 B 3/4 8-2 Amendment No. 228 l
t