ML20151D315
| ML20151D315 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/08/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151D317 | List: |
| References | |
| NUDOCS 8804140132 | |
| Download: ML20151D315 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION a
t.
j WASHINGTON, D. C. 20665
\\,...../
CAROLINA POWER & LIGHT COMPANY, et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PL ANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The appiteation for amendment by Carolina Power & Light Company (the licensee), dated September 29, 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, ana the rules and regulations of the Comission; 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 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 paragraph 2.C.(2) of Facility Operating Licente No. DPR-62 is hereby amended to read as follows:
8804140132 880408 PDR ADOCK 05000324 P
r 2
1 (2)TechnicalSpecifications
-The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.150, are hereby incorporated in the
. license.
Carolina Pcwer & 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 implerented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 8,1988 A
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l ATTACHMENT T0 LICENSE AMENDHENT NO. 150
(
FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 j
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 3-78 3/4 3-78 l
3/4 3-78a 3/4 3-78a 3/4 3-79 3/4 3-79 3/4 3-80 3/4 3-80 i
3/4 3-81 3/4 3-81 r
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INSTRUMENTATION 3/4.3.6 RECIRCULATION PUMP'TRI? AC*UATION INSTRUMENTATION ATVS RECIRCULATION PUMP TRIP (RPT) SYSTEM INSTRUMENTATION LIMITINC CONDITION FOR OPERATION 3.3.6.1 The ATWS-RPT system instrumentation trip systems shown in Table l
3.3.6.1-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.1-2.
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
With an ATWS-RPT system instrumentation trip setpoint less a.
conservative than the value shown in the Allowable Values column of Table 3.3.6.1-2, declare the instrument channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b.
With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.
With the total number of OPERABLE channels less than 3 as required by c.
the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
1.
If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition within one hour.
2.
If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperable.
d.
With one trip system inoperable, restore the inoperable trip system j
to OPERABLE status within 14 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
With both trip systems inoperable, restore at least one trip system e.
to OPERABLE status within one hour or be in at least STAATUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
BRUNSWICK - UNIT 2 3/4 3-78 Amendment No. JJ),150
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INSTRUMENTATION l
SURVEILLANCE RIQUIREMENTS l
4.3.6.1.1 Each ATWS-RPT system instrumentation channel shall be demonstrated i
OPERABLE by the performance of the CHANNEL CHECX, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.6.1-1.
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i 4.3.6.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.
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l BRUNSWICK - UNIT 2 3/4 3-78a Amendment No. 150
Ec:
di TABLE 3.3.6.1-1 5
Q ATUS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION MINIMIM NUMBER OF INSTRUMENT TRIP FIMCTION AND INSTRUMENT NUMBER CIIANNELS PER TRIP SYSTEH(a)
+4 1.
Besctor Vess'el Water Level -
2(b)
Low, Level 2 (821-LT-N024A-2, B-2; B21-LT-N025A-2, B-2)
(821-LTM-N024A-2, B-2; B21-L1N-N025A-2, B-2) 2.
Beactor Vessel Pressure - High 2(b)
(B21-PT-N045A&C, B21-PT-N045B&D)
(521-PTM-N045A&C, 821-PTM-N045B&D) u 5
Y (a)
One trip system may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance provided that the other trip system is OPERABLE.
(b)
Trip System A consists of 4 channels: LT/LTM-N024 A-2, LT/LTM-N025A-2, PT/PTM-N045A, and PT/PTM-N045C Trip System B consists of 4 channels: LT/LTM-N0248-2, LT/LTM-N0258-2, PT/PTM-N0458, and PT/PTM-N045D i
9
,3, t.o O
L
5
-2 TABI.E 3.3.6.1-2 un N
ATWS RECIRCUI.ATION PtJHP TRIP SYSTEM INSTRUMENTATION SETPOINTS a
2 TRIP ALLOWABLE m
TRIP FIAICTION AND INSTRUMENT NUMBER SETPOINT VAI.tJE 1.
>+ 112 inches *
> + 112 inches
- Low, Level 2 (B21-LTM-NO24A-2,B-2; B21-L1M-N025A-2,B-2)
_ 1120 psig
< 1120 psig 2.
Reactor Vessel Pressure - High (B21-PTM-N045A,B,C,D)~
2 u
D u
ln o
N 9
Q-
- Vessel water levels refer to REFERENCE IEVEL ZERO.
On O
M 481 C3
g Op TABLE 4.3.6.1-1 a
N A1MS RECIRCULATION PUHi* TRIP SYSTEM INSTRUMENTATION SURVEILI.ANCE 14Eytill(EHEllTS En CilANNEL CilANNEL FUNCTIONAI.
CIIANNE!.
es TRIP FUNCTION AND INSTRUMENT NtMBER CllECK TEST CAI.l liR ATION 1.
Low, Level 2 (821-LT-NO24A-2, B-2; a) 821-LT-N025A-2, B-2)
NA NA R(b)
(821-LTM-N024A-2, B-2; 821-LTM-N025A-2, B-2)
D H
H 2.
Reactor Vessel Pressure - High (521-PT-N045A, B, C, D)
NA NA R
a ln (821-PTM-N045A, B, C, D)
D H
H 1
(a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.
ky (b) Transmitters are exempted from the monthly channel calibration.
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