ML20100N044
| ML20100N044 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/04/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20100N047 | List: |
| References | |
| DPR-62-A-105, DPR-71-A-078 NUDOCS 8412120550 | |
| Download: ML20100N044 (11) | |
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UNITED STATES g
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n NUCLEAR REGULATORY COMMISSION Op
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,o CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated slune 6, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)
F 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, 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 i
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 Pa'rt 51 of the Commission's regulations and all applicable requirements have been satisfied.
?.
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:
84'i2120550 841204 PDR ADOCK 05000324 P..
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78, 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 COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 4,1984 9
a
4 ATTACHMENT TO LICENSE Af1ENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-1 3/4 3-1 3/4 3-9 3/4 3-9 3/4 7 10 3/4 3-10 i
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(BSEP-1-20) l i
L 3/4.3-INSTRUMENTATION 8-3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
Set points and interlocks are given
.in Table 2.2.1-1.
APPLICABILITY: As shown in Table 3.3.1-1.
' ACTION:
s.
With the requirements for the minimum number of OPERABLE channels not '
satisfied for one trip, system, place the inoperable channel (s) and/or trip j
system in the tripped condition
- within one hour.
1 b.
With the requirementsor the minimum number of OPERABLE channels not f
j satisfied for both trip systems, place at least one trip system ** in l
the tripped condition within one hour and take the ACTION required by 1
Table 3.3.1-1.
c.
The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.
j SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channe1[shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL f
CONDITIONS and at the frequencies shown in Table 4.3.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of, all channels shall be performed at least once per 18 months and shall include j
calibration of time delay relays and timers necessary for proper functioning of the trip system.
4.3.1.3 The REACT 0k PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 roaths. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all c,hannels are tested at least once every N l
times 18 months where N is the total number of redundant channels in a specific reactor trip function.
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- An inoperable channel need not be placed in the tripped condition where l
this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.
- If more channels are inoperable in one trip system than in the other, l
place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.
l BRUNSWICK - UNIT 1 3/4 3-1 Amendment No. 78 L_
-(BSEP-1-20)
INSTRUMENTATION 3/4.3I2'ISOLATIONACTUATIONINSTRUMENTATION-LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3'.3 2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.
APPLICABILITY: As shown in Table 3.3.2-1.
ACTION:
With an isolation actuation instrumentation channel trip setpoint a.
less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the j
inoperable channel in the tripped condition until the channel is
}-
restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel (s) and/or, that trip system in the tripped condition
- within one hour.
c.,
With the requirements for the minimum number of OPERABLE channels not satisfied.for.both trip-systems,. place at least one trip system ** in l
the tripped condition within one ho'dr~and"take the ACTION' required by.
~
Table 3.3.2-1.
'd.
The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CRANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.
4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channela 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.
'4
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.
- If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.
BRUNSWICK - UNIT 1 3/4 3-9 Amendment No. 33, 78
=
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(BSEP-1-20)
' INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) s-4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation function shown-in-Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train such that l
' a both logic chains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific isolation function.
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BRUNS'.JICK - UNIT 1 3/4 3-10 Amendment No. 33, 78
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UNITED STATES
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"h NUCLEAR REGULATORY COMMISSION y
pE WASHIP/GTON, D. C. 20555
- p CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated June 6, 1984, 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 t
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 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 Pa'rt 51 of the Comission's regulations and all applicable requirements have been satisfied.
7.
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:
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~~
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as
. revised throu'gh Amendment No.105,.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 COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications, e
Date of Issuance: December 4,1984 t
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ATTACHMEllT TO LICENSE AMENDMENT NO.105 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Rev'ise..the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-1
. 3/4 3-l' 3/4 3-9
. 3/4 3-9
. i e
4 8
g n.x.
(BSEP-2-20) 3/4.3 ' INSTRUMENTATION 3/4.3.1 ~ REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
Set points and interlocks are given
.g in Table 2.2.1-1.
APPLICABILITY: As shown in Table 3.3.1-1.
' ACTION:
a.
With the requirements for the minimum number of OPERABLE channels not satisfied for one trip, system, place the inoperable channel (s) and/or trip system in the tripped condition
- within one hour.
b.
With the requirements'for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one trip system ** in l
the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.
c.
The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.
L.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel.shall be demonstrated OPERABLE by the performance of the CRANNEL CHECK, CRANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.
j 4.3.1.2 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.
4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a l
specific reactor trip function.
"q i
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the I
inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.
l
- If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.
j BRUNSWICK - UNIT 2 3/4 3-1 Amendment No.105 i
-.,.m n.-.
r-(BSEP-2-20)
INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM i
RESPONSE TIME as shown in Table 3.3.2-3.
APPLICABILITY: As shown in Table 3.3.2-1.
ACTION:
With an isolation actuation instrumentation channel trip setpoint a.
1ess conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel (s) and/or tha'e trip system in the tripped condition
- within one hour.
With the requirements for the minimum number of OPERABLE channels c.
not satisfied for both trip systems, place at least one trip system **
l t
in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.
d.
The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITI.ON 5.
SURVEILLANCE REOUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OP'.RABLE by the performance of the CRANNEL CHECK, CRANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL l
CONDITIONS and at the frequencies shown in Table 4.3.2-1.
4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include I
calibration of time delay relays and timers necessary for proper functioning-of the trip system.
L
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken..
- If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.
BRUNSWICK - UNIT 2 3/4 3-9 Amendment No. 33, 105 y,
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