ML20235G226
| ML20235G226 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/24/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235G230 | List: |
| References | |
| NUDOCS 8709290498 | |
| Download: ML20235G226 (12) | |
Text
_ _ - _ _ - _ _ _
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UNITED STATES j
g NUCLEAR REGULATORY COMMISSION
- j WASHINGTON, D. C. 20555
\\...../
CAROLINA POWER & LIGHT COMPANY, et al.
DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 License No. DPR-71 1
1.
The Huclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (thelicensee),datedAugust 28, 1985, as supplemented May 15. 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, and 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 l
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:
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8709290498 870924
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PDR ADOCh 05000324 P
PDR l
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- l (2) Technic'al' Specifications The: Technical Specifications contained in'AppendicesLA and B, as.
revised through. Amendment No.112, are hereby incorporated in'the license. -The licensee shall operate-the facility in accordance with the. Technical Specifications..
'3.
This license amehdment is effective as of'the date of its' issuance and l
shall.be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION JS/
/Elinor:G..'Adensam, Director Project Directorate II-1 Division of. Reactor Projects I/II J
Attachment:
ChangesLto the Technical 1
Specifications Date of Issuance: September 24, 1987 ll 1
l h-N OGC-B M D:PD21:0 P LA:
,., RPR PM:PD21:DRPR
- JA ESylvester/s h E. C le EAdensam-9/
87 9 / tc)/87 9/6/87 7 //%/87 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 112 FACILITY OPERATING LICENSE NO. DPR-71
)
DOCKET NO. 50-325 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 1-17 3/4 1-17 3/4 3-41 3/4 3-41 l
3/4 3-43a 3/4 3-43a o
l 1
(BSEP-1-64)
P
' REACTIVITY CONTROL SYSTEMS ROD BLOCK HONITOR LIMITINC CONDITION FOR OPERATION 3.1.4.3 Both Rod Block Monitor (RBM) channels shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.
ACTION:
With one RBM channel inoperable, POWER OPERATION may continue a.
l provided that either:-
t 1
1.
The inoperable RBM channel is restored to OPERABLE status within 1
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or l
2.
The redundant RBM is demonstrated OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the inoperable RBM is restored to i
OPERABLE status, and the inoperable RBM is restored to OPERABLE j
status within 7 days, or 3.
THERMAL POWER is limited such that MCPR will remain above 1.07 assuming a single error that results in complete withdrawal of any single control rod that is capable of withdrawal.
1 Otherwise, trip at least one rod block monitor channel.
I b.
With both RBM channels inoperable, trip at least one rod block i
monitor channel within one hour.
1 SURVEILLANCE REQUIREMENTS 4.1.4.3 Each of the above required RBM channels shall be demonstrated OPERABL,E by performance of a CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION at the frequencies and during the OPERATIONAL CONDITIONS specified in Table 4.3.4-1.
l BRUNSWICK - UNIT 1 3/4 1-17 Amendment No. 23,112 L -__ __-__-_____-_________- --____ -
(BSEP-1-64)
TABLE 3.3.4-1 (Continued)
CONTROL ROD WITHDRAWAL-BLOCK INSTRUMENTATION NOTE i
I (a) The minimum number of OPERABLE CHANNELS :say be reduced by one'for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.in one of the trip systems for maintenance and/or-testing except
]
for Rod Block Monitor function.
j (b) This function is bypassed if detector is reading >100 cps or the IRM channels are'on range 3 or higher.
(c) This function is bypassed when the associated IRM channels are on range 8 i
or higher.
{
.i (d) A total of 6 IRM instruments must by OPERABLE.
e (e) This function is bypassed when the IRM channels are on range 1.
When THERMAL POWER is greater than or equal.to 30% of RATED THERMAL POWER.
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
i This signal is contained in the channel A logic only.
I l
BRUNSWICK - UNIT 1 3/4 3-41 Amendment No. 5), 197, 112
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- l WASHINGTON, D. C 20555 '
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CAROLINA POWER & LIGHT COMPANY, et al.
DOCKET NO. 50-324' BRUNSWICK STEAM ELECTRIC PLANT,: UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
L Amendment No. 139 License No. DPR-62 1',
4 1.
The Nuclear Regulatory Comission (the Commission), has found that:
Y A.
The application for. amendment filed by Carolina Power & Light Company i
(the licensee), dated August 28, 1985, as supplemented May 15, 1987, 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;,
i B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1
C.
There is reasonable assurance (1) that the activities authorized t
by this amendment can be conducted without endangering the health q
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 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 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-62 is hereby amended to read as follows:
l l
- (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as
)
revised through Amendment No.139, are hereby incorporated in the license. The licensee shall operate the facility in accordance
-1 1
with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II l
Attachment:
Changes to the Technical Specifications Date of Issuance: September 24, 1987 f
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ATTACHMENT TO LICENSE AMENDMENT N0. 139 FACILITY OPERATING LICENSE NO. DPR-62 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 Pages Insert Pages 3/4'1-17 3/4 1-17 3/4 3-41 3/4 3-41 3/4 3-43a 3/4 3-43a i.
4
)
_L____.____--_----_-____-_--____-_--____--
___--_._-___--____L
(BSEP-2-59) l REACTIVITY CONTROL SYSTEMS ROD BLOCK MONITOR LIMITINC CONDITION FOR OPERATION 3.1.4.3 Both Rod Block Monitor (RBM) channels shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.
ACTION:
With one RBM channel inoperable, POWER OPERATION may continue a.
provided that either:
1.
The inoperable RBM channel is restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or o
2.
The redundant RBM is demonstrated OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at l
1 east once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the inoperable RBM is restored to I
OPERABLE status within 7 days, or 3.
THERMAL POWER is limited such that MCPR will remain above 1.07, assuming a single error that results in complete withdrawal of any single control rod that is capable of withdrawal.
l Otherwise, trip at least one rod block monitor channel;.
b.
With both RBM channels inoperable, trip at least one rod block monitor channel within one hour.
SURVEILLANCE REQUIREMENTS 4.1.4.3 Each of the above required RBM channels shall be demonstrated l
OPERABLE by performance of a CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION at the frequencies and during the OPERATIONAL CONDITIONS specified in Table 4. 3. 4 - l'.
I i
i l
BRUNSWICK - UNIT 2 3/4 1-17 Amendment No. ($,139 j
i
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1 (BSEP-2-59)
~^
TABLE 3.3.4-1 (Continued) 1 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE (a) The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in one of the trip systems for maintenance and/or testing except for Rod Block Monitor function.
(b) This function is bypassed if detector is reading >100 cps or the IRH i
channels are on range 3 or higher.
(c) This function is bypassed when the associated IRM channels are on range 8 or higher.
l (d) A total of 6 IRM instruments must be OPERABLE.
\\
(e) This function is bypassed when the IRM channels are on range 1.
I When THERMAL POWER is greater than or equal to 30% of RATED THERMAL j
POWER.
i With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
j l
i This signal is contained in the Channel A logic only.
i i
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l BRUNSWICK - UNIT 2 3/4 3-41 Amendment No. ES, 732,139
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