ML20005D725
| ML20005D725 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/08/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005D726 | List: |
| References | |
| NUDOCS 8912140359 | |
| Download: ML20005D725 (10) | |
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UNITED STATES h
NUCLEAR REGULATORY COMMISSION
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i CAROLINA POWER & LIGHT COPPANY. et al.
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DOCKET NO. 50-324 4
i ERUNSWICK STEAM ELECTRIC PL ANT tl NIT 2 AMENDPENT 10 FACILITY OPERATING LICENSE Amencment No. 169 License No. Opp-62 1.
The huclear Regulatory Contoission (the Commission) has found thet:
A.
The application for amencrent by Carolina Power & Light Company (the licensee), dated s'une 9,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amenced (the Act),
eno the Ccnmission's rules anc regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, anc the rules and regulations of the Commission; C.
Thes e is reasonable assurance (i) that the activities authorized by inis anencment can be conoucted without endangering the health 000 safety Of the public, and (ii) that such activities will be conoucted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical tc the con. mon defense end security or to the health and safety of the public; ano l
E.
The issuance of this amencment is in accorcence with 10 CFR Part 51 of the Commission's regulations one all applicable recuirements have been satisfied.
2.
Accorcingly, the license is amenced by chenges to the Technical Specifications, 6s indicatec in tne attachment to this license amendment; dnd paragraph 2.C.(2) of Facility Operating License ho. DPR-62 is hereby amenced to react as follows.:
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(2) Technical Specifications The Technical Specifications contained in Appenoices A ano B as revised through Amencrcent No.169, are hereby incorporated in the license.
Carolina Power & Light Compary shall cperate the factitty in decorodrce with tt.e Technical Specifications.
3.
This license amendment is effectise as of the date of its issLance and shall be irrplementet. within 60 cays of issuance.
FOR THE NUCLEAR REGULATOP.Y COMMISS10N Elir.cr G. Adensar, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachnent:
thanges to the Technical Specifications Date et issuance: November 8, 1989 h
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ATTACHMENT TO LICEhSE AMENDMENT NO.169 FACILITY OPERATING LICEASE ?!0. OPR-62 1
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00CKET NO. 50-324 4
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Replace the following pages of the Appencia A Technical Specifications
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with the enclosta pages.
The revisec areas are indicateo by marginal lines, j
Remove Pages Insert Pages 2-1 2-1 E-1 5-1 e
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,2. 0 SAFETY LIMITS AND LIMITINC SAFETY SYSTEM SETTINCS 2.1 SAFETY LIMITS THEP. MAL POWER (Low Pressure :r Low Flow) r 2.1.1 THERMAL POWER shall not exceed 251 of RATED THERMAL POW t
10% of rated f'sw. reactor vessel steam dome pressure less than 800 psia or core flow less tha APPLICABILITY: CONDITIONS I and 2.
E ACTION:
With THERKAL POWER exceeding 25% of RATED THERMAL POWER and the rea steam dome pressure less than 800 psia or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
THERMAL POWER (High Pressure and High Flow)
L 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less tha with the reactor vessel steam dome pressure greater than 800 psia and core flow greater than 10% of rated flow.
APPLICABILITY: OPERATIONAL CONDITIONS I and 2 ACTIOW1 With MCPR less than 1.06 and the reactor vessel steam dome pressure greater than 800 psia and core flow greater than 10% of rated flow, i
be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
REACTOR CDOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.
i APPLICABILITY CONDITIONS 1, 2, 3, and 4 ACTIONI With the reactor coolant system pressure, as measured in the reactor vessel steam done, above 1325 peig, be in at least HOT SHUTDOWN with reactor coolant system pressure < 1325 paig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
l BRUNSWICK - UNIT 2 2-1 Amandment No. 169 i
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k 5.0 DESICW FEATURES 5.1 SITE EXCLUS!CW AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.
LOW POPULA* ION 20NE t
5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1.
of affluent For the purpose release calcu1 1tions, the boundary f or atmospheric releases is the to dilution in the Atlantic Ocean. SITE BOUNDARY and the bout.dary for liq 5.2 CONTAIRMENT CONFICURATION 5.2.1 The PRIMARY CONTAIRMENT is a steel-lined, reinforced concrete structure composed of a series of vertical right form a drywell.
cylinders and truncated cones which series of vents. This dryvell is attached to a suppression chamber through a vessel in the shape of a torus.The suppression chamber is a concrete, steel-lined pressu The primary containment has a minimum free air volume of 288,000 cubic. feet.
DESICN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained fort Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperatures dryvell 300'F 4
Suppression chamber 200'r Maximum external pressure 2 psig.
c.
5.3 REACTOR CARE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies limited to the following fuel types BP8s8R, CE8 8EB, and CESx8NB.
l BRUNSWICK - UNIT 2 5-1 Amendment No. 169
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UNITED STATES f
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CAROLINA POWER & LIGHT COPPaNY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAN ELECTRIC PLANT UNIT 2 AtdENDMENT TO FACILITY OPERATING LICENSE Amencment No. 169 License No. OPR.Et 1.
The huclear Regulatory Contnission (the tcmmission) has found that:
A.
The application for amencrent by Carolina Fower &
t requirements of the Atomic Energy Act of 1954, as amenced (the Act),
and the Conniission's rules anc regulations set forth in 10 CFR Chapter I; 1
B.
The facility will operate in conformity with the application, the provisiens of the Act, anc the rules and regulations of the Commission; C.
There is reasonable assurance (i) tnat the activities authori:ed by tnis an=ncment can be conouctec without endangering the health one sofsty of the public, one (ii) that such activities will te concuctec in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical tc the con.mcn cefens and security or to the neelth and safety of the public; ano E.
The issuance of this amenccent is in accorcanc. with 10 CFR Part 51 of the Commission's regulations one oil applicable recuirements have been satisfied.
2.
Accorcingly, the license is an no c by cnonges to tre Technical Specifications, 6s indicatec in tne attachment to this lictns. atendment; and paragraph 2.C.(2) of Facility Operating License ho. CPR-62 is rareby amenced to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appenoices A anc B, as revised through Amercr.:ent ho.169, ere hereby incorporated in the license.
Carolina Power & Light Compary shall cperate the facility in eccorcerce with the Technical Specifications.
3.
This license amendment is effectiv6 as of the cate of its isscance and shall be in.plemented within 60 cays of issuance.
FOR THE NUCLEAR REGULATOP.Y COMMISSION Elir.cr C. Adensam, Director Project Directorate 11-1 Divisiotr of Reactor Projects - I/11 Office of Nuclear Reactor Regulaticn
Attachment:
thanges to the Technical Specifications Date ct Issuance: Noveinber 8,1989 t
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ATTACHMENT TO LICEhSE AMENDHENT N0.169 FACILITY OPERATING LICEhSE ?!0. OPR-62 00CKET NO. 50-324 keplace the following pa with the enclosee pages.ges of the Appencix A Technical Specifications The revised areas are indicatec by marginal lines.
_ Remove Pages insert Pages 2-1 51 2-1 5-1 5
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2.0 SAFETY LIMITS AND LIMITINC SAFETY SYSTEM SETTINCS 1
2.1 SAFETY LIMITS t
IMERMAL POWER (Low Pressure or Low Fisv) 2.1.1 THERMAL POWER snalt not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than SCO psia or core flow less tha 10% of rated flow.
n APPLICABILITY! CONDITIONS 1 and 2.
ACTION 9
With THERMAL POWER exceeding 25% of RATED THERMAL POWER and steam dome pressure less than 800 psia or core flow less than 10% of rated r vessel flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
IHERMAL_ POWER (High Pressure and High Flow) 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not t
with the reactor vessel steam dome pressure greater than 800 psia and be less than 1.06 flow greater tnan 10% of rated flow.
core APPLICABILITYt OPERATIONAL CONDITIONS 1 and 2 ACTIONI
'With MCPR less than 1.06 and the reactor vessel steam dome pressure great than 300 psia and core flow greater than 10% of rated flow, SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
be in at least HOT REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, snall no exceed 1325 psig.
APPLICABILITY CONDITIONS 1, 2, 3, and 4 ACTIONt With the reactor coolant steam done, above 1325 pois, be in atsystem pressure, as sensured in the reactor vessel system pressure r 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.least HOT SHUTDOWN with reactor coolant BRUNSWICK - UNIT 2 2.g Amendment No.169
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5.0 DESIGN FEATURES
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5.1 SITE EXCLUS*CV AREA 5.1.1 The exclasion area shall be as shown in Figure 5.1.1-1.
' LOW POP"LAT*0N 2CNE 5.1.2 The low peputation zone shall be as shown in Figure 5.1.2-1.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1.
of effluent SITE BOUNDARY and the boundary for liquid release to dilution in the Atlantic Ocean.
r or 5.2 CCNTAIKMENT CONFICURATION 5.2.1 The PRIMARY CONTAINMENT is a stee!-lined, reinforced concrete structu composed of a series of vertical right form a drywell.
cylinders and truncated cones which series of vents. This drywell is attached to a suppression chamber through a vessel in the shape of a torus.The suppression chamber is a concrete, steel-lined pres The primary containment has a minimum free air volume of 288.000 cubic feet.
OESICN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained fort Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperature:
drywell 300*F Suppression chamber 200*F Maximum external pressure 2 psig.
c.
i 5.1 REACTot Catt FUEL ASSEMBLIES i
5.3.1 The reactor core shall contain 560 fuel assemblies limited to the following fuel types:
BP8 8R, CE8x8EB, and CESx8NB.
l BRUNSWICK - UNIT 2 5-1 Amendment No. 169
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