ML20034C237
| ML20034C237 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/23/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034C238 | List: |
| References | |
| NUDOCS 9005020208 | |
| Download: ML20034C237 (10) | |
Text
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![taKaap UNITED STATES -
NUCLEAR REGULATORY. COMMISSION e
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CAROLINA POWER & LIGHT COMPANY, et al.
DOC KET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE k
Amendnent No.141 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission)-has found that:
A.
The application for aandnent filed by Carolina Power & Light Comany.
1 (the licensee), dated February 16,.1990, coglies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 6nd the Commission's rules and regulations set-forth in 10 CFR Chapter I; D.
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 amendant can be conducted without endangering the health-and safety of the public, and-(ii) that such activities will be conducted in cogliance with the Comission's regulations;-
D.
The issuance of this amendment will not-be-inimical to the-h common defense and security or to the health and safety of the l
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.
a 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in' the attachment to this license anendment; and paragraph 2.C.(2) of facility Operating License No. DPR-71 is.
hereby amended to read as follows:
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(2) Techlical Specifications The Technical Specifications contained in Appendices:A and B, as
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revised through-Amendment No.141, are hereby incorporated in the,
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. license.. Carolina Power & Light Company shall operate the. facility?
- l in accordance with the Technical Specifications.
3,
-This license amendment is effective as of the date of its issuance andL
. shall be iirplenented within 60_ days of issuance.:
FOR =THE NUCLEAR REGULATORY COMMISSION j
i e
Orignal. signed by:
Elinor G. Adensam, Director Project Directorate 11-1 Division of -Reactor Projects. I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: 4/23/90 5
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1 ATTACHMENT TO LICENSE-AMENDMENT NO.141
-j FACILITY OPERATING LICENSE NO. DPR-71 J
DOCKET NO. 50-325 1
Replace the following pages of the Appendix A Technical l Specifications with-the enclosed pages.
The revised areas are indicated by 'carginal lines.
Remove Pages Insert Pages 1
3/40-2 3/4 0-P B 3/4 0-2 B 3/4 0-2 d
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@ LICABILITY 4
i SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements'shall be applicable during..the OPERATIONAL CONDITIONS or-other' states specified for individual. Limiting Conditions for' Operation unless otherwise stated.in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement snal! be performed within the specified time interval with a maximum allowable extension not to' exceed 25% of the surveillance interval.
4.0.3 Performance of a Surveillance Requirement within -the :specified.' time interval'shall: constitute' compliance with OPERABILITY. requirements for a aj Limiting Condition.for Operation and associated ACTION statement s unless otherwise required'by the= specification.. Surveillance requirements do.not'
- have to be performed on inoperablej equipment.
4.0.4 Entry into an-OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance' Requirement (s) associated with the Limiting Condition for Operationf have been, performed within the ~ applicable.
-surveillance. interval.or as otherwise.specified.
4.0.5 ' Surveillance Requirements f or inservice inspection and testing of ' ASME.
-Code Class 1, 2, and 3 components shall be applicable as follows:
During the time period:
a.
1.
From issuance.of the Facility Operating License to the start of-facility commercial operation, inservice testing of ASME Code.
4 Class 1, 2, and 3 pumpo and valves shall be performed in accordance.with Section-XI of the ASME Boiler and Pressure Vessel Code, 1974' Edition, and Addenda through Winter 1975 except where specific written relief has been granted by the comission.
2.
Following start of f acility comercial operation, ' inservice inspection of ASME Code Class 1, 2, and'3 components 'nd.
a inservice testing of.~ASME Code, Class 1, 2,'and:3= pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as.
required by 10 CFR 50, Section 50.55a(g), except where specific written-relief has been granted by the Commission. pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
'i BRUNSWICK - UNIT 1 3/4 0-2 Amendment No. din 141 1
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b APPLICABILITY l
BASES 4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are meet and will'be performed during the OPERATIONAL CONDITIONS for which the Limiting Conditions for-Operation are applicable. Provisions for additional surveillance activities
.)
j to be performed without regard to the applicable OPERATIONAL CONDITIONS are -
provided in the individual _ Surveillance Requirements.
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'4. 0. 2 The provisions of this specification provide allowable tolerances i
for perf orming surveillance ~ activities 'beyond' those specified in the ' nominal l
surveillance interval. These tolerances are necessary to provide operational j
flexibility because'of scheduling and performance considerations. The phrase.
j "at_least" associated with a surveillance frequency does.not negate this n
allowable tolerance value and permits the - perf ormance of more: f requent surveillance activities.
It is-not intended thatLthis' provision be'used=
I repeatedly as a convenience to extent surveillance intervals beyond that-specified for surveillance'that are not performed during refueling outages.
j The tolerance value is sufficiently restrictive to ensure that the reliability associated with the surveillence activity is not :significantly j
degraded beyond that obtained from the nominal specified interval.
I 4.0.3 The provisions of 'the specification set forth the criteria for l
determination of compliance with the OPERABILITY requirements of the Limiting j
Conditions for Operation. Under this criteria, equipment, systems, or components are assumed to be OPERABLE if the associated surveillance activities have been' satisfactorily performed within the specified time-interval.
Nothing-in this provision is to.be construed.aa defining equipment, systems, or components OPERABLE, when such items are found or known to be inoperable although still meeting the. Surveillance Requirements.
4.0.4 This specification ensures that surveillance activities associated with a Limiting Condition for Operation have' been performed ~within the specified time interval prior to entry into an applicable CONDITION.
The intent of this provision is to. ensure that surveillance activities have been satisf actorily demonstrated on a current basis.as required to meet the OPERABILITY requirements of the Limiting Condition for' Operation.
Under the terms of this specification, for example,~ during intical plant startup or following extended plant outage, the applicable surveillance s
activities must be performed within the stated surveillance interval prior to-placing or returning the system or equipment into OPERABLE status.
Exceptions a
to some surveillance activities have been provided for an individual specifications.
BRUNSWICK - UNIT 1 B 3/4 0-2 Amendment No.
141 i
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UNITE'D STATES -
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NUCLEAR REGULATORY COMMISSION
%...../y WASHINGTON, D. C. 20555 QROLINA POWER & LIGHT COMPANY - et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT,' UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE I
i Amendment No.173 i
License No,' DPR 1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applice. con for amendment filed by Carolina Power & Light Comparty H
(the licensee), dated February:16,.1990, complies with the standards-and requirements of_ the Atomic Energy Act of 1954, as~ amended (the Act), and the Commission's nJ1es and regulations set.forth in 10 CFR. Chapter I; i
B.
The facility will operate -in conformity-with the-application, the-I provisions of the Act and the rules and regulations of the o
Comni ssion; 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 a
conducted in compliance with the Commission's regulations; D.
The issuan 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 a11 applicable"r_equirements -
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical I
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:
4 2
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.173. are hereby incorporated in the
-license., Carolina Power & Light Company shall operate the facility-in accordance with the Technical Specifications.
3.
This license amenoment is effective as'of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Orignal signed by:
Elinor G. Adensam Director Project Directorate 11-1 Division of Reactor Projects I/II-Office of Nuclear Reactor Regulation 1
~1 Attachrent:
i Changes to the Technical Specifications j
Date of Issuance: 4/23/90 i
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OFFICIAL RECORD COPY a
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ATTACHMENT T0 LICENSE AEll0 MENT' NO.173-FACILITY OPERATING' LICENSE NO. DPR-62 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-1 3/4 0-2 3/40-2 i
B 3/4 0-2 B 3/4 0-2 if,e.
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.----i-,.-..,,.,
APPLICABILITY SURVEILLANCE REQUIREMENTS
';4.0.1 Surveillance Requirements shall be applicable 'during the OPERATIONAL CONDITIONS or other' states specified for individual ~ Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval, 4.0.3-Performance of a Surveillance Requirement within the specified time interval shall-constitute compliance with OPERABILITY requirements for a Limiting Condition f or Operation and associated ACTION' statement s ' unless otherwise required.by the specification.
Surveillance requirements do not have to be performed on inoperable equipment.:
't 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable state 1
shall not be made unless-the Surveillance-Requirement (s) associated with the Limiting Condition for Operation have -been: performed' within the applicable surveillance' interval'or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and-testing of ASME-Code Class 1, 2,'and 3 components shall be applicable as follows:
a.
During the time periodt 1.
From issuance of the Facility Operating License to the start of facility commercial operation, inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and. Addenda through Winter 1975 except where specific written relief has been granted by the commission.
2.
Following start of -f acility commercial' operation, inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and-valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as.
required by 10 CFR 50, Section,50.55a(g), except where specific written relief has b6en granted by the Commission pursuant to 10 CFR 50,'Section 50.55a(g) (6) (i).
^
SRUNSWICK - UNIT 2 3/4 0-2 Amendment No. E3, 173 T
1 3
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- APPLICABILITY BASES 4.0.1.This specification provides that surveillance activities,necessary.
to ensdre the Limiting. Conditions for Operation are' meet and will be. performed during the OPERATIONAL CONDITIONS for which the Limiting Conditions ~ for' Operation are applicable.. Provisions for additional surveillance activities to be 'perf ormed without regard to the applicable.0PERATIONAL CONDITIONS are provided in the individual Surveillance Requirements.
4.0.2.The provisions of this specification-provide allowable tolerances for performing surveillance activities beyond those specified in the. nominal surveillance interval. These tolerances are necessary.to. provide operational.
flexibility because of scheduling and performance considerations..The phrase
)
"at.least" associated.with a surveillance frequency does notinegate this allowable tolerance value and permits. the -performance of more f requent.
i surveillance activities.
It is not intended that this provision be-used.
repeatedly as a: convenience _ to extent surveillance intervals beyond that specified for: surveillance - that are-not performed during refueling' outages, j
u The: tolerance value is'sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal'specified interval.
4.0.3. The-provisions of the' specification set forth the criteria ~for i
determination of compliance with the OPERABILITY requirements of the Limiting Conditions of Operation. Under this criteria, eqaigment, systems, or components are assumed to be OPERABLE iffthe associated surveillance activities have been satisf actorily performed within the specified-time interval. Nothing in this provision is-to be: construed as' defining equipment,
{
systems, or campone.ts SPERABLE, when such items are found or known to be.
R inoperable although s.ill meeting the Surveillance Requirements.
4.0.4 This specification ensures that surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an applicable CONDITION.
The intent of this provision is to ensure that surveillance' activities _have been q
satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.
I b
BRUNSWICK - UNIT 2 B 3/4 0-2 Amendment No. - 173 i
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