ML20073C083
| ML20073C083 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/04/1983 |
| From: | Clark R, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20073C090 | List: |
| References | |
| DPR-51-A-075, NPF-06-A-042 NUDOCS 8304130012 | |
| Download: ML20073C083 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION E
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT t'O.1 AMENDMENT TO FACILITY OPERATING LICENSE Amndnent No. 75 License No. DPi-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power a Light Company (the licensee) dated flay 28, 1982, as modified January 14, 1983, 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; B.
The facility will operate in confomity with the application, the provisions of the Act, ad the rules and regulations of the Comission; C.
There is resonable assurance (1) that the activities authorized by this arnendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Consission's regulations; D.
The issuance of this amendment will not be inimical to the cosmon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable mquirements have been satisfied.
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Accordingly,thelicenseisamendedhychangestotheTechnical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No. 75. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the'
+ Technical Specificati,ons.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION flLE
/ Johh F. Stolz, Chief Opefating Reactors Branch F, sDivision of Licensing Attachmcrt:
Changes to the Technical Specifications Date of Issuance: April 4,1983 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 75
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FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Tec'inical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicatinc the area of chance.
Remove Pages insert Pages 67 67 G7a 67a O
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4 SURVEILLANCE STANDARDS Specified surveillance intervals may be adjusted plus or mint ?5 percent to accommodate normal test and surveillance schedules.
The maxin,sn. combined interval.for any 3 consecutive tests shall not exceed 3.25 times the specified surveillance interval.
Surveillance requirements are not applicable when the plant operating co1ditions are below those requiring i
operability of the designated component.
However, the required surveillance must be performed prior to reaching the operating conditions requiring operability.
For example, instrumentation requiring twice per week surveillance' when the reactor is critical need not have the required surveillance when the reactor is shutdown.
Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Londition for Operation.
Exceptions to these requirements are stated in the individual specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.1 OPERATIONAL SAFETY ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.
Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
Specification The minimum frequency and type of surveillance required for a.
reactor protective system and engineered safeguards system instrumentation when the reactor is critical shall be as stated in Table 4.1-1.
b.
Equipment and sampling test shall be performed as detailed in Tables 4.1-2 and 4.1-3.
Discrepancies noted during surveillance testing will be corrected c.
and recorded.
d.
A power distribution map shall be made to verify the expected power distribution at periodic intervals at least every 10 effective full power days using the incore instrumentation detector system.
Aiaendment No. 25, 75 67
i Bases The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting.Qonditions for Operation.
Under these 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 as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.
Check Failures such as blown instrument fuses, defective indicators, faulted amplifiers which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system.
Furthermore, such failures are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear plant systems, when the plant is in operation, the minimum checking frequency stated is deemed adequate for reactor system instrumentation.
Calibration Calibration shall be performed to assure the presentation and acquisition of accurate information.
The nuclear flux (power range) channels shall be calibrated at least twice weekly (during steady state operating conditions) against a heat balance standard to compensate for instrumentation drift.
During nonsteady state operation, the nuclear flux channels shall be calibrated daily to compensate for instrumentation drift and changing rod patterns and core physics parameters.
9 Aaendaent No. 75 67a
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ARKANSAS POWER & LIGHT COMPANY 4
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No 42 License No. NPF-6 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas. Power a Light Company i
(the licensee) dated flay 28, 1982, as modified January 14, 1983, complies with the standards and requirements of the Atomic Energy l
Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity 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 (11) that such activities will be l
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the cosmon defense and security or to the health and safety of the public; 4
and E.
The issuance of this amendment is in accordance with 10 CPR Part 4
i 51 of the Comission's regulations and all applicable mquirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.42, 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 lh h 0-w.
Robert A. Clark, Chief i
Operating Reactors Branch #3 Division of Licensing Attachntnt:
Changes to the Technical Specifications Date of Issuance:
April 4,1933 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replate the fo.11owing page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amenilment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is provided to maintain document l
comple teness.
Remove Page Insert Page,
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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification.
3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constittte compliance with the specification.
In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.
3.0.3 In the event a Limiting Condition for Operation and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the specification within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, action shall be initiated to place the unit in a rode in which the specification does not apply by placing it, as applicable, in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least HOT SHUTOOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless corrective measures are completed that permit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery or until the reactor i
is placed in a MODE in which the specification is not. applicable.
Exceptions to these requirements shall be stated in the individual specification.,
3.0.4 Entry into an OPERATIONAL MODE or other specified applicability condi-tion shcil not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION statements unless otherwise excepted.
This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION statements.
3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or 1
solely because its normal power source is inoperable, it may be considered l
OPERABLE for the purpose of satisfying the requirements-of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2)' all of its redundant system (s),
subsystem (s), train (s), component (s), and device (s) are OPERABLE, or likewise satisfy the requirements of this specification.
Unle'ss both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing.it, as applicable, in at least HOT STAND 8Y within 6~
hours, in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />., and in at least COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This specification is not applicable in MODES S or 6.
ARKANSAS - UNIT 2 3/4 0-1 Amendment No.13
l SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
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4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25% of the sur'veillance interval, and b.
A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY require-ments for a Limiting Condition for Operation.
Exceptions to these require-ments are stated in the individual specifications.
Surveillance Require-ments do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified appli' ability condi-tion shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and t' esting of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
a.
During the time period:
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 Ccde 1974 Edition, and Addenda through Summer 1975, except where specific written relief r
has been granted by the Commission.
2.
Following start of facility commercial operation, inservice inspection of ASME Code Class 1, 2 and 3 components and in-service 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 la CFR 50 Section 50.55a(g),
except where specific written relief has bean granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).
ARKANSAS - UNI'T 2 3/4 0-2 Amendment No. 42 l
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