ML20033H219
| ML20033H219 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/05/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20033H220 | List: |
| References | |
| DPR-51-A-129, GL-89-014, NPF-06-A-103 NUDOCS 9004180398 | |
| Download: ML20033H219 (11) | |
Text
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i ARKAtlSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS flVCLEAR ONE._ UNIT'1 AMENDMENT T0' FACILITY OPERATING LICENSE Amendment No.'129 License No. DPR-51 J
1.
The' Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power,and Light Company y
(thelicensee)datedOctober 19, 1989,-complies with the standards and requirements of-the Atomic Energy Act of 1954, es amended (the -
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Act), and the Comission's rules and regulations set forth,in-10 CFR Chapter 1; B.
The facility will operate in conformity with:the application, as-amended, the provisionsof the Act, and the rules andL regulations of the Comission;-
C.
There is reasonable assurance:
(1) that the activities: authorized ty this atendment can be conducted without endangering the health and safety of the public, and (ii). that such activities will be conducted in ecmpliance with the Corrinission's' regulations; D.
The issuance of this license amendment willinct.be inimical to the corron defense and security or to the henith and safety of. the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Cottission's regulations and all: applicable requirements have been satisfied.
I 900418o398 900405 ADOCK0500g3 PDR P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license s
an.endment, and Paragraph 2.C.(2) of facility Operating License No.
DPR-51 is hereby amended to read as follows:
(2) Technical Specjfications The Technical Specifications contained in Appendix A, as revised through Amendment No.129, are hereby incorporated in the license.
The licensee shall. operate the facility in accordance with the
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Technical Specifications.
3.
The license amendnent is effective as cf its date of issuance.
FOR THE' NUCLEAR REGULATORY COMMISSION
- w i s19
/)dds Fr)ederick J. Heb cn, Director r
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Project Directorate IV Division of Reactor Projects - III, i
IV, V and Special Projects l
Office cf Nuclear Reactor Regulation I
Attachnent:
1 Cher.ges to the Technical Specifications Date of Issuerte: April 5,1990 l
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ATTACHMENT TO LICENSE AMENDMEllT NO. 129~
FACILITY 0PERATING LICENSE NO. DPR-51 DOCKET NO. 50-313' RevisethefollowingpageoftheAppendix"A"IechnicalSpecifications' with the attached page. -The revised page is identified by Amendment number and contains a vertical'line indicating.the area of change.
REMOVE PAGE INSERT PAGE 67 67 l
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SURVEILLANCE REQUIREMENTS Specified surveillance intervals may be extended up'to 25 percent to.
I accommodate normal test and surveillance schedules.
Surveillance requirements are not applicable when the plant operating conditions are below those requiring operability of the designated component.
However, the required surveillance must be performed prior to reaching the operating conditions requiring operability.
For example, instrumentation requiring i
twice per week surveillance when the reactor is critica1Lneed not have the required surveillance when the reactor is shutdown.
Inservice inspection of ASME Code Class 1, 2, 3 components 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 l
l 50.55a(g), except where specific written relief has been granted by the NRC l
pursuant to110 CFR 50, Section 50.55a(g)(6)(i).
Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet-the OPERABILITY requirements for a limiting Condition for Operation.
Exceptions to these requirements are stated in the individual specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
L 4.1 OPERATIONAL SAFETY ITEMS l
Applicability Applies to items directly related to safety limits and limiting conditions for operation, l
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Objective l'
To specify the minimum frequency and type of surveillance to be applied,to i
unit equipment and conditions.
Specification s
a.
The minimum frequency and type of surveillance required for 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 Table 4.1-2 and 4.1-3.
3 c.
Discrepancies noted during-surveillance testing will be corrected 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 syste.T.,
AmendTent No. 25. 75. 77, 129 67
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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I ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50- 68 i
ARKANSAS NUCLEAR ONE, UNIT 2 j
i AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.103' i
License No. NPF-6 j
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1.
The Euclear Regulatory Conr.ission (the Connission) has found that:-
A.
The application for' amendment by Arkansas Power and Light Company
- i (thelicensee)datedOctober 19, 1989, complies with the standards j
and requirements of the Atomic ~ Energy Act of 1954, as amended (the-Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; 1
B.
The-facility will operate in conformity with the application,-as.
amended, theLprovisions of the Act, and the rules,and regulations of the Conn.ission; i
C.
There is reasonable assurance:
(i)thatthe.activitiesauthorized by this amendment can be conducted without endangering the health
^=i 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 license amendnent will r.ct be inimical to the cons.cn defense and security or to the health and safety of the public; and.
E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the.Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by-changes to the Technical Specifications as indicated in the attachment to this license ar.endment, and Paragraph 2.C.(2) of Facility Operating License No.
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NPF-6 is hereby amended to read as-follows:
l-(2) Technic,a,1_ Spec,ilications ec l'
i The Technical Specifications-contained in Appendix A, as revised through Amendment No.103, are hereby incorporated in the license.
The licensee.shall operate the facility in accordance with the l
Technical Specifications.
3.
The license amendment is effective as of its date of issuence.
FOR THE NUCLEAR REGULATORY COMMISSION l
rH0 k:be_.
l Frederick J. Heb on, Director Project Directorate IV Division of Reactor Projects - III,
.IV, V and Special Projects Office of Nuclear Reactor Regulation l
Attachmer.t:
- Cherces to the Technical Specifications Date of Issuarce:
April 5,1990 i
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ATTACHMENT TO LICENSE AMENDMENT-NO. jfg TACI_LITY_0PERATING LICENSE-NO._NPF __
DOCKET NO. 50-368 P.evise the following pages of-the Appendix "A" Technical Specifications with-the attached pages.' The revised pages are identified by Amendraent nurcher and contain vertical lines indicating the area of change..The l.
corresponding overleaf pages are also provided to maintain document l
completeness.
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REMOVE PAGES INSERT PAGES 3/4 0-2 3/4 0-2 B 3/4 0 B~3/4 0-2 s
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a 3/4 LIMIT 1t'G CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4. 0 APPLICABILITY LIMITING CONDITION FOR OPERATION
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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 j
and/or associated ACTION within the specified time interval shall constitute i
compliance with the specification.
In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, j
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 l' hour, action shall be: initiated to place the unit in a mode 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 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 /> 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 is placed in a MODE in which the specification is notiapplicable.
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 shall 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 solely because its normal power source is inoperable, it may be considered 4
OPERABLE for the purpose of satisfying the requirements-of its applicable i
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 3
satisfy the requirements of this specification.
Unless 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 pl:ce 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 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 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 5 or 6.
i ARKANSAS --UNIT 2 3/4 0-1 Amendment No.19
'1 SURVEILLANCE REOUIREMENTS (Continued) 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.
i 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance; interval.
- 4. 0.'3 l Failure to perform a Surveillance Requirement within the specified time l
interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Exceptions to these requirements-are stated in the individual specifications.
Surveillance Requirements do' not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or othei specified applicability.
condition shall not be made unless the Surveillance Requirement (s)~
i assorWed with the Limiting Condition for Operation h:ve been performed within the stated 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 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
'r Vessel Code 1974 Edition, and. Addenda through Summer 1975, except where specific written relief 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 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 D
the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
ARKANSAS - UNIT 2 3/4 0-2 Amendment No. f2, 103
APPLICABILITY BASES (Continued) o
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l systems, subsystems, trains, components and devices in the other division must-l be OPERABLE or likewise satisfy Specification 3.0.5 (i.e.. be capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices.in 'oth divisions must also o
l be_0PERABLE.
If these conditions are not satisfied, action is required _in L
- accordance with this-specification.
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In MODES 5 or 6. Specification 3.0.5 is not applicable, and thus the-individual ACTION statements for each applicable Limiting Condition for Opera-tion in these MODES must be adhered to'.
I ARKANSAS - UNIT 2 4 3/4 0-lb Amendment No.19
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APPLICABILITY BASES 1 ~
4.0.1
.This specification provides that. surveillance activities necessary to insure the Limiting Conditions for. Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the I
l-Limiting Conditions-for Operation are applicable.
Provisions for; additional surveillance activities to be: performed without-regard to the-j applicable OPERATIONAL MODES or other conditions are provided in the 1
individual Surveillance Requirements.
Surveillance Requirements for Special Test Exceptions need only be performed when the Special= Test Exception lis-being utilized as an. exception to an individual specification.
4.0.2.- Specification 4.D.2 establishes.the limit for which the specified time interval for Surveillance. Requirements may be extended.
It permits an-allowable extension of the normal surveillance interval to facilitate
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surveillance scheduling and consid6 ration of plant operating conditions-that -
may not'be suitable-for conducting the surveillance; e.g., transient conditions N
l or,other ongoing surveillance or maintenance activities.
It also' provides' flexibility.to accommodate the length of..a fuel cycle for surveillances-that.
are performed at each refueling' outage and are specified with an 18-month-1 surveillance interval.
It is not intended that this provision be used
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repeatedly as a convenience to extend surveillance intervais beyond that specified for surveillances that are not p'erformed during refueling outages.
The. limitation of Specification 4.0.2 is based on engineering. judgement and the recognition that the most probable result of any particular surveillance i
being performed is the verification of conformance with the Surveillance.
Requirements.
This provision is sufficient to-ensure that the reliability 1
ensured through surveillance activities is not significantly degraded.beyond 1
that obtained from the specified surveillance intervals.
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4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the l
Limiting Conditions for Operation.
Under this criteria, equipment, systems j
or components are assumed'to be OPERABLE if the associated surveillance l
activities have been satisfactorily performed within the.specif_ied time interval.
Nothing in this provision is to be' construed as defining equipment systems or components OPERABLE, when such items are found or i
known to be inoperable although-still meeting the' Surveillance j
Requirements.
4.0.4 This specification ensures that the: surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL-MODE or other applicable condition.
The intent of this. provision is to ensure 1
that surveillance activities have been satisfactorily demonstrated on a l
current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.
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ARKANSAS - UN]T 2 B 3/4 0-2 Amendment No. 103
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