ML20003E267
| ML20003E267 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/23/1981 |
| From: | Clark R, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20003E268 | List: |
| References | |
| DPR-51-A-054, NPF-06-A-022 NUDOCS 8104020722 | |
| Download: ML20003E267 (10) | |
Text
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[pa rtogb UNITE D STATES o
f' 4 NUCLEAR REGULATORY COMMISSION f
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ARKANSAS POWER \\ LIGHT _ COMPANY DOCKET NO. 50_313_
ARKANSAS NUCLEAR ONE_
'JNIT NO.1 AMENDMENT TO FACILITY OPERA,T_ING LICENSE Amenchent No. 54 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated June 26, 1980, 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, 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 amendmer.t is in accordance with 10 CPR Part 51 of % Conmission's regulations and all applicable requirements have been satisfied.
f/8
2 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-51 is hereby amended to read as follows:
(2) Techni_c al_ _Sp_eci fi c_a tions The Technical Specifications contained in Appendices e
A and B, as revised through Amendment No. 54, 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 NtlCLEAR REGULATORY COMMISSION r
L s
oh 'F. Stolz, Chief pe ating Reactors Branch #4
' ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 23. 1981 m
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ATTACHMENT TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the fc11owing page.of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment
- number and contains vertical lines indicating the area of change.
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4.19 FIRE DETECTION INSTRLNENTATION Applicability Applies to surveillance of fire detection instrumentation required operable by Specification 3.5.5.
Obfective To assure that the fire detection instrumentation required operable by Specification 3.5.5 is available and cperable when needed.
Specification 4.19.1 Each required fire detection instrument
- rhall be demon-strated operable at least once per six mcnths by perfor-mance of a channel functicnal test.
4.19.2 The NFPA Code 72D Class A supervised circuits supervision
- associated with the detector alarms of each recuired fire detection instrument shall be der.cnstrated operable at least once per six months.
4.19.3 The non-supervised circuits between the local panels in Specification 4.19.2 and the control room shall be demon-strated operable at least once per 31 days.
Bases s
These required demcnstrations will assure operability of the fire detection instrumentation.
t
- The minimum number of fire detectors and circuits inside the containment I
shall be functionally tested during each cold shutdown exceeding All fire 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed during the previous six months.
detectors located inside the containment and their associated l'
circuits shall be tested during each refueling outage.
a Amendment No. 30,54 110p
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- NUCLEAR REGULATORY COMMISSION
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$4.....,C ARKANSAS POWER & LIGHT _ COMPANY DOCKET NS 3 m ARKANSAS NUCLEAR ONE - UNIT NO. 2 AMENDMENT TO FA_C_ILITY OP_ERATING LICENSE Arendent No 22 License No.NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated June 26, 1980, 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 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 endar.gering the health and safety of the public, and (11) 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 CPR 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, NPF-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 22, 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 NilCLEAR REGULATORY COMMISSION
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ta r Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 23, 1981 4
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ATTACHMENT TO LICENSE AMENDMENT N0.22 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368
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Replace the following pages of the Appendix "A" Technical Specifications
- with the enclosed pages..The revised pages are identified hy amendment number and contain ~ vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 3-43 8 3/4 3-3 m
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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.#
ACTION:
With one or more of the fire detection instrument (s) shown in Table 3.3-11 inoperable:
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) a.
with the inoperable instrument (s) at least once per hour.
Fire zones located inside primary containment are exempt from this requirement during Modes 1 and 2.
b.
Restore the inoperable instrument (s) to OPERABLE ' status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status, The provisions of Specifications 3.0.3 and 3.0.4 are not c.
applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8.1 _Each of the above required fire detection ins'trument.s shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.*
l 4.3.3.8.2 The NFPA Code 72D Class A supervised circuits supervision associated I
with the detector alarms of each of the above required fire detection instru-l ments.shall be demonstrated OPERABLE at least once per 6 months.*
l 4.3.3.8.3 The non-supervised circuits between the local panels in Specification 4.3.3.8.2 and the control room shall be demonstrated OPERABLE at least once per i
i 31 days.
- The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.
- The minimum number of fire detect 4% 61d circuits required inside the contain-s ment shall be functionally testro N-ing each cold shutdown exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed during the nb tie i six months. All fire detectors located inside the containment anc' t eb ' sociated circuits shall be tested during each refueling outage.
ARKANSAS - UNIT 2 3/4 3-43 Amendment No. 22
TABLE 3.3-11 FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE HEAT SMOKE 1.
Containment North Penetration Area-Upper 2/ Area 2/ Area North Penetration Area-Lower 2/ Area 2/ Area South Penetration Area-Upper 2/ Area 2/ Area South Penetration Area-Lower 2/ Area 2/ Area 2.
Cable Spreading Protective Wire 4
3.
Switchgear Room-Room 2100-Elev. 372 2
Room 2101-Elev. 372 2
4..
Remote' Shutdown Panels 1
5.
Emergency Diesel Generator Rooms Room 2093-Elev. 369 1
2 Room 2094-Elev. 369 1
2
- 6.-
. Diesel Fuel Storage Vaults 1/Vaalt 7.
Penetration Rooms North Penetration Area-Upper 2/ Roan 1/ Room North Penetration Area-Lower 2/ Roan 1/ Room South Penetration Area-Upper 2/ Room 1/ Room South Penetration Area-Lower 2/ Roan 1/ Roan f
ARKANSAS - UNIT 2 3/4 3-44
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INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975.
3/4.3.3.7 CHLORINE DETECTION SYSTEtiS i
The OPERABILITY of the chlorine detection system ensures that sufficient I
l capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release.
This capability is required to
' orotect control room personnel and is consistent with the recommendations of Regelatory Guide 1.95, " Protection of Nuclear Power Plant Control Room I 3perators Against an Accidental Chlorine Release," February 1975.
l!3/4.3.3.8 FIRE DETECTION INSTRUMENTATION
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OPERABILITY of the fire detection instrumentation ensures that adequate
.; darning capability is. available for the prompt detection of fires. This
!; capability is required in order to detect and locate fires in their early lfstages.
Prompt detection of' fires will reduce the potential for damage to
! safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is
!.f inoperable, except for detectors located in the containment during Modes 1
'I and 2, the establishment of frequent fire patrols in the affected areas is ll required to provide detection capability until the inoperable instrumentation
!! is restored to OPERABILITY.
3 N 3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE
- ar;d will protect the turbine from excessive overspeed.
Protection from jiturbine excessive'overspeed is required since excessive overspeed of the
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- urbine could generate potentially damaging missiles which could impact
- !'and damage safety related components, equipment or structures.
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,RPANSAS - UNIT.2 B 3/4 3-3 Amendment' No. 22 l!
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