ML20100E461
| ML20100E461 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/18/1985 |
| From: | John Miller, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20100E464 | List: |
| References | |
| DPR-51-A-096, NPF-06-A-064 NUDOCS 8504030490 | |
| Download: ML20100E461 (9) | |
Text
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4 pun g fg UNITED STATES E
NUCLEAR REGULATORY COMMISSION e
- p WASHINGTON, D. C. 20555
%....+/
ARKANSAS POWER & LIGHT COMPANY DOCKET N0. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.96 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 October 16, 1984, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 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 anendment is in accordance with 10 CFR 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. DPR-51 is hereby amended to read as follows:
$$$$o$13 PDR 2
i l
l l, Technical Specifications The Technical Specifications contained in Appendices l
A and B, as revised through Amendment No. 64, 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 its date of issuance.
FOR THE NUCLEAR RE ULATORY COMMISSION i
Jo n F. Stolz, Chie 0 rating Reactors Branch #4 l
ivision of sicensing l
Attachment:
Changes to the Technical Specifications Date of Issuance: March 18, 1985 i
o.
ATTACHMENT TO LICENSE AMENDMENT N0.96 FRCILITY OPERATING LICENSE NO. OPR-51 DOCKET N0. 50-313 Replace the following 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.
Remove Insert 66 t 66 t 0
0
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'P 3.23 REACTOR BUILDING PURGE VALVES APPLICABILITY This specification applies to the reactor building purge supply and exhaust isolation valves.
OBJECTIVE To specify that reactor butiding isolation purge valves be closed whenever containment integrity is required by TS 3.6.1.
SPECIFICATION 3.23.1 The reactor building purge supply and exhaust isolation valves shall be closed and handswitch keys removed whenever containment integrity is required by TS 3.6.1.
BASES The reactor building supply and exhaust isolation valves are required to be closed during normal plant operation in order to ensure reactor building integrity. Purging is allowed only when containment integrity is not required by TS 3.6.1.
A 4
Amendment No. 55, 96 66t
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION O
p WASHINGTON, D. C. 20555
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NilCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (thelicensee)datedOctober 16, 1984, 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 conformity with the application, the provisions of the Act, and the rules ar.d regulations of the Commission; 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 Commission's regulations; D.
The issuance 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 Comnissi n's regulations and all applicable requirements have been satisfied.
I l
_.. _ ~
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. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGU T0pYpCOMMISSION
/-
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 18, 1985
ATTACHMENT TO LICENSE AMENDMENT N0.64 FACILTIY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following 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 areas of change. The corresponding overleaf page is also provided to maintain document completeness.
Renove Page Insert Page 3/4 6-9a 3/4 6-9a m
e 8
6 CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.6 The containment purge supply and exhaust isolation valves shall be closed and handswitch keys removed.
l APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one or more containment purge supply and/or exhaust isolation valves not closed with the handswitch keys removed, place the valve (s) in the closed position with handswitch key (r) removed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.6 The containment pu*ge supply and exhaust isolation valves shall be determined closed at least once per 31 days.
ARKANSAS - UNIT 2 3/4 6-9a Amendment No. 64
U CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each' spray system capable of taking) suction from the RWT on a Containment Spray Actuation Signal (CSAS and automatically transferring suction to the containment sump on a Recirculation Actuation Signal (RAS).
Ecch spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT
~
STANDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying that each valve (manual, power operated or automatic) in the flow path is positioned to take suction l
from the RWT on a Containment Pressure--High-High test signal.
r 2.
Verifying that the system piping is full of water from
^
the RWT to at least elevation 505' (equivalent to > 12.5%
I indicated narrow range level) in the risers within the containment.
l i
b.
By verifying that each pump demonstrates degradation of < 6.3%
from its original acceptance test pump performance curve when t::sted pursuant to Specification 4.0.5.
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ARKANSAS-UNIT 2 3/4 6-10 l