ML19325D905
| ML19325D905 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/17/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19325D906 | List: |
| References | |
| NPF-06-A-101 NUDOCS 8910270145 | |
| Download: ML19325D905 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION c.
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e ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-368 j
ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. NPF-6
'I.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated June 13, 1989, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),
and the Comission's rules and regulations set forth in 10 CFR j'
Chapter I; b
B.
The facility will operate in conformity with the application, as t
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amended, 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 healtb.
and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the j
common defense and security or to the health and safety of the public; b
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E.
The issuance of tnis amendment is in accordance with 10 CFR Part 51 l
of the Comission's regulations and all applicable requirements have l
been satisfied.
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8910270145 891017 PDR ADOCK 0500036G l:
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2-t 2.
Accordingly, the license is amended by changes to the Technical Specifications.as indicated in the attachment to this license amendment,andParagraph2.C.(2)ofFacilityOperatingLicenseNo.
NPF-6 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.101, are hereby incorporated i
in the license. The' licensee shall operate the fact'ity in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGtlLATORY COMMISSION Vb m
- o.,
l Frederick J. Hebdon, Director l
Project Directorate IV Division of Reactor Projects - III, IV, V and Special Projects l
Office of Nuclear Reactor. Regulation Attacht.ient:
l Changes to the Technical l
Specifications l
l Date of Issuance: October 17, 1989 l
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ATTACHMENT TO i.! CENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the' Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGE; INSERT PAGES 3/4 3-1 3/4 3-1 3/4 3-la 3/4 3.la l
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3/4.3 INSTRUMENTATION
'3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrementation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown iii Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.
Tne total bypass function shall be demonstrated OPERABLE at least once per 18 l
L months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit'at least once per 18 months.
Each test shall include at least one channel per function such that all channels'are tested at least once every N times 18 months where N is the total ntnnber of redundant channels in a specific reactor trip l
function as shown in the " Total No. of Channels" column of Table 3.3-1.
l 4.3.1.1.4 Deleted.
l ARKANSAS - UNIT 2 3/4 3-1 Amendment No.101 i
i INSTRUMENTATION 1 SURVEftLANcf REOUIREMENTE (Continued) 4.3.1.1.5 -The Core. Protection Calculator System shall be determined 0*ERABLE~at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying'that less than three auto restarts have occurred on each calculator during the past 12 hourr..
L 4.3.1.1.6 The Core Protection Calculator System sha111be subjected 'to a L
CHANNEL FUNCTIONAL TEST to' verify 0PERASILITY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of receipt of a valid High CPC Room Temperature alarm.
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ARKANSAS - UNIT 2 3/4 3-la Amendment No. 24, 101 I
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