ML19326C511
| ML19326C511 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/22/1976 |
| From: | Phillips J ARKANSAS POWER & LIGHT CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19326C512 | List: |
| References | |
| 1-116-13, NUDOCS 8004230630 | |
| Download: ML19326C511 (3) | |
Text
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lt/22/76
- !r. Dennis L. 7.icnann Little Roch, Arkansas oATe nectivso J. D. Phillios 11/24/76 gecTven ONoTonizso Paon surufPomu Nuusen or copies sectivso Nonicid*L
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Andt. to ol/chan',e to tech specs....
furnisSing chang,es that i cre requested in referenced letter.
gJHIS DOCUMENT CONTAINS g< P00R QUAUTY PAGES (10-P)
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Araansas Unit No. 1 SAFETY FOR ACTION /lNFORMATION psmTu n ll/24/76 dJL 8 ASSIGNED AD:
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Director of Nuclear Reacto ATTN:
Mr. Dennis L. Zie nn, Chief Operating Reactors Branch #2 7
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u U. S. Nuclear Regulatory Commission Washington, D. C.
20555 4
Eubj ect: Arkansas Nuclear One-Unit 1 Proposed Technical Specifications (File:
1511.1)
Gentlemen:
Your letter of September 9,1976, to Mr. J. D. Phillips requested we levise or resubmit our request for a license amendment to be consistent with the enclosed model technical specifications of your letter which are based on Revision 1. of Regulatory Guide 1.83, dated July 1975.
Attached find those changes as requested, save those exceptions which are delineated below.
Specification Reason for Exception 3.4.5 Limiting conditions for operation of the ste m generators presently exist in Specification 3.1.
Therefore, we see no need for a change until the conversion to Standard Technical Specifications 4.4.5.3 Subsequent inservice inspections should be allowed at intervals of. not less than 10 months rather than 12 months in the event a refueling shutdown is scheduled between 10 and 12 months after the previous inservice inspection.
4.4.5.5 Reporting Requirements presently exist in Specification 6.12.3 for abnormal degrada-tion in the reactor coolant pressure boundary and for conditions that require remedial II..).U 13 T A x p AveNo. iNve ston owNe o 3 MeMu sa Mioots sour >4 uTitities system
Mr. Dennis L. I ann N mbsr 22, 1976 1-116-13 9
Specification Reason for Exception action or corrective measures to prevent the existence or development of an unsafe condition. Therefore, we see no need to duplicate these requirements. Annual Operating Report requirements have been revised to include the complete results of the steam generator tube inservice inspec-tion.
(Sr Technical Specification 6.12.3) 4.4.5.6 This specification was not incorporated as it did not pertain to steam generator tubing surveillance. Presently, redundant IcVel instrumentation provides assurance that the. steam generator level is maintained within operable limits.
Table 4.4-2 Minor changes have been incorporated to facilitate the course of action required for each set of circumstances.
3.4.6.2 Limiting conditions for operation pertaining to Reactor Coolant System leakage presently exist in Specification 3.1.6.
Therefore, we see no need for a change until the con-version to Standard Technical Specifications.
4.4.6.2 Performance of surveillance requirements to demonstrate Reactor Coolant System leak-ages would presently pose implementation problems. Therefore, this change has not been preposed but will be included in the submittal for convers' n to Standard Tech..ical Specifications.
If you should have any questions and/or comments concerning the above, please contact us.
Very truly yours, s
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J. D. Phillips Senior Vice President JDP:ay 1
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