ML20133A680
| ML20133A680 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/23/1996 |
| From: | Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20133A683 | List: |
| References | |
| 2CAN129610, NUDOCS 9701020046 | |
| Download: ML20133A680 (2) | |
Text
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i Entrgy oper tions,Inc.
=~Entergy 1448 S.R 333
==
l C. Randy Hutchinson l
Vce presms OperaWs ANO December 23,1996 2CAN129610 l
U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Proposed Technicci Specification Bases Changes Related To Snubbers Gentlemen:
Attached are changes revising the Bases associated with Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification (TS) 3/4.7.8. The changes will enable on-line testing of selected snubbers by clarifying the intent of the TS.
l A review of the Unit 2 Technical Specification bases was performed to determine if on-line testing of snubbbers was acceptable. Since the sample of snubbers to be tested is taken randomly, the sample may include systems that are required to be in service during refueling operations (e.g., shutdown cooling system). Another consideration of the review was that dose rates are significantly elevated adjacent to piping where the reactor coolant system water is circulating, such as Emergency Core Cooling System (ECCS) subsystems, during the early l
days of a refueling shutdown. Presently, this time frame is the most important time to complete initial snubber sample plan testing such that any additional testing due to sample expansion may be completed during the remainder of the outage. It was the conclusion of the review that on-line testing of accessible ECCS snubbers is acceptable, since it provides a more conservative approach when considering outage duration, plant,afety, and radiation exposure i
risk.
As these are changes to the Bases of the Technical Specifications, a "No Significant Hazards Determination" is not requircd. A review of the changes in accordance with 10 CFR 50.59 has concluded that no unreviewed safety question exists.
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9701020046 961223 PDR ADOCK 05000368 PDR p
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U. S. NRC December 23,1996 2CAN129610 Page 2 i
i We request that these changes be issued with the next scheduled amendment. Should you have any questions regarding these changes, please contact me.
l Very truly yours, f f.r
.Mims Direc r, Licensing D C 1/rts i
Attachments L
cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV l
. 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i
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