2CAN109012, Lists Clarifications Re Withdrawal of Inservice Testing Relief Request
| ML20062C474 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/24/1990 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN109012, NUDOCS 9010310256 | |
| Download: ML20062C474 (2) | |
Text
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-: - Ente iaem c-u:a. ia>.
R:uto 3, Box 137G Opera ons.
n=* wet i
. Te 501964-3100
'i October 24, 1990 1
U. S. Nuclear Regulatory Commia'sion i
Document Control Desk Mail Station PI-137 Washington, DC 20555 ii
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Withdrawal of Interim Inservice Testing Relief Request Gentlemen:
Dy letter dated September 21, 1990 (2CAN099009), Entergy Operations requested an one time interim. relief from performing the quarterly-partial stroke test for the safety injection tank outlet check valve 2SI-16A..This relief request was' discussed with Mr. Chester Poslusny, the NRR Project Manager, and Mr. Ken Dempsey of your staff,. on September 27,11990.The following clarifications woro provided to'us during this discussion.
Clarification 1 l
l Based on the September 27,.1990, conversation, the NRC indicated'that requests for relief are not required if we are in compliance with the alternate provisions of the Coco, but deviate from the. Inservice Testing (IST) program.
The deviations and ths reasons for the deviationsishould be-noted in the IST program.
In this sptcific case Section IWV-3522 of the.
ASME Code states that if the check valve cannot be exercised during plant
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operations, it shall be specifically idtntified by the Owner and shall be full-stroke exercised during cold shutdowns.
4 based on this clarification, Entergy Operations withdrawals the previously l
submitted IST relief request for the safety' Injection tank outlet check i
valve 2SI-16A.
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Clarification 2 For non-ASME components in the IST program for which certain Code provisions could not be met, 10CFR50.55a does not require relief requests to be submitted ~
Documentation, however, is required to'be available at the' site that provides assurance of the continued _ operability of the component f
through tests that are performed.
We request confirmation that these clarifications are consistent alth the NRC's position for Generic Letter 89-04.
Should you have any questions regarding this issue, please contact me.
Very truly yours, q
^
. ]W.
James J.
'inicaro
\\
Manager,_Iicensing JJF:RWC:fc cc:
Mr. Robert Martin U. S. Nuclear Regulatory Commission.
Region-IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-l' U. S. Nuclear Regulatory Commission NRR Mail Stop 11-B-19 Ono White Flint North 1
11555 Rockville Pike Rockv1110, Maryland 20852
_NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road q
Russellville, AR 72801 Mr. Chester Posluany NRR Project Manager,_ Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 11-B-19 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 O
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