2CAN069602, Forwards Revised Spec 3/4.4.12,including New 24 H Action Statement for Single Inoperable LTOP Relief Valve in Modes 5 & 6,per Discussion W/Nrc Re 960411 Proposed TS Change on LTOP as Requested by GL 90-06
| ML20117N674 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/18/1996 |
| From: | Yelverton J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20117N681 | List: |
| References | |
| 2CAN069602, 2CAN69602, GL-90-06, GL-90-6, NUDOCS 9606240067 | |
| Download: ML20117N674 (3) | |
Text
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== ENTERGY l8 2 % f "*'"-
Jackson, MS 39286-1995 Tel 601368 5690 Jerry W. Yelverton Executwe Vice Prescent and chief Operating Officer 1
Jee 18,1996 2CAN069602 U S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555 l
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Supplemental Change Regarding ANO-2 Proposed Technical Specification On Low Temperature Overpressure Protection Gentlemen:
On April 11,1996, Entergy submitted a proposed Arkansas Nuclear One, Unit 2 (ANO-2) i Technical Specification change for incorporation of a new Specification for low temperature overpressure protection (LTOP) as requested by Generic Letter 90-06. In that submittal, Entergy proposed a new Specification 3/4.4.12 and Bases utilizing ASME Code Case N-514.
The Specification proposed for ANO-2 included a single 7 day action statement for modes 4, 5 and 6.
In a subsequent discussion the NRC Staff stated that the 7 day action is acceptable for a single inoperable LTOP relief valve in mode 4, however, in modes 5 and 6 the required action time should be reduced to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Therefore, please find attached a revised Specification 3/4.4.12 including a new 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> action statement for a single inoperable LTOP relief valve in modes 5 and 6. The new ANO-2 proposed action statement wording is consistent with the l
wording contained in Attachment B-1 of Enclosure B to NRC Generic Letter 90-06. The i
Bases contained in the original April 11,1996 submittalis uneffected by this proposed change.
The attached proposed change does not modify the no significant hazards considerations previously performed in accordance with 10CFR50.91(a)(1) as provided in our April 11,1996 submittal.
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U.S.NRC June 18,1996 2CAN069602, Page 2 Very truly yours,
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4 Attachment To the best of my knowledge and belief, the statements contained in this submittal are true.
SUBSCRIBED AND SWORN TO before me, a Notary Public in and for AinAs County and the State of Mississippi, this 18tA day of Ju n e.
,1996.
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.My Commission Expires D_N_ f3.Y3.. 55"GCHEm,Ita A+"U W
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U. S. NRC June 18,1996 2CAN069602, Page 3 cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 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 i
Rockville, MD 20852 Mr. Bernard Bevill Acting Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205 l
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