ML20136H150
| ML20136H150 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/17/1997 |
| From: | Gaudet T ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-97-0046, W3F1-97-46, NUDOCS 9703190066 | |
| Download: ML20136H150 (7) | |
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T6 504-739-6650 W3F1-97-0046 A4.05 PR March 17,1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Request For AdditionalInformation License Amendment Request NPF-38-181 Gentlemen:
By letter dated August 21,1996, Waterford 3 submitted a change under the provisions of 50.90 to resolve a discrepancy regarding the design and testing of Containment Vacuum Relief (CVR) instrument sensing lines penetrating the primary containment. The proposed change described a plant modification that would cut and cap the non-essential CVR instrument sensing line in penetration 65 and add an additional automatic isolation valve and two test ccnnections to the non-essential CVR instrument sensing line in penetration 53. The proposed change also provided the regulatory bases for the design of the essential safety related CVR sensing lines and requested NRC staff approval of this design. In addition, the proposed change requested that a License Condition (Attachment 1) to the Operating License be deleted because it would no longer be applicable. The purpose of this letter is to respond to a staff request for additionalinformation concerning 1) the location of the f
code class break on the non-essential CVR instrument sensing line, and 2) the type
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of testing that will be performed on the associated components. In addition, this letter proposes to modify the previous request associated with Attachment 1 to the Operating License.
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Code Class Break 190044 i
The location of the code class break for the non-essential CVR instrument sensing l
line (following completion of the proposed modification)is identified on Attachment A of this letter.
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' Request For AdditionalInformation NPF-38-181 W3F1-97-0046 Page 2 March 17,1997 Testing The safety related essential CVR sensing line will be pressurized and leak tested at refueling intervals. This test is described in Plant Operating Procedure OP-903-110.
The line will be pressurized to 48 psig and any leakage will be accounted for in the total containment bypass leakage limit imposed by the Technical Specifications. The excess flow check valves (CVR 302A and CVR 302B) will be functionally tested to ensure the valves close on excess flow and reopen when pressure equalizes across the valves.
The containment isolation valves in the non-essential CVR sensing line (CVR400 &
CVR401 in penetration 53) will be stroke-tested in the closed direction on a quarterly bases pursuant to the IST Plan. CVR 400 and CVR 401 will also be pressure t'sted pursuant to 10 CFR 50 Appendix J.
The instrument connection at penetration 65 will be pressure tested upon completion of the proposed modification (prior to startup following Refuel 08). Subsequent testing will occur as part of the containment leak test pm jram pursuant to 10 CFR 50 Appendix J. to Ooerating License to the Waterford 3 Operating License was initially required to assure that direct position indication (pursuant to RG 1.97) would be provided for the isolation valves in the CVR non-essential instrument sensing lines when the valves were changed from manual valves to automatic valves. Accordingly, Waterford 3 requests that the previous proposed change that modified Operating License Condition 2.C.1 and Attachment 1 be withdrawn and that Attachment 1 to the l
Operating License be modified as indicated on Attachment B of this letter. By adopting this request, the Operating License will be conditioned in much the same manner as the originallicense.
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I Request For Additional Information NPF-38-181 W3F1-97-0046 Page 3 March 17,1997 The original amendment request assumed that the proposed modification to the non-essential CVR instrument sensing lines would be performed at power. Therefore, a step by step sequence for performing this activity was provided. Waterford 3 now expects to perform the modification during Refuel 08. Thus, the step by step l
sequence may be different due to the change in criteria, f
The additional information and proposed change described in this request has no impact on the no significant hazards evaluation that was provided in letter dated August 21,1996.
if you should have any questions concerning the above, please contact l
Paul Caropino at (504) 739-6692.
Very truly yours, 8 #7 l
T.J. Gaudet Acting - Director Nuclear Safety & Regulatory Affairs i
TJG/PLC/ssf Attachments l
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L.J. Callan, NRC Region IV C.P. Patel, NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident inspectors Office l
Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers l
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1 W3F1-97-0046 ATTACHMENT A 1
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Proposed Attachment 1 i
to the Ooeratina License ATTACHMENT 1 WATERFORD STEAM ELECTRIC STATION OPERATING LICENSE NPF-38 This attachment identifies items which must be completed to the Commission's satisfaction prior to startup following the refueling outage number 8.
Non-essential Containment Vacuum Relief Sensing Lines:
Penetration 65 will be modified to reflect a Containment Leak Rate Test connection as indicated in licensee submittal dated August 21,1996 l
(Attachment C page 4 of 4).
Penetration 53 will be modified such that two automatic containment isolation valves l
will be located outside containment with continuous direct position indication in the control room as indicated in licensee submittal dated August 21,1996 (Attachment C page 4 of 4).
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