ML20136H269
| ML20136H269 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/14/1997 |
| From: | Gaudet T ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20136H271 | List: |
| References | |
| W3F1-97-0055, W3F1-97-55, NUDOCS 9703190103 | |
| Download: ML20136H269 (3) | |
Text
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xteit^ rocce Tei 504 739-6650 I
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A4.05 PR March 14,1997 U.S. Nuclear Regulatory Commission
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l Attn.: Document Control Desk i
Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Request for Additional Information Relating to Technical Specification Change Request NPF-38-188 Gentlemen:
By letter W3F1-96-0214 dated December 2,1996, Waterford 3 proposed a change to l
the Technical Specifications (TS) to permit the use of 10CFR50 Appendix J, Option B, Performance-Based Containment Leakage Testing for Type A, B and C leak rate i
testing. Letter W3F1-97-0023 revised this request to add the combined bypass leakage rate and containment purge supply and exhaust valves with resilient seals leak rate to the Administrative Section 6.15, " Containment Leakage Rate Testing Program." Per conversation with the Staff on March 11,1997, Waterford 3 provides the following changes to our previous submittals:
On page number 4, paragraph 2 of the December 2,1996 Letter the last I
sentence reads " Reference to Specification 4.6.1.2 has been removed since it is referenced the Containment Leakage Rate Testing Program." This should be changed to read " Reference to Specification 4.61.2 has been removed g'
since it is referenced in the Containment Leakage Rate Testing Program."
In Attachment B, TS page number 3/4 6-15, of the December 2,1996 Letter, the required frequency of 3 months for SR 4.6.1.7.2 is being retained rather than adopting the frequency of 184 days or within 92 days of opening the valves as specified in the NRC Model. A revised page 3/4 6-15 is provided in Attachment A to this letter.
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Request for Additional Information Relating to Technical Specification Change Request NPF-38-188
' W3F1-97-0055 Page 2 March 14,1997 In Attachment B, TS page number B 3/4 6-1, of the December 2,1996 Letter, the change bar should include the last paragraph of Section 3/4.6.1.2. A revised page B 3/4 6-1 is provided in Attachment A to this letter.
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in Attachment B, TS page number 6-24 of the December 2,1996 Letter and the Attachment to the February 3,1997 Letter, the page number is listed the same as the previous page. A revised page 6-25 is provided in Attachment A to this letter.
Attachment B to this Letter provides a description of the differences between the u
NRC Model which was provided to Nuclear Energy institute by Letter dated November 2,1995 and the Waterford 3 proposed changes. The differences between the W-3 proposal and the Model TS are due primarily to W-3's TS being currently written to the CE Standard TS (NUREG 0212) and the Model being written to the Improved TS (NUREG 1432). W-3 proposed changes that were related to Option B and did not include other aspects of the improved TS in the proposal. Other differences as delineated in this document are requirements that are specific due to the design and licensing basis for W-3. In all cases the proposed changes do not.
deviate from the requirements of Option B and are either consistent with, or more conservative than the Model TS.
The enclosed change supplements the previous submittals listed above. Only the TS pages affected by this latest revision are included. Please replace the affected pages with the attached. This additional information has no affect on the previously provided no significant hazards determination.
l Request for Additional Information Relating to Technical Specification Change Request NPF-38-188 W3F1-97-0055 Page 3 l
March 14,1997 l
Should you have any questions or comments concerning this request, please contact me at (504) 739-6666 or Paul Caropino at (504) 739-6692.
l Very truly yours, t
/
T.J. Gaudet l
Acting - Director l
Nuclear Safety & Regulatory Affairs l
TJG/ CWT /ssf l
Attachments:
Revised pages of NPF-38-188 Differences Between the Waterford 3 Submittal and the NRC Model i
cc:
L.J. Callan, NRC Region IV C.P. Patel, NRC-NRR l
R.B. McGehee l
N.S. Reynolds NRC Resident inspectors Office Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers i
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