ML20134E194

From kanterella
Jump to navigation Jump to search
Forwards Page for Replacement in 961202 Submittal of TS Change Request to Permit Use of 10CFR50,App J,Option B, Performance-Bases Containment Leakage Testing for Type A,B & C Leak Rate
ML20134E194
Person / Time
Site: Waterford Entergy icon.png
Issue date: 02/04/1997
From: Gaudet T
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134E197 List:
References
W3F1-97-0023, W3F1-97-23, NUDOCS 9702060076
Download: ML20134E194 (2)


Text

.

. -~

Entergy l"J'gg"*"2'"*-

. O9erations

~^ =

m sw3wm W3F1-97-0023 A4.05 PR February 4,1997 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 Revised Technical Specification Change Request NPF-38-188 Gentlernen:

By letter W3F1-96-0214 dated December 2,1996, Waterford 3 proposed a change to the Technical Specification (TS) to permit the use of 10CFR50 Appendix J, Option B, Performance-Based Containment Leakage Testing for Type A, B and C leak rate testing. The combined bypass leakage rate was removed from Specification 3.6.1.2 and 4.6.1.2d with the intent of placing this requirement in the Containment Leakage Rate Testing Program. The containment purge supply and exhaust valves with resilient seals leak rate was also removed from Specification 4.6.1.7.2. Since these requirements were to be required by the program, they were omitted from the Technical Specifications. While reviewing the Containment Leakage Rate Testing Program, Waterford 3 reconsidered this and concluded that these requirements should be placed in the Administrative Section 6.15," Containment Leakage Rate j

Testing Program." Attached is the proposed change to the page of our original submittal, which now contains item "c" for combined bypass leakage rate and item "d" for the containment purge valves with resilient seals.

The enclosed change supplements the previous submittal listed above. Only the

((

page affected by this latest revision is included. Please replace the affected page

//

with the attached. This additionalinformation has no affect on the previously provided no significant hazards determination.

g r

9702060076 970204

?

PDR ADOCK 05000382 P

PDR j

i Revised Technical Specification Change Request NPF-38-188 W3F1-97-0023 Page 2 February 4,1997 i

Should you have any questions or comments concerning this request, please contact me at (504) 739-6666 or Paul Caropino at (504) 739-6692.

Very truly yours, f

J J

M T.J. Gaudet Acting - Director Nuclear Safety & Regulatory Affairs l

TJG/ CWT /ssf

Attachment:

Revised page of NPF-38-188 cc:

E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident inspectors Office Administrator Radiation Protection Division (State of Louisiana)

American Nuclear Insurers i