ML20078S250
| ML20078S250 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/14/1995 |
| From: | Hutchinson C ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20078S254 | List: |
| References | |
| RTR-NUREG-1434 PCOL-93-11, NUDOCS 9502240057 | |
| Download: ML20078S250 (3) | |
Text
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" ENTERGY PrA Geson MS 39150 Tel 601437 2600 C. R. Hutchinson February 14,1994 U2" aw one sw U.S. Nuclear Regulatory Commission Mail Station P1-37 Washington, D.C. 20555 Attention:
Document Control Desk l
Subject:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Conversion to Technical Specifications based on NUREG 1434
" Improved Technical Specifications Revision 0" Proposed Amendment to the Operating License (PCOL-93/11 Revision 4)
Reference:
1)
GNRO-94/00014, Conversion to Technical Specifications based on NUREG 1434 " improved Technical Specifications Revision 0" Proposed Amendment to the Operating License (PCOL-93/11 Revision 3), dated February 10,1995.
2)
GNRO-93/00122, Drywell Bypass and Drywell Airlock Testing, Proposed Amendment to the Operating License (PCOL-93/13), dated October 22,1993.
3)
GNRO-93/00069, Modification of the Technical Specifications Operability and Surveillance Requirements for the Main Steam isolation Valve Leakage Control System, Proposed Amendment to the Operating License (PCOL-93/05), dated June 25,1993.
GNRO-95/00017 Gentlemen:
Entergy Operations, Inc. by this letter is submitting a revision to the proposed amendment to the Grand Gulf Nuclear Station (GGNS) Operating License submitted via Reference 1, additional information concerning the proposed changed submitted via Reference 2, and an addition to the proposed change submitted via Reference 3. of this letter provides a markup of the affect of the changes to the Reference 2 submittal in the format of the current Technical Specifications. This information was I
previously provided in the format of the improved Technical Specifications by Reference 1.
{ provides additional information concerning GGNS's plans for the setting of the pretreatment radiation monitor when NEDO-31400 is implemented.
9502240057 950214 ii PDR ADOCK 05000416 l
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February 14, 1995 GNRO-95/00017 i
Page 2 of 3 i modifies the Reference 3 request to relocate many of the specific surveillance requirements for the Main Steam isolation Valve Leakage Control System. The change was requested to be issued concurrent with the issuance of the improved Technical Specifications to support the Technical Specification conversion effort. The Reference 3 requested relocation of surveillance requirements is modified to allow the Staff additional time to review the remainder of the requested change (i.e., the relocation of current l
Technical Specification requirements 4.4.1.4.a.1 and 4.6.1.4.a.2). The revised proposed surveillance requirements and associated discussions of change are provided in the format of the Improved Technical Specifications conversion packages to assist the Staff in the inclusion of this change into the conversion package. The revised surveillance does not supersede the Reference 3 requested change and Entergy Operations, Inc. requests that the Staff complete their review of the requested change in a timely manner.
l' As previously discussed with the Staff, Entergy plans to implement the improved Technical Specifications at GGNS approximately 30 days before our seventh refueling outage.
Therefore, we request that this change receive review priority to support its approval by l
February 17,1995.
The requested changes are bounded by the previous basis provided in References 1,2, and 3 for the determination that the proposed amendment involves no significant hazards considerations t.ased on the guidelines presented in 10CFR50.92. In accordance with the i
provisions of 10CFR50.4, the signed original of the requested amendment is enclosed and, in accordance with 10CFR50.30, an Oath or Affirmation relating to the requested changes to the Operating License is enclosed, i
Yours truly, f
s
/ ffW l
C.
. Hu inson Vice President, Operations GGNS
\\BSF
Enclosures:
1.
Affirmation per 10CFR50.30 (1 page) 2.
Revised Drywell Bypass Test Surveillance (1 page) 3.
Additional Information Conceming Pretreatment Offgas Radiation Monitor (1 page) 4.
Revised MSIV-LCS Surveillance Requirements (6 pages) 4
4 February 14, 1995 GNRO-95/OOO17 Page 3 of 3 cc:
Mr. H. W. Keiser (w/o)
)
Mr. R. B. McGehee (w/o)
Mr. N. S. Reynolds (w/o)
Mr. J. E. Tedrow (w/a)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region il 101 Marietta St., N.W., Suite 9900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager (w/2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 Mr. C. S. Schulten (w/2) l Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 11E22 Washington, D.C. 20555 Dr. Eddie F. Thompson (w/a)
State Health Officer State Board of Health P.O. Box 1700 Jackson, Mississippi 39205
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