ML20199G486

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Submits Info in Order to Permit Staff to Continue Review of Util Response to GL 96-06,dtd 970128,in Response to Rai. Rev 0 to GGNS-97-0002, GL 96-06 Evaluation of Drywell & Containment Penetrations, encl.W/26 Oversize Drawings
ML20199G486
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 11/20/1997
From: Hughey W
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20199G490 List:
References
GL-96-06, GL-96-6, GNRO-97-00114, GNRO-97-114, TAC-M96815, NUDOCS 9711250191
Download: ML20199G486 (3)


Text

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"I Ent:rgy oper:tions,Inc.

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[ PO Box 756 Pori Gtm>n. MG 39150 l Tel 001437 0470 W. K. Hughey Detar November 20, 1997 Mj " '"*

  • U.S. Nuclear Regulatory Commission Mall Station P1-37 Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF 29 '

Request for AdditionalInformation Related to Generic Letter 96-06 for Grand Gulf Nuclear Station, Unit 1 (TAC No. M96815) dated September 15,1997 GNRO-97/00114 Gentlemen:

The subject letter requested the following informatioa in order to permit the staff to continue its r: view of the Grand Gulf response to Generic Letter 96-06 dated January 28,1997.

1. Summaries of the evaluations of the eighteen piping lines penetrating the containment and drywell.
2. The summaries should describe the method of analysis, including the assumptions used, and the results.
3. Fabrication drawings of piping sections evaluated.
4. A discussion on how the criteria used for evaluations meet the licensing basis criteria for 4gj$

Grand Gulf Nuclear Station, Unit 1.

5. The schedule for completion of any modification that you are required.

/'

The following information is provided in response to your request: )l

1. Grand Gulf Nuclear Station Engineering Report GGNS-97-0002, Rev. O provides information relative to items 1,2 and 4. This report contains an engineering evaluation of the Drywell Cooling /Ch!!Ied Water System and penetration overpressurization, screening criteria to identify drywell and containment penetrations potentially susceptible to overpressurization due tc trapped fluid, results of all drywell and containment penetration screenings including explanations, and the maximum expected delta-t results for each of the susceptible penetrations. Attachment 1 to this engineering report provides a discussion on how criteria found in Generic Letter 91-18 and Appendix F of the ASME Code was used ir determining that the piping meets the operability requirements of the licensing basis for Grand Gulf Nuclear Station, Unit 1. ' ^"

9711250191 971120" D

D~~w e 6" ' * ,

. GNRD'97/00114

  • Page 2 of 4
2. The following fabrication drawings of the piping associated with the susceptible penetrations that were evaluated are provided to address item 3:
  • C-1003, Unit 1 Containment Cylinder Wall Penet Schedule & Radiation Shielding Details C-1003, Drawing Revision Notice, Rev. No.11, Drn Number 3226 C-1054, Unit 1 Containment Drywell Wall Penetrations, Sleeve Schedule & Details
  • C-1063, Unit 1 Containment Drywell Wall Penetrations, Schedule & Shielding Details
  • M-13338, System Piping Isometric
  • M-KA1333B, Design Change Drawing, DCP 90/109, Rev._16 M-KA13338, Design Change Drawing, DCP 90/109-1, Rev.16
  • M-1333C, System Piping Isometric
  • M-1331F, System Piping Isometric M-A1331F, System Piping Isometric

+ M-1336F, System Piping Isometric M 1356D, System Piping Isometric M-1355D, System Piping Isometric FSK-S 1094A-004-C, System Piping Isometric M-1371 A, System Piping Isometric M-1353M, System Piping Isometric M 1353K, System Piping Isometric

. M-1342F, System Piping Isometric ,

  • FSK-S 1078A-135-C, System Piping Isometric

. M 1343C, System Piping Isometric M-1351 A, System Piping Isometric

= M-13518, System Piping Isometric FSK-S-10788-127-C, System Piping Isometric

  • M-1357D, System Piping Isometric a FSK-S-00338-067-8, System Piping Isometric
  • FSK-S-00338-134-C, System Piping Isometric
3. Our recent submittal GNRO 97/00106, dated Nov. 4,1997 addresses item 5. In accordance with 10 CFR 50 Appendix B, and GL 91-18 (Rev.1) prompt corrective action to resolve the nonconforming condition will continue in a timely manner commensurate with the safety significance of the issue and is expected to be completed pHor to the restart from RF10 (now scheduled for Fall 1999).

Please feel free to contact Wayne Russell at (601) 437-2717 should you have any questions or require additionalinformation.

Yours truly, V'"

., Q (1-ttiachmenti 1 - Grand Gulf Nuclear Station Engineering Report GGNS-97-0002, Rev. 0 2 - Fabrication drawings of piping sections evaluated cc:' (See Next Page)

. . . . ~ _ - . . . _ . . .

-. GNRO-97/00114 .

' Page 3of4 cc: Ms. J. L. Dixon-Herrity, GGNS Senior Resident (w/a)

Mr. L J. Smith (Wise Carter)(w/o)

Mr. N. S. Reynolds (w/o)' I Mr. H. L. Thomas (w/o)  !

Mr. E. W. Merschoff (w/a) i Regional Administrator .J U.S. Nuclear Regulatory Commission l Region IV  ;

611 Ryan Plaza Drive, Suite 400

. Arlirigton, TX 76011 Mr. J. N. Donohew, Project Manager (w/2)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555

_ . _ _ _ _ _ _