ML080710001: Difference between revisions

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| number = ML080710001
| number = ML080710001
| issue date = 03/14/2008
| issue date = 03/14/2008
| title = Grand Gulf, Unit 1 - Request for Additional Information VRR-GGNS-2007-02 Request for Alternative from ASME OM Code 5-Year Test Interval for Main Stream Safety Relief Valves (TAC No. MD7758)
| title = Request for Additional Information VRR-GGNS-2007-02 Request for Alternative from ASME OM Code 5-Year Test Interval for Main Stream Safety Relief Valves
| author name = Donohew J N
| author name = Donohew J N
| author affiliation = NRC/NRR/ADRO/DORL/LPLIV
| author affiliation = NRC/NRR/ADRO/DORL/LPLIV

Revision as of 03:45, 10 February 2019

Request for Additional Information VRR-GGNS-2007-02 Request for Alternative from ASME OM Code 5-Year Test Interval for Main Stream Safety Relief Valves
ML080710001
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/14/2008
From: Donohew J N
NRC/NRR/ADRO/DORL/LPLIV
To:
Entergy Operations
Donohew J N, NRR/DLPM,415-1307
References
TAC MD7758, VRR-GGNS-2007-02
Download: ML080710001 (4)


Text

March 14, 2008

Vice President, Operations Entergy Operations, Inc. Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR ALTERNATIVE NO. VRR-GGNS-2007-02 FROM ASME OM CODE 5-YEAR TEST INTERVAL FOR MAIN STEAM SAFETY RELIEF VALVES (TAC NO. MD7758)

Dear Sir or Madam:

By letter dated January 8, 2008, Entergy Operations, Inc. (Entergy), submitted a Request for Alternative No. VRR-GGNS-2007-02 to extend the 5-year test interval, on a one-time basis, for 12 Main Steam Safety Relief Valves (SRVs) for Grand Gulf Nuclear Station. Entergy requests relief from American Society of Mechanical Engineers Operation and Maintenance Code (ASME OM Code), 2001 Edition through 2003 Appendix, "Code of Operation and Maintenance of Nuclear Power Plants," Subsection ISTC, Mandatory Appendix I.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and determined that additional information is required in order to complete the evaluation. The additional information being requested is related to the 12 Main Steam SRVs. The staff's request was provided to your staff via electronic mail on February 27, 2008. As discussed with Michael Larson of your staff, the NRC staff is requesting a response within 30 days of the date of this letter.

If you have any questions, please contact me at 301-415-1307.

Sincerely,

/RA/ Jack N. Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket No. 50-416

Enclosure:

Request for Additional Information cc: See next page March 14, 2008 Vice President, Operations Entergy Operations, Inc. Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR ALTERNATIVE NO. VRR-GGNS-2007-02 FROM ASME OM CODE 5-YEAR TEST INTERVAL FOR MAIN STEAM SAFETY RELIEF VALVES (TAC NO. MD7758)

Dear Sir or Madam:

By letter dated January 8, 2008, Entergy Operations, Inc. (Entergy), submitted a Request for Alternative No. VRR-GGNS-2007-02 to extend the 5-year test interval, on a one-time basis, for 12 Main Steam Safety Relief Valves (SRVs) for Grand Gulf Nuclear Station. Entergy requests relief from American Society of Mechanical Engineers Operation and Maintenance Code (ASME OM Code), 2001 Edition through 2003 Appendix, "Code of Operation and Maintenance of Nuclear Power Plants," Subsection ISTC, Mandatory Appendix I.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and determined that additional information is required in order to complete the evaluation. The additional information being requested is related to the 12 Main Steam SRVs. The staff's request was provided to your staff via electronic mail on February 27, 2008. As discussed with Michael Larson of your staff, the NRC staff is requesting a response within 30 days of the date of this letter.

If you have any questions, please contact me at 301-415-1307.

Sincerely, /RA/

Jack N. Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket No. 50-416

Enclosure:

Request for Additional Information cc: See next page DISTRIBUTION

PUBLIC LPLIV r/f RidsAcrsAcnw&mMailCenter RidsNrrDciCptb RidsNrrDorlDpr RidsNrrDorlLpl4 RidsNrrPMJDonohew RidsNrrLAJBurkhardt RidsOgcRp RidsRgn4MailCenter STingen, NRR/DCI/CPTB JMcHale, NRR/DCI/CPTB LWilkins, NRR/DORL/LPL4 ADAMS Accession No.: ML080710001 OFFICE NRR/LPL4/GE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME LWilkins JDonohew JBurkhardt THiltz DATE 3/13/08 3/14/08 3/12/08 3/14/08 OFFICIAL AGENCY RECORD Grand Gulf Nuclear Station (2/25/08) cc: Senior Vice President Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Vice President, Oversight Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995

Senior Vice President & Chief Operating Officer Entergy Operations, Inc. P.O. Box 31995 Jackson, MS 39286-1995 Associate General Counsel Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Manager, Licensing Entergy Operations, Inc. Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150 State Health Officer State Health Board P.O. Box 1700 Jackson, MS 39215 Attorney General Asst. Attorney General State of Mississippi P.O. Box 22947 Jackson, MS 39225-2947 Office of the Governor State of Mississippi Jackson, MS 39201

Attorney General Department of Justice State of Louisiana P.O. Box 94005 Baton Rouge, LA 70804-9005 President Claiborne County Board of Supervisors P.O. Box 339 Port Gibson, MS 39150

Richard Penrod, Senior Environmental Scientist/State Liaison Officer Office of Environmental Services Northwestern State University Russell Hall, Room 201 Natchitoches, LA 71497 Chief, Energy and Transportation Branch Environmental Compliance and Enforcement Division Mississippi Department of Environmental Quality P.O. Box 10385 Jackson, MS 39289-0385

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064

Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 399 Port Gibson, MS 39150

REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR ALTERNATIVE VRR-GGNS-2007-02 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416 By letter dated January 8, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080080589), Entergy Operations, Inc. (Entergy), submitted a Request for Alternative No. VRR-GGNS-2007-02 to extend the 5-year test interval, on a one-time basis, for 12 Main Steam Safety Relief Valves (SRVs) for Grand Gulf Nuclear Station, Unit 1 (GGNS). Entergy requests relief from American Society of Mechanical Engineers Operation and Maintenance Code (ASME OM Code), 2001 Edition through 2003 Appendix, "Code of Operation and Maintenance of Nuclear Power Plants," Subsection ISTC, Mandatory Appendix I.

The staff has reviewed the information provided and determined that the following additional information is required in order to complete the evaluation:

1. Verify that Valves 1B21-F041K, 1B21-F041F, 1B21-F051F, 1B21-F051B, 1B21-F041D, and 1B21-F047D were refurbished to a like-new condition prior to being placed in storage and later installed in October 2005. Verify that Valves 1B21-F047L, 1B21-F041G, 1B21-F047G, 1B21-F051C, and 1B21-F047C were refurbished to a like-new condition prior to being placed in storage and later installed in March 2007.
2. Discuss if the controlled environment for the storage of Valves 1B21-F041K, 1B21-F041F, 1B21-F051F, 1B21-F051B, 1B21-F041D, 1B21-F047D, 1B21-F047L, 1B21-F041G, 1B21-F047G, 1B21-F051C, and 1B21-F047C was equipped to prevent condensation and corrosion.
3. Please provide test results for Dikkers Model G-471 SRVs that were maintained in a controlled environment similar to the GGNS controlled environment for an extended period of time and setpoint tested prior to actual installation. As an alternative, discuss why the as-found set-pressure test results for Dikkers Model G-471 SRVs provided in a letter dated September 28, 2007 (Agencywide ADAMS Accession No. ML072740030) are applicable to the GGNS SRVs.

Enclosure