ML051530547

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RAI Related to GL 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at pressurized-water Reactors
ML051530547
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/27/2005
From: Kalyanam N
NRC/NRR/DLPM/LPD4
To: Venable J
Entergy Operations
Kalyanam N,NRR/DLPM,415-1480
References
GL-04-002, TAC MC4729
Download: ML051530547 (4)


Text

May 27, 2005 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 (WATERFORD 3) -

REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NO. MC4729)

Dear Mr. Venable:

By letter dated March 3, 2005, Entergy Operations Inc. (the licensee), provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Waterford 3. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function.

Additionally, addressees were requested to submit to the NRC the information specified in the GL.

The NRC staff has completed its preliminary review of your response and has determined it needs additional information requested in the enclosure to complete our review.

This RAI requests additional information about your overall plans and schedules and not any information on detailed plans or extensive analyses. In light of this, please provide the additional information requested in the enclosure within 30 days of receipt of this letter.

If you have any questions, please call me at (301) 415-1480.

Sincerely,

/RA/

N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

RAI cc w/encl: See next page

May 27, 2005 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 (WATERFORD 3) -

REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NO. MC4729)

Dear Mr. Venable:

By letter dated March 3, 2005, Entergy Operations Inc. (the licensee), provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Waterford 3. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function.

Additionally, addressees were requested to submit to the NRC the information specified in the GL.

The NRC staff has completed its preliminary review of your response and has determined it needs additional information requested in the enclosure to complete our review.

This RAI requests additional information about your overall plans and schedules and not any information on detailed plans or extensive analyses. In light of this, please provide the additional information requested in the enclosure within 30 days of receipt of this letter.

If you have any questions, please call me at (301) 415-1480.

Sincerely,

/RA/

N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

RAI cc w/encl: See next page DISTRIBUTION PUBLIC PDIV-r/f RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDlpmLpdiv1 (DTerao) RidsNrrPMNKalyanam RidsNrrLADBaxley RidsRgn4MailCenter (DGraves) DCullison/DSolorio RidsNrrDlpmDpr RidsNrrDssaDpr MWebb Accession No.: ML051530547

  • RAI input from the staff without any major change OFFICE PDIV-1/PM PDIV-1/LA DSSA/SPLB/SP* PDIV-1/SC NAME NKalyanam DBaxley DCullison/DSolorio DTerao DATE 5/27/05 5/27/05 5-23-05 5/27/05 OFFICIAL COPY

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS" ENTERGY OPERATIONS INC.

WATERFORD STEAM ELECTRIC STATION, UNIT 3 By letter dated March 3, 2005, Entergy Operations Inc. (the licensee) provided its 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Waterford Steam Electric Station, Unit 3. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete its review:

1. In your 90-day response to GL 2004-02, you indicated that you intend to use future test results, industry guidance, and NRC guidance to account for chemical precipitants in your evaluation and their availability will impact the schedule for performing an evaluation. The cooperative NRC-Electric Power Research Institute tests in progress at the University of New Mexico are designed to determine if chemical effects occur, but are not designed to measure head loss associated with any chemical effects. The staff notes that some chemical effects have been observed in the initial three tests.
2. In your 90-day response to GL 2004-02, you indicated that you intend to use industry owners group guidance and component manufacturer data to evaluate long-term performance degradation of downstream susceptible components caused by debris-laden fluid and their availability will impact the schedule for performing an evaluation.

For both of these issues, you state their evaluation may occur after the September 1, 2005, response due date, depending on the schedule for testing and the availability of industry guidance. This is contrary to the information request in GL 2004-02, which requests that chemical and downstream effects be addressed in the September 1, 2005, response. This delay is also contrary to the staffs position that there is currently sufficient information to address sump vulnerability that the staff is not going to wait for additional test results. In addition, the September 1, 2005, response will be incomplete if the evaluation is not complete, the design is not complete, or there is no schedule for upgrades. Accordingly, please discuss your plans and schedule for evaluating chemical effects and the long-term downstream effects.

Discuss any plans for performing testing to support your evaluation of these effects.

Waterford Steam Electric Station, Unit 3 cc:

Mr. Michael E. Henry, State Liaison Officer Regional Administrator, Region IV Department of Environmental Quality U.S. Nuclear Regulatory Commission Permits Division 611 Ryan Plaza Drive, Suite 400 P.O. Box 4313 Arlington, TX 76011 Baton Rouge, Louisiana 70821-4313 Parish President Council Vice President Operations Support St. Charles Parish Entergy Operations, Inc. P. O. Box 302 P. O. Box 31995 Hahnville, LA 70057 Jackson, MS 39286-1995 Executive Vice President Director & Chief Operating Officer Nuclear Safety Assurance Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 17265 River Road Jackson, MS 39286-1995 Killona, LA 70066-0751 Chairman Wise, Carter, Child & Caraway Louisiana Public Services Commission P. O. Box 651 P. O. Box 91154 Jackson, MS 39205 Baton Rouge, LA 70825-1697 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Winston & Strawn 1700 K Street, N.W.

Washington, DC 20006-3817 Resident Inspector/Waterford NPS P. O. Box 822 Killona, LA 70066-0751 May 2005