ML041180601
| ML041180601 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/26/2004 |
| From: | Donohew J NRC/NRR/DLPM/LPD4 |
| To: | Randolph G Union Electric Co |
| Donohew J N, NRR/DLPM,415-1307 | |
| References | |
| BN-03-001, TAC MB9562 | |
| Download: ML041180601 (5) | |
Text
April 26, 2004 Mr. Garry L. Randolph Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSES TO BULLETIN 2003-01, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS" (TAC NO. MB9562)
Dear Mr. Randolph:
By letters dated August 8, 2003 (ULNRC-04884), and March 25, 2004 (ULNRC-04966), you submitted responses to NRC Bulletin 2003-01, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors," dated July 9, 2003, for the Callaway Plant, Unit 1. The NRC issued Bulletin 2003-01 to all pressurized-water reactor (PWR) licensees requesting that they provide a response, within 60 days of the date of the bulletin, that contains either the information requested in the following Option 1 or Option 2 that was stated in the bulletin:
Option 1:
State that the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions have been analyzed with respect to the potentially adverse post-accident debris blockage effects identified in this bulletin, taking into account the recent research findings described in the Discussion section, and are in compliance with all existing applicable regulatory requirements.
Option 2:
Describe any interim compensatory measures that have been implemented or that will be implemented to reduce the risk which may be associated with potentially degraded or nonconforming ECCS and CSS recirculation functions until an evaluation to determine compliance is complete. If any of the interim compensatory measures listed in the Discussion section will not be implemented, provide a justification. Additionally, for any planned interim measures that will not be in place prior to your response to this bulletin, submit an implementation schedule and provide the basis for concluding that their implementation is not practical until a later date.
You provided a response that addressed Option 2 of the bulletin. In your response, you discussed the interim compensatory measures (ICMs) that have been and will be implemented, and the schedule for the implementation. The letter dated March 25, 2004, provided changes to the letter dated August 8, 2003, in which the sump screen inspection acceptance criteria were modified.
G. Randolph The NRC staff has reviewed and evaluated the information provided in your responses to the Bulletin and has determined that the enclosed additional information is needed to complete our review. These questions were sent to your staff by e-mail on April 20, 2004, to expedite your response to the questions and any differences from the enclosed questions are only editorial.
Because of the current refueling outage that you are in, your staff has agreed to respond by June 30, 2004. If you have any questions, please contact me at 301-415 1307, or through the internet at jnd@nrc.gov.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Request for Additional Information cc w/encl: See next page
G. Randolph April 26, 2004 The NRC staff has reviewed and evaluated the information provided in your responses to the Bulletin and has determined that the enclosed additional information is needed to complete our review. These questions were sent to your staff by e-mail on April 20, 2004, to expedite your response to the questions and any differences from the enclosed questions are only editorial.
Because of the current refueling outage that you are in, your staff has agreed to respond by June 30, 2004. If you have any questions, please contact me at 301-415 1307, or through the internet at jnd@nrc.gov.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC PDIV-2 Reading RidsNrrDlpmPdiv (HBerkow)
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MKowal AWang SWeerakkody ACCESSION NO.: ML041180601 NRR-088 OFFICE PDIV-2/PM PDIV-2/LA Bull 2003-01/LPM PDIV-2/SC NAME JDonohew:mp EPeyton AWang SDembek DATE 4/26/04 4/23/04 4/26/04 4/26/04 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML041180601.wpd OFFICIAL RECORD COPY
Callaway Plant, Unit 1 cc:
Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855 John ONeill, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington, D.C. 20037 Mr. Mark A. Reidmeyer, Regional Regulatory Affairs Supervisor Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251 U.S. Nuclear Regulatory Commission Resident Inspector Office 8201 NRC Road Steedman, MO 65077-1302 Mr. Chris Younie Manager, Quality Assurance AmerenUE P.O. Box 620 Fulton, MO 65251 Manager - Electric Department Missouri Public Service Commission 301 W. High P.O. Box 360 Jefferson City, MO 65102 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Mr. Ronald A. Kucera Deputy Director for Public Policy Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65102 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839 Mr. Dan I. Bolef, President Kay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, MO 63130 Mr. Lee Fritz, Presiding Commissioner Callaway County Court House 10 East Fifth Street Fulton, MO 65151 Mr. David E. Shafer Superintendent, Licensing Regulatory Affairs AmerenUE P.O. Box 66149, MC 470 St. Louis, MO 63166-6149 Mr. Keith D. Young Manager, Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251 Mr. Scott Clardy, Director Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109
REQUEST FOR ADDITIONAL INFORMATION RELATED TO BULLETIN 2003-01, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED WATER REACTORS" UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 By letter dated August 8, 2003, Union Electric Company (the licensee) submitted the response for the Callaway Plant, Unit 1 (Callaway) to NRC Bulletin 2003-01, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors [PWRs]," dated July 9, 2003. The response was supplemented in the letter of March 25, 2004, in which the licensee provided changes to its letter dated August 8, 2003, related to the sump screen inspection acceptance criteria. The following request for additional information is based on these letters:
1.
The Westinghouse Owners Group (WOG) has developed operational guidance in response to Bulletin 2003-01 for Westinghouse and Combustion Engineering (CE)-type PWRs. For Callaway, the response stated that the licensee will consider plant specific procedural modifications that would delay the switchover to containment sump recirculation after the WOG program has been completed. Please provide a discussion of the WOG recommended compensatory measures that have been or will be implemented for Callaway. Include a discussion of the evaluations or analyses performed to determine that these compensatory measures are acceptable for Callaway and provide technical justification for those WOG compensatory measures not being implemented. Also include a detailed discussion of the procedures being modified, the operator training being implemented, and the schedule for implementing these compensatory measures.
2.
In the response to Bulletin 2003-01, it is stated that the licensee will be implementing operator training on indications of and responses to sump clogging. However, the response does not completely discuss the operator training to be implemented. Please provide a detailed discussion of the operating procedures to be modified, the indications of sump clogging that the operators are instructed to monitor, and the response actions the operators are instructed to take in the event of sump clogging and loss of emergency core cooling system recirculation capability.
3.
In the supplemental response to Bulletin 2003-01 dated March 25, 2004, it is stated that the sump screen inspection acceptance criteria has been modified by adding acceptable tolerances to each criterion associated with breaches in the sump screens. Please provide the technical basis for these tolerances, including how they were determined, and why they are acceptable.