ML043130439

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RAI, Response to Bulletin 2004-01
ML043130439
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/10/2004
From: Robert Pascarelli
NRC/NRR/DLPM/LPD2
To: Singer K
Tennessee Valley Authority
pascarelli, R J, NRR/DLPM, 415-1245
References
BL-04-001, TAC MC3512, TAC MC3513
Download: ML043130439 (5)


Text

November 10, 2004 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37401-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO NRC BULLETIN 2004-01 (TAC NOS. MC3512 AND MC3513)

Dear Mr. Singer:

By a letter dated July 27, 2004, Tennessee Valley Authority (TVA) provided a response to U.S. Nuclear Regulatory Commission (NRC)Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. The NRC staff has reviewed TVAs submittal and finds that additional information is needed before we can complete our review of TVAs response.

This request for additional information was discussed with your staff and a response is requested within 30 days of the receipt of this letter. If you have any questions, please feel free to contact me at (301) 415-1245.

Sincerely,

/RA/

Robert J. Pascarelli, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosure:

Request for Additional Information cc w/encl: See next page

November 20, 2004 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37401-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO NRC BULLETIN 2004-01 (TAC NOS. MC3512 AND MC3513)

Dear Mr. Singer:

By a letter dated July 27, 2004, Tennessee Valley Authority (TVA) provided a response to U.S. Nuclear Regulatory Commission (NRC)Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. The NRC staff has reviewed TVAs submittal and finds that additional information is needed before we can complete our review of TVAs response.

This request for additional information was discussed with your staff and a response is requested within 30 days of the receipt of this letter. If you have any questions, please feel free to contact me at (301) 415-1245.

Sincerely,

/RA/

Robert J. Pascarelli, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosure:

Request for Additional Information cc w/encl: See next page Distribution:

PUBLIC RidsOgcRp RidsNrrPMRPascarelli RidsRgn2MailCenter (SCahill)

PDII-2 R/F RidsAcrsAcnwMailCenter BClayton (Hard copy)

SCoffin RidsNrrDlpmLpdii2 (MMarshall)

TColburn EAndruszkiewicz ADAMS Accession Number: ML043130439 NRR-088 OFFICE PDII-2/PM PDII-2/LA PDII-2/SC NAME RPascarelli BClayton MMarshall DATE 11/10/04 11/10/04 11/10/04 OFFICIAL RECORD COPY

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION NRC BULLETIN 2004-01 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of your response, dated July 27, 2004, to NRC Bulletin 2004-01, Response to NRC Bulletin 2004-01:

Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-water Reactors. Based on the staffs review, please provide a supplemental response which addresses the following question.

Your response to Bulletin 2004-01 Question (1)(c) did not clearly communicate your intentions with respect to ensuring that an appropriate dialogue would be established with NRC technical staff in the event that circumferential primary water stress corrosion cracking (PWSCC) is identified at any locations covered under the scope of Bulletin 2004-01. The NRC staff addressed this issue, in part, on page 5 of Bulletin 2004-01 stating,... the NRC staff believes that the topic of NDE [nondestructive examination] scope expansion should be discussed with the NRC if circumferential PWSCC is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of this bulletin to ensure that the licensee has performed an adequate extent-of-condition evaluation.

Because of the potential plant-specific and generic significance of circumferential PWSCC at locations covered under the scope of Bulletin 2004-01, it is the NRC staffs position that cognizant members of the Office of Nuclear Reactor Regulations Materials and Chemical Engineering Branch (EMCB) should be promptly made aware of any emerging issue regarding this degradation phenomenon at your facility. This is important not only for the reason cited in the passage above, from Bulletin 2004-01, but also so that the NRC staff can evaluate any such information and fulfill its obligation to inform other U.S. nuclear power plant licensees of new operational experience which may be relevant to the continued safe operation of their facilities.

It is the NRC staffs expectation that, if you obtain inspection results in the future that indicate that circumferential PWSCC may be occurring at any location covered under the scope of Bulletin 2004-01, you should contact your NRC Headquarters Project Manager (PM) and request a teleconference or meeting with EMCB technical staff. Notification of your NRC PM should allow ample time for you to incorporate any insights from the aforementioned teleconference or meeting into your plans for evaluating the extent of condition at your facility prior to the end of the outage during which the degradation was discovered.

In order to document TVAs intent to follow the guidance stated above, please provide a supplement to your Bulletin 2004-01 item (1)(c) response which states:

If circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of this bulletin, [we] will develop plans to perform an adequate extent-of-condition evaluation and [we] will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.

Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, General Manager Nuclear Engineering Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Randy Douet Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Frederick C. Mashburn Senior Program Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Paul L. Pace, Manager Licensing and Industry Affairs ATTN: Mr. James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. David A. Kulisek, Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. M. Scott Freeman Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, TN 37379 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 County Mayor Hamilton County Courthouse Chattanooga, TN 37402-2801