ML062180078

Sequoyah, Units 1 and 2 - RAI Re Snubber Examination and Testing

ML062180078
Person / Time
Site:	Sequoyah
Issue date:	08/08/2006
From:	Pickett D V NRC/NRR/ADRO/DORL/LPLII-2
To:	Singer K W Tennessee Valley Authority
Pickett D V, NRR/DORL, 415-1364
References
TAC MC9657, TAC MC9658
Download: ML062180078 (5)

Text

August 8, 2006Mr. Karl W. SingerChief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FORADDITIONAL INFORMATION REGARDING SNUBBER EXAMINATION AND TESTING (TAC NOS. MC9657 AND MC9658)

Dear Mr. Singer:

By letter dated January 25, 2006, Tennessee Valley Authority (the licensee) requested relieffrom the American Society of Mechanical EngineersSection XI Code requirements for snubber examination and testing. The proposed request for relief is a continuation of the previously approved relief request from the Sequoyah Nuclear Plant (SQN), Units 1 and 2 second 10-year inspection interval and was submitted for applicability during SQN's third 10-year inspectioninterval that began on June 1, 2006.In order for the staff to complete its review of this application, we request that the licenseeprovide responses to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you intend to respond to this RAI within 30 days of receipt of this letter.Sincerely,/RA/Douglas V. Pickett, Senior Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-327 and 50-328

Enclosure:

As stated cc w/encl: See next page

ML062180078NRR-088OFFICELPL2-2/PMLPL2-2/LA(A) CPTB/BCLPL2-2/BCNAMEDPickettRSolaCHammer for TLiuLRaghavan for MMarshallDATE 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 Mr. Karl W. SingerSEQUOYAH NUCLEAR PLANTTennessee 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. Larry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Robert J. Beecken, Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Randy DouetSite Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000General CounselTennessee Valley Authority ET 11A 400 West Summit Hill DriveKnoxville, TN 37902Mr. John C. Fornicola, ManagerNuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. Paul L. Pace, ManagerLicensing and Industry Affairs ATTN: Mr. James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000Mr. David A. Kulisek, Plant ManagerSequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000Senior Resident InspectorSequoyah Nuclear Plant U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, TN 37379Mr. Lawrence E. Nanney, DirectorDivision of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532County MayorHamilton County Courthouse Chattanooga, TN 37402-2801Ms. Ann P. Harris341 Swing Loop Road Rockwood, Tennessee 37854 REQUEST FOR ADDITIONAL INFORMATIONSEQUOYAH NUCLEAR PLANT UNITS 1 AND 2SNUBBER RELIEF REQUESTSNUBBERS INSPECTION AND TESTING FOR THIRD 10-YEAR INTERVALTAC NOS. MC9657 AND MC96581.The licensee requested relief from the requirements of IWF-5200(a) and (b), and IWF-5300(a) and (b) (Page E1-2). IWF-1220 states that "the inservice inspection requirements for snubbers shall be in accordance with the requirements of IWF-5000."

Article IWF-5000 also contains requirements for snubber preservice and inservice examinations, and tests for snubbers integral and nonintegral attachments under IWF-5200(c) and IWF-5300(c). Please explain, whether and how the requirements of IWF-5200(c) and IWF-5300(c) will be met. 2.The licensee requested relief from IWF-5400, Repair/ Replacement Activities (Page E1-2). IWF-5400 states that "Repair/replacement activities performed on snubbers shall be in accordance with IWA-4000. Snubbers installed, corrected or modified by repair/replacement activities shall be examined and tested in accordance with the applicable requirements of IWF-5200 prior to return to service." Please explain, whether and how IWF-5200(c) requirements of IWF-5200 will be met.

3.IWF-5200(a) and (b), and IWF-5300(a) and (b) states that "preservice and inserviceexamination and testings shall be performed in accordance with ASME/ANSI OM, Part 4." Under Basis for Relief (Page E1-3), the licensee states that "Sequoyah Nuclear Plant (SQN) Technical Requirement Manual (TRM) adopts the provisions provided in NRC Generic Letter (GL) 90-09." GL 90-09, only provides guidance for Snubber Visual Examination Intervals and Corrective Actions. GL-90-09 does not replace any other requirements of OM Part 4. Therefore please explain the following:3a.OM-4, Section 2.1 requires preservice examination of snubbers. Please explain,how these preservice requirements are met in the proposed alternative SQN TRM.3b.OM-4, Section 3.1 requires preservice operability testing of snubbers. Pleaseexplain, how these preservice operability testing requirements are met in theproposed alternative SQN TRM.4.On page E1-4, last paragraph, the licensee states that "Performance of each test orinspection is documented and retained with the site procedure as a summary report with the data similar to the requirements prescribed in the ASME Section XI Code. The licensee is to provide actual subsection and/or paragraph of ASME Section XI, which is intended to meet for this requirement of documentation.Enclosure 5.Please explain, how the requirements of OM-4, Section 3.2.4 "Inservice OperabilityFailure Evaluation" are met in the proposed alternative as specified in the SQN TRM.