ML20134N680
| ML20134N680 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/19/1997 |
| From: | Hernan R NRC (Affiliation Not Assigned) |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| References | |
| TAC-M96998, TAC-M96999, NUDOCS 9702240355 | |
| Download: ML20134N680 (4) | |
Text
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i Mr. Oliver D. Kingsley, Jr.-
President, TVA Nuclear and February 19, 1997 Chief Nuclear Officer Tennessee Valley Authority I
6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - TECHNICAL SPECIFICATION CHANGE REQUEST TS 96-05 FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TAC NOS. M96998 AND M96999)
Dear Mr. Kingsley:
l The staff is reviewing the subject proposed Technical Specification change requests submitted by the Tennessee Valley Authority in a letter dated October 18, 1996.
The proposed changes would remove footnotes pertaining to alternate steam generator plugging criteria (APC). These criteria were placed in previous license amendments for each unit but were stipulated only for Cycle 8 of operation.
Removing the footnotes would make the APC valid for all future cycles of operation. To complete our review-of your request, the response to the attached request for additional information is needed.
Please contact me at (301) 415-2010 if you have any questions.
Sincerely, Original signed by Ronald W. Hernan, Senior Project Manager i
Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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i Docket Nos. 50-327 and 50-328
Enclosure:
Request for Additional Information lgg{gg,gg{$ ggpy cc w/ enclosure:
See next page Distribution:
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DOCUMENT NAME: G:\\SQN\\96998.RAI T3 GET a copy of this document, Indicate in the bon:
"C" = Copy without attachment / enclosure EEn a copy with attachment / enclosure-
"N" = No copy 0FFICE PDII-4/PM / /, l PDII-4/lA R/ $ PDII-4/D,)
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NAME RHernan - M-BClaytok7 FHebdon 4d DATE 2//Q /9'/
2/ lS /97 2/ (9 /97 0FFICIA RECORD COPY 9702240355 970219 PDR ADOCK 05000327 P
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Mr. Oliver D. Kingsley, Jr.
SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority
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Mr. 0.*J.'Zeringue, Sr. Vice President Mr. J. T. Herron, Plant Manager Nuclear 0perations.
Sequoyah Nuclear Plant i
Tennessee Valley Authority '
. Tennessee Valley Authority
. 6A Lookout Place N
P.O. Box 2000 1101 Market ~ Street Soddy Daisy, TN 37379 Chattanooga, TN 37402-2801' Regional Administrator s
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Mr. Mark 0. Medford,lVice President U.S. Nuclear Regulatory Commission fi Engineering & Technical Services Region II Tenne'ssee.. Valley Authority-101 Marietta Street, NW., Suite 2900 6A Lookout Place Atlanta, GA 30323 1101 Market Street Chattanooga, TN 37402-2801 Mr. Melvin C. Shannon Senior Resident Inspector Mr. R. J. Adney, Site Vice President Sequoyah Nuclear Plant Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road P.O." Box 2000 Soddy Daisy, TN 37379 Soddy Daisy, TN 37379 Mr. Michael H. Mobley, Director General Counsel Division of Radiological Health Tennessee Valley Authority 3rd Floor, L and C Annex ET 10H 401 Church Street 400 West Summit Hill Drive Nashville, TN 37243-1532 Knoxville, TN 37902 County Executive Mr. Raul R. Baron, General Manager Hamilton County Courthouse Nuclear Assurance and Licensing Chattanooga, TN 37402-2801 Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Pedro Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Ralph H. Shell, Manager Licensing and Industry Affairs Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37379 s
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.i REQUEST FOR ADDITIONAL INFORMATION REVIEW OF TECHNICAL SPECIFICATION AMENDMENT REGARDING VOLTAGE-BASED ALTERNATE REPAIR CRITERIA FOR STEAM GENERATOR TUBES SEQUOYAH UNITS 1 AND 2 DOCKET NOS: 50-327 AND 50-328 In a letter dated October 18, 1996, the Tennessee Valley Authority (TVA) submitted for staff review an amendment to change the Technical Specifications (TS) for the Sequoyah Nuclear Plant, Units 1 and 2.
The proposed change removes the footnotes in the existing TS that limit application of voltage-based alternate repair criteria (ARC) for the steam generator 'ubes in Sequoyah units 1 and 2 to cycle 8 operation. Once the footno,es are removed, TVA may apply the voltage-based repair criteria to the steam generator tubes permanently.
TVA referenced three submittals dated September 7,1995, December 12, 1995 and "irch 4, 1996 as documents that contain technical basis to support the current amendment request. The September 7,1995 submittal contains technical basis for the implementation of the interim ARC for Unit 1.
The Decembar 12, 1995 and March 4,1996 submittals contain technical basis for the implementation of the interim ARC for Unit 2.
After reviewing the three documents, the staff requests the following additional information:
1.
TVA referenced the Westinghouse report, 'SLB Leak Rate and Tube Burst Probability Analysis Methods for ODSCC at TSP Intersections,"
WCAP-14277, as a source for performing calculations for burst probability, end of cycle voltage distribution, and leak rate.
Westinghouse published revision 1 of WCAP-14277 in December 1996 because the staff did not find the original report to be acceptable for referencing in safety evaluations.
TVA needs to update its commitment to use Revision 1 of the report.
2.
TVA needs to update its commitment to the latest database it intends to use in performing the calculations specified in Generic Letter (GL) 95-05 for the upcoming Unit I steam generator inspection. On a permanent basis, TP. needs to commit to the protocols for the use of the NRC-approved steam generator database.
3.
TVA submitted plans for inspecting dents at tube support plates for both units in its previous TS amendment requests.
However, for the current j
amendment request, TVA needs to clarify its dent inspection criteria in l
light of revisions to the inspection criteria that may be needed due to the results of inspecting dents less than 5 volts, either in the past or in the future.
Enclosure l
1 a
I 4.
TVA committed to various industry criteria for probe wear and variability in previous amendment requests; however, there have been new probe wear and variability criteria developed since 1995. Therefore, 1
TVA needs to update its commitsent to comply with the criteria proposed, finalized and agreed upon in the following letters:
(1) the Nuclear En6egy Institute (NEI) letter to NRC, subject: " Eddy Current Probe Replacement Criteria for Use in ODSCC Alternate Repair Criteria," January 23, 1996; (2) the NEI letter to NRC, subject: "New Probe Variability for Use in i
the 00 SCC Alternate repair Criteria," January 23, 1996; (3) the NEI letter to NRC, subject: " Eddy Current Probe Replacement Criteria for Use in 00 SCC Alternate Repair Criteria (Project No. 689)," February 23, 1996; (4) the letter from B. Sheron of NRC to A. Marion of NEI dated February 9, 1996; and (5) the letter from B. Sheron of NRC to A. Marion of NEI dated l
Narch 18, 1996.
5.
TVA has incorporated the model TS specified in GL 95-05 into the l
existing unit I and 2 technical specifications and has committed to certain sections in Attachment 1 of GL 95-05. However, it is not clear in TVA's previous submittal whether it has committed to comply with all sections in Attachment 1 of GL 95-05. To clarify, TVA needs to commit to comply with GL 95-05 in its entirety. Alternatively, TVA needs to provide exceptions to GL 95-05, should there be any.
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