ML060890464
| ML060890464 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/09/2006 |
| From: | Pickett D Plant Licensing Branch III-2 |
| To: | Singer K Tennessee Valley Authority |
| Pickett , NRR/DLPM, 415-1364 | |
| References | |
| TAC MC9271 | |
| Download: ML060890464 (5) | |
Text
May 9, 2006 Mr. Karl W. Singer
Chief Nuclear Officer and
Executive Vice President
Tennessee Valley Authority
6A Lookout Place
1101 Market Street
Chattanooga, Tennessee 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INTEGRITY (TSTF-449) (TAC NOS. MC9271)
Dear Mr. Singer:
By letter dated December 15, 2005, Tennessee Valley Authority (TVA), submitted an application for an amendment to revise the Watts Bar Nuclear Plant, Unit 1 technical specification (TS)
requirements consistent with Technical Specification Task Force (TSTF) Traveler, TSTF-449, Revision 4, "Steam Generator Tube Integrity." As stated on page E1-3 of Enclosure 1 to the
application, the current steam generators will be replaced in September 2006. In addition, the
approved alternate tube repair criteria (ARC) (i.e., voltage based ARC for outside diameter
stress corrosion cracking and the use of the F-star), and the sleeving repair method will be
deleted as part of this TS change.
The Nuclear Regulatory Commission staff has reviewed the application consistent with the model safety evaluation dated March 2, 2005 (70 FR 10298), and determined the need for
additional information to complete its review.
We request that TVA provide responses to the enclosed request for additional information within 60 days. If you have any questions about this material, please contact me at (301) 415-1364.
Sincerely,/RA/ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2
Division of Operating Reactor Licensing
Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Request for Additional Information
cc w/enclosure: See next page
ML060890464NRR-088OFFICELPL2-2LPL2-2/PMLPL2-2/LABC:CSGBLPL2-2/BCNAMESCraneDPickettRSola EMurphy for AHiser BMozafari for MMarshallDATE4/13/064/14/064/14/064/14/065/9/06
Mr. Karl W. Singer Tennessee Valley Authority WATTS BAR NUCLEAR PLANT 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 President Nuclear Engineering & Technical Services
Tennessee Valley Authority
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801 Mr. Robert J. Beecken, Vice President Nuclear Support
Tennessee Valley Authority
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs Site Vice President
Watts Bar Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000
Spring City, TN 37381 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. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs
Tennessee Valley Authority 4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801 Mr. Paul L. Pace, Manager Licensing and Industry Affairs
Watts Bar Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000
Spring City, TN 37381 Mr. Jay Laughlin, Plant Manager Watts Bar Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000
Spring City, TN 37381 Senior Resident Inspector Watts Bar Nuclear Plant
U.S. Nuclear Regulatory Commission
1260 Nuclear Plant Road
Spring City, TN 37381 County Executive 375 Church Street
Suite 215 Dayton, TN 37321 County Mayor P. O. Box 156
Decatur, TN 37322 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 Ms. Ann P. Harris 341 Swing Loop Road
Rockwood, Tennessee 37854 Enclosure REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT, UNIT 1 APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT REGARDING STEAM GENERATOR TUBE INTEGRITY (TSTF-449)
DOCKET NO. 50-390 TAC NO. MC9271 By letter dated December 15, 2005 (Agencyw ide Documents Access and Management System (ADAMS) No. ML053540067), Tennessee Valley Authority (the licensee), submitted an
application for an amendment to revise the Watts Bar Nuclear Plant, Unit 1 technical
specification (TS) requirements consistent with Technical Specification Task Force (TSTF)
Traveler, TSTF-449, Revision 4, "Steam Generator Tube Integrity." (ADAMS No.
ML051090200). As stated on page E1-3 of Enclosure 1 to the application, the current steam
generators will be replaced in September 2006. In addition, the approved alternate tube repair
criteria (ARC) (i.e., voltage based ARC for outside diameter stress corrosion cracking and the
use of the F-star), and the sleeving repair method will be deleted as part of this TS change.
The Nuclear Regulatory Commission (NRC), Steam Generator Tube Integrity and Chemical Engineering Branch staff has reviewed the application consistent with the model safety
evaluation dated March 2, 2005 (70 FR 10298), and determined the need for the following
additional information to complete its review:1.Insert A of Enclosure 2 to the application contains TS 5.7.2.12, "Steam Generator (SG) Program," and corresponds to Insert 5.5.9 of TSTF-449, Revision 4.
The last sentence in TS 5.7.2.12.a states, "Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected and/or
plugged, to confirm that the performance criteria are being met." The intent of this
paragraph is to ensure that condition monitoring assessments are conducted when
the SG tubes are inspected or plugged as stated in paragraph a of Insert 5.5.9 of
TSTF-449, Revision 4. The staff requests the licensee to either justify the use of "and/or" in the last sentence of TS 5.7.2.12.a or to replace "and/or" with "or."2.Insert A of Enclosure 2 to the application contains TS 5.7.2.12, "Steam Generator (SG) Program," and corresponds to Insert 5.5.9 of TSTF-449, Revision 4.
The last sentence in TS 5.7.2.12.b.2 states, "The accident induced leakage is not to exceed 1.0 gpm for the faulted SG." The corresponding sentence in Insert 5.5.9 of
TSTF-449, Revision 4, states, "Leakage is not to exceed [1 gpm] per SG [,except
for specific types of degradation at specific locations described in paragraph c of
the Steam Generator Program]." The intent of this sentence is to ensure that
leakage does not exceed 1 gpm in any SG except for those instances defined in paragraph c of the SG program. The staff requests the licensee to discuss its plans to modify this sentence consistent with TSTF-449, Revision 4.3.Enclosure 3 to the application includes the new bases for TS 3.4.17, "Steam Generator (SG) Tube Integrity," and corresponds to section B 3.4.20, "Steam
Generator (SG) Tube Integrity," found on pages B 3.4.20-1 through B 3.4.20-7 of
TSTF-449, Revision 4.
On page B 3.4-100 of the application, second paragraph under "Applicable Safety Analysis," the last sentence reads, "The dose consequences of these events are
within the limits of GDC 19 (Ref. 2), and 10 CFR 100 (Ref. 3)." The corresponding
sentence on page B 3.4.20-2 of TSTF-449, Revision 4, includes, "or the NRC
approved licensing basis (e.g., a small fraction of these limits)." The staff requests
the licensee to justify the exclusion of this phrase from its application.4.Enclosure 3 to the application includes the new bases for TS 3.4.17, "Steam Generator (SG) Tube Integrity," and corresponds to section B 3.4.20, "Steam
Generator (SG) Tube Integrity," found on pages B 3.4.20-1 through B 3.4.20-7 of
TSTF-449, Revision 4.
On page B 3.4-102 of the application, second paragraph under "Actions," the last sentence reads, "If it is determined that tube integrity is not being maintained until
the next SG inspection, Condition B applies." The corresponding sentence on page
B.3.4.20-4 of TSTF-449, Revision 4, does not include the phrase "until the next SG
inspection," however, the required action found in Enclosure 2 of the application, page 3.4-43, includes the phrase, "until the next refueling outage or SG tube
inspection." The staff requests the licensee to justify the deviation from the action
described in TS 3.4.17 and the wording in TSTF-449, Revision 4.