Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARML1014501152010-05-18018 May 2010
License Amendment Request for Reactor Coolant System Pressure Transmitter Replacement
Project stage: Request
ML1017206072010-06-21021 June 2010
Acceptance Review Email, License Amendment Request, Revise Technical Specification 6.8.3.1, Containment Post Tensioning System Surveillance Program, Consistent with Updated Edition of ASME Code, Section XI
Project stage: Acceptance Review
ML1102403852011-01-24024 January 2011
Request for Additional Information, License Amendment Request, Revise TS 6.8.3.I, Containment Post Tensioning System Surveillance Program, Consistent with Updated Edition of ASME Code Section XI
Project stage: RAI
NOC-AE-11002632, Revised Proposed Amendment to Technical Specification 6.8.3.I for Containment Post-Tensioning System Surveillance Program2011-03-0101 March 2011
Revised Proposed Amendment to Technical Specification 6.8.3.I for Containment Post-Tensioning System Surveillance Program
Project stage: Other
ML1106902232011-03-0101 March 2011
Revised Proposed Amendment to Technical Specification 6.8.3.I for Containment Post-Tensioning System Surveillance Program
Project stage: Other
NRC-2011-0063, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 6.8.3.I, Containment Post Tensioning System Surveillance Program, Consistent with Updated Edition of ASME Code, Section Xi2011-03-15015 March 2011
Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 6.8.3.I, Containment Post Tensioning System Surveillance Program, Consistent with Updated Edition of ASME Code, Section Xi
Project stage: Approval
ML1107405092011-03-15015 March 2011
Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 6.8.3.I, Containment Post Tensioning System Surveillance Program, Consistent with Updated Edition of ASME Code, Section XI
Project stage: Other
ML1107405012011-03-15015 March 2011
Letter, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification 6.8.3.I, Containment Post Tensioning System Surveillance Program, Consistent with Updated Edition of ASME Code, Section XI
Project stage: Other
NOC-AE-11002665, Proposed Amendment to Technical Specifications for Containment Post-Tensioning System Surveillance Program (Revision 2) (TAC ME3969/ME3970)2011-05-0202 May 2011
Proposed Amendment to Technical Specifications for Containment Post-Tensioning System Surveillance Program (Revision 2) (TAC ME3969/ME3970)
Project stage: Other
ML11129A0272011-05-0202 May 2011
Proposed Amendment to Technical Specifications for Containment Post-Tensioning System Surveillance Program (Revision 2) (TAC ME3969/ME3970)
Project stage: Other
ML1113702772011-05-27027 May 2011
Issuance of Amendment Nos. 196 and 184, Revise Technical Specification 6.8.3.I, Containment Post Tensioning System Surveillance Program and Surveillance Requirement 4.6.1.6, Containment Prestressing System
Project stage: Approval
2011-03-01
[Table View] |
Text
From:
Thadani, Mohan Sent:
Monday, June 21, 2010 3:31 PM To:
Harrison, Albon Cc:
Lingam, Siva; Lent, Susan; Burkhardt, Janet; Khanna, Meena
Subject:
ACCEPTANCE REVIEW FOR AMENDMENT TO TS 6.8.3.1. "COTAINMENT POST-TENSSIONING SYSTEM SURVEILLANCE PROGRAM."
Mr. Edward D. Halpin Chief Nuclear Officer STP Nuclear Operating Company South Texas Project P. O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - RE: AMENDMENT TO TECHNICAL SPECIFICATION 6.8.3.1 "COTAINMENT POST-TENSSIONING SYSTEM SURVEILLANCE PROGRAM. (TAC NOS. ME3969 AND E3970)
Dear Mr. Halpin:
By letter dated May 18, 2010, (ADAMS Accession No. ML101450414), STP Nuclear Operating Company (the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) staff approval of an amendment to Technical Specification 6.8.3.1, Containment Post-Tensioning System Surveillance Program, for South Texas Project, Units 1 and 2.
The purpose of this letter is to provide the results of the NRC staff=s acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-1476.
Mohan C Thadani Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov
