ML112232205
| ML112232205 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/23/2011 |
| From: | John Lamb Watts Bar Special Projects Branch |
| To: | Bhatnagar A Tennessee Valley Authority |
| Lamb J 301-415-3100 | |
| References | |
| TAC MD6717, GL-08-001 | |
| Download: ML112232205 (4) | |
Text
August 23, 2011 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - CLOSEOUT OF GENERIC LETTER 2008-01, MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS (TAC NO. MD6717)
Dear Mr. Bhatnagar:
On January 11, 2008, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (NRC Agencywide Documents Access and Management System (ADAMS) Accession No. ML072910759). The stated purpose of GL 2008-01 was (a) to request addressees to submit information to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance; and, (b) to collect the requested information to determine if additional regulatory action is required.
GL 2008-01 requested that licensees provide the following information within 9 months of the date of the GL:
(a) A description of the results of evaluations that were performed pursuant to requested actions specified in the GL. This description should provide sufficient information to demonstrate that you are or will be in compliance with the quality assurance criteria in Sections III, V, XI, XVI, and XVII of Appendix B to Title 10, Code of Federal Regulations Part 50 and the licensing basis and operating license as those requirements apply to the subject systems; (b) A description of all corrective actions, including plant, programmatic, procedure, and licensing basis modifications that you determined were necessary to assure compliance with these regulations; and, (c) A statement regarding which corrective actions were completed, the schedule for completing the remaining corrective actions, and the basis for that schedule.
A. Bhatnager Watts Bar Nuclear Plant (WBN), Unit 2 is a holder of a construction permit and as such was not an addressee of GL 2008-01. However, in support of its operating license application, TVA, in letter dated January 29, 2008 (ML080320443), provided an "Open Action Required for Licensing" to respond to GL 2008-01.
By letters dated April 10, 2008 (ADAMS ML081050481), May 9, 2008 (ML081360101),
June 6, 2008 (ML081630086), July 11, 2008 (ML081970084), October 1, 2008 (ML082800172),
and March 11, 2011 (ML110750022), Tennessee Valley Authority submitted information in response to GL 2008-01 for WBN Unit 2. The NRC staff has reviewed the submitted information and has concluded that for WBN Unit 2, you responded to the requested information.
Consequently, your GL response is considered closed. In a letter dated March 11, 2011, TVA made seven commitments. For convenience, the seven commitments are listed below:
- 1.
Tennessee Valley Authority will evaluate adopting the revised Improved Standard Technical Specification Surveillance Requirement (SR) 3.5.2.3 (NUREG 1431) at WBN Unit 2 within 6 months of NRC approval of the Traveler.
- 2.
Complete evaluation of Containment Spray pump 2A-A pipe chase horizontal suction piping for venting. Add a vent valve to this location or conduct periodic ultrasonic thickness examinations if necessary (90 days prior to fuel load).
- 3.
Add vent valves to selected locations in the Emergency Core Cooling System (ECCS) and Residual Heat Removal System (RHRS) piping to enhance filling and venting (90 days prior to fuel load).
- 4.
Complete walk down survey of ECCS and RHRS piping and evaluate the piping for latent voids that could exceed 5-percent of the pipe cross sectional area (90 days prior to fuel load).
- 5.
Operating procedures are being revised to improve instructions for filling and venting portions of the ECCS discharge pipe (90 days prior to fuel load).
- 6.
Complete Preoperational tests on ECCS and RHRS systems to confirm WBN Unit 1 operating experience showing no gas intrusion/accumulation issues (90 days prior to fuel load).
- 7.
Periodic venting procedures used to meet SR 3.5.2.3 are being revised to require that a report is entered into the Corrective Action Program for an extended gas release (90 days prior to fuel load).
A. Bhatnager Notwithstanding, the NRC's Region II staff may decide to perform (and would contact you to schedule) an inspection using Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01 and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
If you have any questions regarding this matter, I may be reached at 301-415-3100.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv
Notwithstanding, the NRC's Region II staff may decide to perform (and would contact you to schedule) an inspection using Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01 and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
If you have any questions regarding this matter, I may be reached at 301-415-3100.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 cc: Distribution via Listserv DISTRIBUTION:
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