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MONTHYEARML0402104582004-01-16016 January 2004 TVA Nuclear Quality Assurance (Nqa) Plan - Response to NRC Request for Additional Information Dated October 14, 2003 Project stage: Response to RAI ML16158A4302016-06-0606 June 2016 Notice of Intent to Apply the Previously Approved Quality Assurance Plan to Spent Fuel Storage Activities, and to Store Spent Fuel at an Independent Spent Fuel Storage Installation (ISFSI) Project stage: Other 2004-01-16
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Category:Letter
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - 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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 January 16, 2004 10 CFR 50.55(f) (3)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of Docket Nos. 50-391 Tennessee Valley Authority ) 50 -438 50-439 TVA NUCLEAR QUALITY ASSURANCE (NQA) PLAN (TVA-NQA-PLN89-A) - NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) DATED OCTOBER 14, 2003 (TAC NOS. MC0678, MC0683, AND MC0684)
The purpose of this letter is to respond to NRC's RAI regarding TVA's proposed changes to the NQA Plan submitted on August 28, 2003.
The enclosure restates NRC's questions and provides TVA's responses.
There are no regulatory commitments in this submittal. If you have questions, please contact R. M. Brown at (423) 751-7228.
Sincerely, 1f 1 Mark skiur L'
Manager Nuclear Licensing Enclosure cc: See page 2 Pnmed on o.mcWld pae
U.S. Nuclear Regulatory Commission Page 2 January 16, 2004 cc (Enclosure):
Mr. Stephen J. Cahill, Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Ms. Margaret H. Chernoff, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Senior Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION Request for Information TVA proposes the addition of a new Appendix F to the NQAP which states that deferred plant equipment may be abandoned in place.
The U.S. Nuclear Regulatory Commission's policy statement on deferred plants was published in the Federal Register (52 FR 38077) on October 14, 1987. Holders of construction permits for nuclear power plants were alerted of the policy through Generic Letter 87-015, which calls particular attention to quality assurance requirements for maintenance, preservation and documentation.
Please describe how your position on deferred plant equipment, described in the proposed new Appendix F to the NQAP, is consistent with the Commission's policy.
Response
TVA's proposed NQA Plan change will allow TVA some flexibility to discontinue maintenance, preservation, and documentation (MPD) activities for certain structures, systems, and components (SSC) where such maintenance is no longer practical or feasible. For those SSC which TVA continues to conduct MPD activities, the MPD requirements will be maintained under the terms of the current NQA Plan.
This approach is entirely consistent with the requirements of Generic Letter 87-15. Implicit in the Commission's Policy Statement on Deferred Plants is the notion that those SSC being protected under the policy actually be in place and relied upon at the time the plant is eventually reactivated and put into operation. This is, in fact, more than an implicit understanding. In response to a commenter on the policy statement regarding SSC which are safety-related vs. important to safety, the NRC stated, "In the context of this policy statement, it is expected that a utility, planning to maintain its reactivation option or transfer of ownership to others, will identify any structures, systems, and components (SSC) which are important to safety and establish appropriate maintenance, preservation, and documentation (MPD) for these SSC. If a utility determines, based on an analyses of cost effectiveness, to develop MPD only for safety-related SSC, it must recognize a possibility that SSC for which appropriate MPD were not developed may have to be replaced if and when reactivation or transfer of ownership takes place." (52 Fed. Reg.
38077 [October 14, 1987]) In TVA's case, we have made certain determinations, and may make future determinations, that it would be I
- w . -
- more economical to replace or possibly restore certain SSC following testing by repair or corrective maintenance than to continue pointless MPD activities. NRC's policy should not be interpreted in a manner that would require utilities to develop and maintain MPD for SSC which may be removed, never be used, and must be replaced anyway. Though TVA's ratepayers understand and bear the increased costs associated with high-level QA requirements because of the important degree of assurance they provide, it would be very difficult to defend the expenditure of these high costs to maintain SSC which TVA determines will never be used or may be able to be eventually refurbished, tested, and fully qualified for later use at a much lower cost. QA requirements for MPD are and will continue to be maintained for "active" SSC and the lay-up and NQA Plan requirements will not change.
Request for Information Further, describe your process for tracking and documenting the status of deferred plant equipment pending reactivation of construction activities.
Response
Under the proposed lay-up program, TVA would have the ability to characterize SSC as either active or inactive. SSC would be identified, recorded, and its status tracked by the following methods:
Watts Bar Unit 2 Active/Inactive items would be shown in a data field in a QA verified database.
Bellefonte Units 1 and 2 Active/Inactive items would be shown in a data field on a QA record that is generated to document preventative maintenance.
These records would be verified by a controlled process consistent with data use requirements of NQA Plan, Section 13.0, and Appendix E. Based on these requirements, the related software is not required to be quality-related because the data is further verified by a controlled QA records process before issuance of records.
In both situations, QA data would be readily available to indicate equipment status for eventual construction.
For those SSC classified as active, the QA requirements for MPD would continue to be maintained. MPD activities would cease for SSC classified as inactive. Upon resumption of construction activities or should the particular SSC be considered for reinstallation in an operating unit, TVA may consider the viability of restoring the SSC by evaluating and/or testing it as required in order to prove that it has not become degraded and that it can perform its intended function.
Any inactive SSC which cannot be adequately restored to adequately perform its intended function would be replaced or removed by the design change process.
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