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Results
Other: CNL-14-077, Responses to Degraded Voltage Issue Requests for Additional Information, ML102290358, ML102290360, ML102290361, ML102290362, ML102290363, ML102290364, ML102290365, ML102290366, ML102290367, ML102290368, ML102290383, ML102290384, ML102290385, ML102290386, ML102290387, ML102290388, ML102290389, ML102290390, ML102290391, ML102290392, ML102290403, ML102290404, ML102290405, ML102290406, ML102290407, ML102290408, ML102290409, ML102290410, ML102290411, ML102290414, ML102290439, ML102290440, ML102290441, ML102290442, ML102290443, ML102290444, ML102290445, ML102290446, ML102290447, ML102290448, ML102290458, ML102290459, ML102290460, ML102290461, ML102290462, ML102290463, ML102290464, ML102290465, ML102290466... further results
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MONTHYEARML1001916862010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97, Section 8 - Electric Power Through 8E-12 Project stage: Request ML1005500072010-03-11011 March 2010 Request for Additional Information Related to Licensee'S Final Safety Analysis Report Amendment 95 Related to Section 4.2.2, Reactor Vessel Internal Components Project stage: RAI ML1010405732010-04-0909 April 2010 Response to NRC Request for Additional Information Regarding Licensee'S Final Safety Analysis Report (FSAR) Amendment Related to Section 4.2.2, Reactor Vessel Internal Components. Project stage: Response to RAI ML1011303512010-05-0505 May 2010 Request for Withholding Information from Public Disclosure (Tac No. ME2731) Project stage: Withholding Request Acceptance ML1014500842010-06-23023 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Reactor Systems, Nuclear Performance and Code Review, Ansd Plant Systems Project stage: RAI ML1015402502010-06-24024 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review, Plant Systems, and Testing (Tac Nos. ME2731 and ME3091) Project stage: RAI ML1017903992010-06-28028 June 2010 Request for Additional Information (RAI) Regarding Licensee'S Final Safety Analysis Report Amendment Related to Section 4.2.2, Reactor Vessel Internal Components Project stage: Request ML1016200062010-06-29029 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review (Tac No. ME2731) Project stage: RAI ML1015304742010-07-0202 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Mechanical and Civil Engineering Systems Project stage: RAI ML1016000262010-07-0808 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report, Amendment Related to Quality and Vendor Branch Review Project stage: RAI ML1015303542010-07-12012 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Electrical Engineering Systems Project stage: RAI ML1018001562010-07-15015 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Chapter 8, Electric Power Project stage: RAI ML1023003272010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-4A (Dwg No. 1-47W845-5, R38) Project stage: Other ML1022904652010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-2 (Dwg No. 1-47W845-2, R76) Project stage: Other ML1023003282010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-4B (Dwg No. 1-47W845-7, R14) Project stage: Other ML1023003292010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-5 (Dwg No. 1-47W611-67-1, R8) Project stage: Other ML1023003302010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-6 (Dwg No. 1-47W611-67-2, R5) Project stage: Other ML1023003312010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-8 (Dwg No. 1-47W611-67-4, R5) Project stage: Other ML1023003322010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-9 (Dwg No. 1-47W611-67-5, R10) Project stage: Other ML1023003332010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-10 (Dwg No. 1-47W610-67-1, R27) Project stage: Other ML1023003342010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-10 Sh a (Dwg No. 1-47W610-67-1A, R16) Project stage: Other ML1023003352010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-11 (Dwg No. 1-47W610-67-2, R15) Project stage: Other ML1023003432010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-12 Sh a (Dwg No. 1-47W610-67-3A, R7) Project stage: Other ML1023003442010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-13 (Dwg No. 1-47W610-67-4, R17) Project stage: Other ML1023003452010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-11 Sh a (Dwg No. 1-47W610-67-2A, R8) Project stage: Other ML1023003462010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-12 (Dwg No. 1-47W610-67-3, R12) Project stage: Other ML1023003472010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5, R14) Project stage: Other ML1023003482010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5A, R2) Project stage: Other ML1023003492010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-16 (Dwg No. 1-47W859-4, R23) Project stage: Other ML1023003502010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-17 (Dwg No. 1-47W859-3, R18) Project stage: Other ML1023003512010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-18 (Dwg No. 1-47W859-2, R36) Project stage: Other ML1023003522010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-19 (Dwg No. 1-47W859-1, R47) Project stage: Other ML1023003602010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-23 (Dwg No. 1-47W611-70-1, R9) Project stage: Other ML1023003612010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-20 (Dwg No. 1-47W610-70-1, R23) Project stage: Other ML1023003622010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-21 (Dwg No. 1-47W610-70-2, R29) Project stage: Other ML1023003632010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-21A (Dwg No. 1-47W610-70-2A, R15) Project stage: Other ML1023003642010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-22 (Dwg No. 1-47W610-70-3, R17) Project stage: Other ML1023003652010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-24 (Dwg No. 1-47W611-70-2, R11) Project stage: Other ML1023003672010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-25 (Dwg No. 1-47W611-70-3, R4) Project stage: Other ML1023003682010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-25A (Dwg No. 1-47W611-70-4, R4) Project stage: Other ML1023003692010-08-0505 August 2010 Final Safety Analysis Report Figure 9.3-1 (Dwg No. 1-47W610-32-1, R15) Project stage: Other ML1022903652010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-7 (Dwg No. 1-45W760-211-9, R16) Project stage: Other ML1023003972010-08-0505 August 2010 Final Safety Analysis Report Figure 9.5-25A (Dwg No. 1-47W610-82-2, R7) Project stage: Other ML1023003982010-08-0505 August 2010 Final Safety Analysis Report Figure 9.5-25B (Dwg No. 1-47W610-82-3, R7) Project stage: Other ML1023003992010-08-0505 August 2010 Final Safety Analysis Report Figure 9.5-25C (Dwg No. 1-47W610-82-4, R7) Project stage: Other ML1022903682010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-14B (Dwg No. 1-45W760-82-1, R17) Project stage: Other ML1022903672010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-9 (Dwg No. 1-45W760-211-11, R13) Project stage: Other ML1022903662010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-8 (Dwg No. 1-45W760-211-10, R12) Project stage: Other ML1022903622010-08-0505 August 2010 Final Safety Analysis Report Figure 8.1-3 (Dwg No. 1-45W700-1, R28) Project stage: Other ML1022903582010-08-0505 August 2010 Final Safety Analysis Report Figure 8.1.2 (Dwg No. 1-15E500-1, R31) Project stage: Other 2010-06-28
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Category:Audit Report
MONTHYEARML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 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 ML21217A2222021-08-13013 August 2021 Regulatory Audit Summary Related to Request to Revise Technical Specifications to Change the Steam Generator Water Level ML18115A1382018-07-10010 July 2018 Staff Review of the Seismic Probabilistic Risk Assessment Associated with the Implementation of the Near-Term Task Force Recommendation 2.1: Seismic (CAC Nos. MF9879 and MF9880; EPID L-2017-JLD-0044 ML15345A4242015-12-23023 December 2015 Audit Report Related to License Amendment Request to Revise Technical Specification 4.2.1, Fuel Assemblies ML15334A1252015-12-23023 December 2015 Audit of the Licensee'S Management of Regulatory Commitments ML15294A2032015-10-30030 October 2015 NRC Report for the Audit of Tennessee Valley Authority'S Flood Hazard Reevaluation Report Submittals Relating to the Near-Term Task Force Recommendation 2.1-Flooding for Browns Ferry, Units 1,2 & 3, Sequoyah, Units 1 & 2, and Watts Bar, Uni ML14323A5622014-12-0303 December 2014 Report for the Audit Regarding Implementation of Licensing Preservation Program ML14211A3462014-08-18018 August 2014 Report for the Westinghouse Audit in Support of Reliable Spent Fuel Instrumentation Related to Order EA-12-051 ML14128A1292014-05-15015 May 2014 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML13343A0362013-12-20020 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13022A4012013-02-0707 February 2013 Audit of the Licensee'S Management of Regulatory Commitments ML1110306242011-04-27027 April 2011 Accident Analyses Audit Report Westinghouse Documents Relating to Final Safety Analysis Report Accident Analyses ML1034005992011-01-20020 January 2011 Commercial Grade Dedication of Hardware and Software Used in the Post Accident Monitoring System Audit Report ML0929300102009-10-21021 October 2009 Audit of the Licensee'S Management of Regulatory Commitments ML0621204692006-11-22022 November 2006 Plant Audit Report--Watts Bar Unit 1 Nuclear Plant New Sump Design in Response to Audit Report ML0615900812006-07-0303 July 2006 Letter, Audit of the Licensee'S Management of Regulatory Commitments ML0419101202004-07-0606 July 2004 LTR-04-0425 - Richard Schneider Ltr Final TVA Control Area Readiness Audit 2024-07-25
[Table view] 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) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter 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 IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 2024-09-05
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 20, 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 WADS BAR NUCLEAR PLANT. UNIT 2 -COMMERCIAL GRADE DEDICATION OF HARDWARE AND SOFTWARE USED IN THE POST-ACCIDENT MONITORING (PAMS) SYSTEM AUDIT REPORT (TAC NO. ME2731)
Dear Mr. Bhatnagar:
The U.S. Nuclear Regulatory Commission (NRC) staff performed an audit of the commercial grade dedication of the new or changed Common Q hardware and software to be used at the Watts Bar Nuclear Plant, Unit 2. The audit took place from September 20 to September 21, 2010 at Westinghouse's facility located in Windsor Locks. Connecticut.
Enclosed is the audit summary report prepared by the NRC staff. If you should have any questions, please contact me at 301-415-2048.
Sil}cere-ry. ,./..... Justin C. Poole, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Audit Summary cc w/encl: Distribution via ListseN REGULATORY AUDIT
SUMMARY
OF THE COMMERCIAL GRADE DEDICATION DOCUMENTATION OF THE NEW OR CHANGED COMMON Q HARDWARE AND SOFTWARE OF THE POST-ACCIDENT MONITORING SYSTEM USED AT WATTS BAR NUCLEAR PLANT, UNIT 2 BACKGROUND By letter dated December 5,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083440224), as supplemented by letter dated February 28,2009 (ADAMS Accession No. ML090570741), the Tennessee Valley Authority (TVA) requested the approval of the Common Q based Post Accident Monitoring System (PAMS). The audit followed the plan for the audit (ADAMS Accession No. ML102560386).
Individuals the staff interacted with included:
Steve Hilmes, TVA Gregory A. Gisoni, Westinghouse (WEC) Andrew P. Drake, WEC Mark J. Stofko, WEC Allen C. Denyer, WEC Stanley E. Dlugolenski Jr., WEC Richard M. Manazir Jr., WEC Stephen L. Packard, WEC Martin P. Ryan, WEC Harold T. Maquire Jr., WEC Mesut B. Uzman, WEC Murat S. Uzman, WEC Matthew A. Shakun, WEC Shawn Downey, WEC (Part time) Warren R. Odess-Gillett, WEC (Part time) Andrew Konzel, WEC (Part time) Arthur J. Trozzi, WEC (Part time) AUDIT
SUMMARY
This audit was conducted in accordance with the regulatory basis identified in the audit plan. As described in the audit plan, the following audit focus areas were covered 1. Commercial Grade Dedication Information of the New or Changed Hardware 2. Commercial Grade Dedication Information of the New or Changed Software 3. Reusable Software Elements Summaries of the specific audit activities and conclusions follow, categorized by their focus area. These were briefly described at the exit briefing.
ENCLOSURE
-2 1. Commercial Grade Dedication Information of the New or Changed Hardware:
The Nuclear Regulatory Commission (NRC) staff traced a few generic critical characteristics through the generic hardware commercial grade dedication documentation.
It was determined that Westinghouse has a detailed, thorough, and proprietary process that is difficult to explain. It was also determined that the amount of material that would need to be docketed to support such an explanation would not be consistent with the safety significance of the PAMS application in Watts Bar Nuclear Plant, Unit 2 (WBN2). The NRC determined that it would not be appropriate to approve the generic commercial grade dedication process as part of this project. The NRC determined that Westinghouse did not have documentation of how the WBN2 critical characteristics were explicitly addressed by the generic components.
The NRC staff requested that TVAlWestinghouse perform an evaluation that the WBN2 requirements on the commercial hardware are enveloped by the generic qualification of that hardware (e.g., see last paragraph of Electric Power Research Institute (EPRI) technical report (TR)-1 07330 Section 1.1, "Background").
- 2. Commercial Grade Dedication Information of the New or Changed Software:
The staff traced a few of generic critical characteristics through the generic software commercial grade dedication documentation.
It was determined that Westinghouse has a detailed, thorough, and proprietary process that is difficult to explain. It was also determined that the amount of material that would need to be docketed to support such an explanation would not be consistent with the safety significance of the PAMS application in WBN2. The NRC determined that it would not be appropriate to approve the generic commercial grade dedication process as part of this project. The NRC also determine'd that Westinghouse did not have documentation of how the WBN2 critical characteristics were explicitly addressed by the generic components.
The NRC staff requested that TVAlWestinghouse perform an evaluation that the WBN2 requirements on the commercial software are enveloped by the generic qualification of that software (e.g., see last paragraph of EPRI TR-107330 Section 1.1, "Background").
- 3. Reusable Software Elements:
The functions that are described in abstract terms (i.e., reactor vessel level indication are designed and implemented by a set of generic modules (i.e., Reusable Software There has been no information docketed that describes the development of these The NRC staff traced a requirement from the PAMS system requirements specification to reusable software element documents (RSEDs) and finally to the associated verification validation (V&V) test The staff will need to make a determination of whether these RSED's can be audited as confirmatory measure to ensure that the process for developing them is being implemented or if the RSED's themselves need to be docketed and reviewed.
Furthermore, staff must determine if the RSED's should be reviewed at the generic platform level or at application level licensing review
-3Review of Commercial Grade Dedication Documents for the Upcoming Common Q Platform Safety Evaluation:
A discussion of the upcoming Common Q platform licensing topical report update review was held. A preliminary agreement was reached on the required documentation to support the commercial dedication activities related to the changes made to the platform.
For new assemblies, the initial commercial dedication reports will be docketed and for product updates, the dedication reports for the changes made will be docketed and reviewed.
This approach is consistent with the documentation that was required for the initial TR safety evaluation.
OPEN ITEMSI CLOSURE PATHS: TVAIWestinghouse agreed to include a description of their generic hardware commercial grade dedication process in the PAMS licensing technical report. (Open Item No. 138 of the Instrumentation and Control Open Item List) TVAIWestinghouse agreed to include (in the PAMS licensing technical report) an evaluation of WBN2 critical characteristics for commercial hardware components against the generic critical characteristics. (Open Item No. 138) TVAIWestinghouse agreed to include a description of their generic software commercial grade dedication process in the PAMS licensing technical report. (Open Item No. 138) TVAIWestinghouse agreed to include (in the PAMS licensing technical report) an evaluation of WBN2 critical characteristics for commercial software components against the generic critical characteristics. (Open Item No. 138) TVAIWestinghouse agreed to include the V&V evaluation of their reusable software element development process in the V&V design phase summary report. This evaluation would include an evaluation against the development process requirements.
This evaluation would also include an evaluation of how the WBN2 specific requirements were addressed by the reusable software elements. (Open Item No. 142) It was acknowledged that TVAIWestinghouse had previously (in September 15,2010, public meeting) stated that they would provide the RSED requirements traceability matrix (RTM). (Open Item No. 145) It was acknowledged that TVAIWestinghouse had previously (in September 15, 2010, public meeting) stated that they would revise and resubmit the PAMS RTM to address all types of issues identified in the public meeting. (Open Item No. 145) It was acknowledged that TVAIWestinghouse had previously (in September 15,2010, public meeting) stated that they would revise and resubmit the Software Verification and Validation phase summary report for the requirements phase to document the completion of the requirements phase review. (Open Item No. 145)
January 20, 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 WATTS BAR NUCLEAR PLANT, UNIT 2 -COMMERCIAL GRADE DEDICATION OF HARDWARE AND SOFTWARE USED IN THE POST-ACCIDENT MONITORING (PAMS) SYSTEM AUDIT REPORT (TAC NO. IV1E2731)
Dear Mr. Bhatnagar:
The U.S. Nuclear Regulatory Commission (NRC) staff performed an audit of the commercial grade dedication of the new or changed Common Q hardware and software to be used at the Watts Bar Nuclear Plant, Unit 2. The audit took place from September 20 to September 21, 2010 at Westinghouse's facility located in Windsor Locks, Connecticut.
Enclosed is the audit summary report prepared by the NRC staff. If you should have any questions, please contact me at 301-415-2048.
Sincerely, IRA! Justin C. Poole, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Audit Summary cc w/encl: Distribution via Listserv DISTRIBUTION:
RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsNrrDeEicb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource NCarte, NRR ADAIV1S Accession No. ML103400599
- via memo OFFICE LPWB/PM LPWB/LA EICB/BC LPWB/BC I\IAME JPoole BClayton WKemper* SCampbel1 DATE 1/18/11 1/6/11 10/25/10 1/20/11 OFFICIAL AGENCY