Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML1009500442010-04-0101 April 2010 Supplemental Information Regarding Certain NRC Generic Letters and Bulletins Project stage: Request ML1019605022010-07-29029 July 2010 RAI, Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves Project stage: RAI ML1021401912010-07-30030 July 2010 Response to Request for Additional Information Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves Project stage: Response to RAI ML1001904432010-08-12012 August 2010 Safety Evaluation Regarding Generic Letter 1995-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves Project stage: Approval 2010-07-29
[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) 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) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection 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 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO 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-24-024, 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-010, 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-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status 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-24-029, 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 2024-09-05
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 July 30, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant (WBN) Unit 2 - Response to Request for Additional Information Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves (TAC No. MD6717)
References:
- 1. NRC letter to TVA, Watts Bar Nuclear Plant, Unit 2 - Request for Additional Information Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves (TAC No.
MD6717), dated July 29, 2010
- 2. TVA letter to NRC, Watts Bar Nuclear Plant (WBN) - Unit 2 - Initial Responses to Bulletins and Generic Letters, dated September 7, 2007 [ML072570676]
- 3. TVA letter to NRC, Watts Bar Nuclear Plant (WBN) Unit 2 -
Supplemental Information Regarding Certain NRC Generic Letters and Bulletins, dated April 1, 2010 [ML100950044]
The purpose of this letter is to submit the Tennessee Valley Authority (TVA) response to U.S. Nuclear Regulatory Commission (NRC) request for additional information (RAI) regarding pressure locking and thermal binding of safety-related power-operated gate valves (Reference 1).
In a letter dated September 7, 2007 (Reference 2), TVA submitted initial information to the NRC regarding pressure locking and thermal binding of safety-related power-operated gate valves as related to Generic Letter 1995-07 for WBN Unit 2.
Supplemental information was submitted April 1, 2010 (Reference 3).
u.s. Nuclear Regulatory Commission Page 2 July 30, 2010 to this letter lists the individual questions posed by the NRC and TVA responses to those questions. Enclosure 2 identifies those actions committed to by TVA in this letter. If you have any questions, please contact William Crouch at (423) 365-2004.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 30th day of July 2010.
Sincerely,
Enclosures:
- 1. Response to NRC Request for Additional Information Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
- 2. List of Regulatory Commitments cc (Enclosures):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
Enclosure 1 Response to NRC Request for Additional Information Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves Tennessee Valley Authority Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391
- 1. NRC Request Which valves related to GL 1995-07 require modifications? Please provide a list of these valves.
TVA Response The 95-07 review of WBN Unit 2 Generic Letter (GL) 89-10 motor operated valves (MOVs) has been completed with the following conclusions:
Eleven Valves Identified for Disk Modification
- 1. 2-FCV-1-16
- 2. 2-FCV-63-8
- 3. 2-FCV-63-11
- 4. 2-FCV-63-156
- 5. 2-FCV-63-157
- 6. 2-FCV-74-1
- 7. 2-FCV-74-2
- 8. 2-FCV-74-8
- 9. 2-FCV-74-9
- 10. 2-FCV-74-33
- 11. 2-FCV-74-35 Seven Valves Identified for Valve Bonnet Modification
- 1. 2-FCV-63-72
- 2. 2-FCV-63-73
- 3. 2-FCV-63-172
- 4. 2-FCV-72-40
- 5. 2-FCV-72-41
- 6. 2-FCV-72-44
- 7. 2-FCV-72-45 E1-1
Enclosure 1 Response to NRC Request for Additional Information Regarding Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves Additionally, controls for Valves 2-FCV-72-2 (EDCR 53292) and -39 (EDCR 53287) will be modified to add a time delay which will eliminate the potential for pressure locking, as is done with Unit 1 Valves 1-FCV-72-2 and -39. Note that this is a controls mod and not a valve modification. EDCRs 53292 and 53287 shall be implemented to eliminate the potential for pressure locking prior to startup.
- 2. NRC Request Which valves are missing from the list of valves related to GL 1995-07? Please provide a list of the missing valves.
TVA Response TVA has confirmed that none of the missing 89-10 valves from TVAs April 1, 2010, letter (Reference 3) are 95-07 valves. There are no missing GL 95-07 valves. The 20 valves identified above are currently installed in WBN Unit 2.
- 3. NRC Request Have there been any plant modifications that changed the original GL 1995-07 assessment for WBN Unit 1? If so, what is the impact of these modifications on WBN Unit 2?
TVA Response In addition to the time delay changes mentioned above, there are 2 other Unit 1 valves, 1-FCV-63-25 and -26, which are being evaluated for GL 95-07 impacts to address new input parameters from the Joint Owners Group (JOG) Topical Report MPR 2524A. Unit 1 has initiated a design change to address JOG pressure locking and MOV requirements. Valves 2-FCV-63-25 and -26 will be evaluated for impact due to new parameters from the JOG Topical Report MPR 2524A prior to startup.
E1-2
Enclosure 2 List of Regulatory Commitments Tennessee Valley Authority Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391 Commitment Committed Date EDCRs 53292 and 53287 shall be implemented to eliminate the Prior to potential for pressure locking prior to startup. Startup Valves 2-FCV-63-25 and -26 will be evaluated for impact due to Prior to new parameters from the JOG Topical Report MPR 2524A prior to Startup startup.
E2-1