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Category:Audit Report
MONTHYEARML21217A2222021-08-13013 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 2021-08-13
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 21, 2009 Mr. Ashok Bhatnagar Senior Vice President Nuclear Generation Development and Construction 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - AUDIT OF THE LICENSEE'S MANAGEMENT OF REGULATORY COMMITMENTS (TAC NO. ME2291)
Dear Mr. Bhatnagar:
In Regulatory Issue Summary 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC [U. S. Nuclear Regulatory Commission] Staff," dated September 21, 2000, the NRC informed licensees that the Nuclear Energy Institute (NEI) document NEI 99-04, "Guidelines for Managing NRC Commitment Changes," contains acceptable guidance for controlling regulatory commitments and encourages licensees to use the NEI guidance or similar administrative controls to ensure that regulatory commitments are implemented and that changes to the regulatory commitments are evaluated and, when appropriate, reported to the NRC.
The NRC Office of Nuclear Reactor Regulation has instructed its staff to perform an audit of licensees' commitment management programs once every 3 years to determine whether the licensees' programs are consistent with the industry guidance in NEI 99-04, and that regulatory commitments are being effectively implemented.
An audit of Watts Bar's commitment management program was performed at the Watts Bar site during the period October 5 - 7, 2009. The NRC staff concludes, based on the audit, that (1) Watts Bar has implemented NRC commitments on a timely basis, and (2) has generally implemented an effective program for managing NRC commitment changes. Details of the audit are set forth in the enclosed audit report.
One example was found where the NRC was not notified of an implementation date change for a commitment to a Bulletin. When pointed out to your staff, a Problem Evaluation Report was issued.
A. Bhatnagar -2 The !\IRC staff has no additional questions regarding this example.
Sincerely, oel S. Wiebe, Senior Project Manager atts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391
Enclosure:
Audit Report cc w/encl: Distribution via Listserv
AUDIT REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION LICENSEE MANAGEMENT OF REGULATORY COMMITMENTS WADS BAR NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-390 AND 50-391
1.0 INTRODUCTION AND BACKGROUND
In Regulatory Issue Summary 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC [U. S. Nuclear Regulatory Commission] Staff," dated September 21, 2000, the NRC informed licensees that the Nuclear Energy Institute (NEI) document NEI 99-04, "Guidelines for Managing NRC Commitment Changes," contains acceptable guidance for controlling regulatory commitments and encourages licensees to use the NEI guidance or similar administrative controls to ensure that regulatory commitments are implemented and that changes to the regulatory commitments are evaluated and, when appropriate, reported to the NRC.
The NRC Office of Nuclear Reactor Regulation (NRR) has instructed its staff to perform an audit of licensees' commitment management programs once every 3 years to determine whether the licensees' programs are consistent with the industry guidance in NEI 99-04, and that regulatory commitments are being effectively implemented.
NEI-99-04 defines a regulatory commitment as an explicit statement to take a specific action agreed to, or volunteered by, a licensee and submitted in writing on the docket to the NRC.
NRR guidelines direct the NRR Project Manager to audit the licensee's commitment management program by assessing the adequacy of the licensee's implementation of a sample of commitments made to the NRC in past licensing actions (amendments, reliefs, exemptions, etc.) and activities (bulletins, generic letters, etc.). The audit is to be performed every 3 years.
2.0 AUDIT PROCEDURE AND RESULTS An audit of the Watts Bar commitment management program was performed at the Watts Bar plant site during the period October 5 - 7, 2009. The audit reviewed commitments made since the previous audit on in May 2006. The previous audit only considered Unit 1 commitments.
The audit consisted of two major parts: (1) verification of the licensee's implementation of NRC commitments that have been completed and (2) verification of the licensee's program for managing changes to NRC commitments.
Enclosure
-2 2.1 Verification of Licensee's Implementation of NRC Commitments The primary focus of this part of the audit is to confirm that the licensee has implemented commitments made to the NRC as part of past licensing actions/activities. For commitments not yet implemented, the NRC staff determines whether they have been captured in an effective program for future implementation.
2.1.1 Audit Scope The audit addressed a sample of commitments made during the review period. It focused on regulatory commitments (as defined above) made in writing to the NRC as a result of past licensing actions (amendments, exemptions, etc.) or licensing activities (bulletins, generic letters, etc.). Commitments made in Licensee Event Reports or in response to Notices of Violation may be included in the sample, but the review will be limited to verification of restoration of compliance, not the specific methods used. Before the audit, the NRC staff searched the Agencywide Documents Access and Management System for the licensee's submittals since the last audit and selected a representative sample for verification.
The audit excluded the following types of commitments that are internal to licensee processes:
(1) Commitments made on the licensee's own initiative among internal organizational components.
(2) Commitments that pertain to milestones of licensing actions/activities (e.g.,
respond to an NRC request for additional information by a certain date).
Fulfillment of these commitments was indicated by the fact that the subject licensing action/activity was completed.
(3) Commitments made as an internal reminder to take actions to comply with existing regulatory requirements such as regulations, Technical Specifications, and Updated Final Safety Analysis Reports. Fulfillment of these commitments was indicated by the licensee having taken timely action in accordance with the subject requirements.
2.1.2 Audit Results The attached Audit Summary provides details of the audit and its results. The NRC staff sampled 11 commitments and all sampled commitments were identified in the licensee's commitment tracking system.
2.2 Verification of the Licensee's Program for Managing NRC Commitment Changes The primary focus of this part of the audit is to verify that the licensee has established administrative controls for modifying or deleting commitments made to the NRC. The NRC staff compared the licensee's process for controlling regulatory commitments to the guidelines in NEI-99-04, which the NRC has found to be an acceptable gUide for licensees to follow for managing and changing commitments. The process used at Watts Bar is contained in Standard Programs and Processes (SPP) 3.3, "NRC Commitment Management." The audit reviewed a sample of commitment changes that included changes that were or will be reported to the NRC,
-3 and changes that were not or will not be reported to the NRC. The audit also verifies that the licensee's commitment management system includes a mechanism to ensure traceability of commitments following initial implementation. This ensures that licensee personnel are able to recognize that future proposed changes to the affected design features or operating practices require evaluation in accordance with the commitment change control process.
2.2.1 Audit Results The attached Audit Summary also provides details of this portion of the audit and its results.
The NRC staff found one example where the NRC was not notified of an implementation date change for a commitment to a Bulletin. When pointed out to your staff, a Problem Evaluation Report was issued. The NRC staff has no additional questions regarding this example. The NRC staff found that SPP-3.3 requirements are consistent with the guidance contained in NEI99-04.
3.0 CONCLUSION
The NRC staff concludes, based on the above audit, that (1) Watts Bar has implemented NRC commitments on a timely basis, and (2) has generally implemented an effective program for managing NRC commitment changes.
4.0 LICENSEE PERSONNEL CONTACTED FOR THIS AUDIT Tom Metzler Gordon Arent Principal Contributors: Joel Wiebe and Justin Heinley
Attachment:
Summary of Audit Results
AUDIT
SUMMARY
IMPLEMENTATION OF COMMITMENTS:
The following commitments were reviewed:
Licensee ADAMS Description Comments No. Reference Unit2 TVA has performed calculations of the safety NCO None Inspection significance evaluation that determined that 0870125013 Report complete penetration welds are not required for Indicated any of the welded ductwork installed. However, Commitment TVA has revised design drawings and other was closed.
applicable documents to require full penetration welds for all future installations. ML072610417 Change safety valve internals from water to NCO None Commitment steam. 850386002 remains open.
Nuclear Engineering Procedure NEP-3.3, NCO None Inspection "Internal Interface Control," issued to provide 870125032 Report improved interface control among design Indicated organizations. NEP-3.3 should provide improved interface control.
ML072530692 Unit 1 The UFSAR will be revised to require the NCO ML061310178 Withdrawn by Emergency Diesel Generator jacket water heat 060012001 letter to NRC exchangers to be cleaned once each spring. dated July 20, 2007.
TVA will perform a self-assessment on Access NCO ML080440412 None.
Authorization and adherence to Behavior 10092575 Commitment Observation Program by the end of the 4 th rescheduled quarter of 2008. without informing NRC.
Problem Evaluation Report (PER) 203941 Issued.
A modification is planned to replace the affected NCO ML062190296 Closed to cables with cables that minimize the 060018001 LER 2006-007 temperature induced current phenomenon.
Attachment
-2 Licensee ADAMS Description Comments No. Reference Volumetric examinations of WBN Unit 1 NCO ML070660025 Verified that unmitigated pressurizer Alloy 600/82/182 butt 070006001 examinations welds will be performed at a frequency of no are scheduled.
more than 4 years between exams until the welds have been mitigated. Action #NCO 070006001-1 Details of the volumetric examination results NCO ML070660025 Verified that including any corrective or mitigative actions 070010001 results were taken for each unmitigated weld examined will reported as be reported to the NRC within 60 days of WBN required by Unit 1 restart. letter to the NRC dated February 27, 2007.
The actions to replace the Min-K insulation and NCO ML072150109 Verified add additional restraint bands will be completed 070015001 completed by during the Unit 1 Cycle 8 Outage. review of completed design change request.
DCN 52226-A Sequoyah and Watts Bar will revise the back-up NCO ML070670149 Verified generator procedure(s) to include supplying one 070008001 completed by train of containment hydrogen igniters per unit, review of and train personnel to the procedure revision, by procedure December 31, 2007. MA-1 Revison 3 and training materials 3-0T-B5b.
TVA intends to perform preliminary evaluations NCO ML081360101 Verified by October 11, 2008. These evaluations may 080023001 completed by identify confirmatory walkdowns that are best review of letter performed during prolonged outages. to NRC dated October 11, 2008.
MANAGEMENT OF CHANGES TO REGULATORY COMMITMENTS:
During the audit, it was noted that the commitment to perform a self-assessment on Access Authorization and adherence to Behavior Observation Program by the end of the 4 th quarter of 2008 was not performed as committed. The licensee had identified the failure to implement the commitment and had documented the failure with Problem Evaluation Report 159953. The auditor informed the licensee that procedure SPP-3.3 was not followed in that the NRC was not
-3 informed of the rescheduled commitment. The licensee documented the failure to inform the NRC in a Problem Evaluation Report. The NRC staff has no further questions regarding this item.
A. Bhatnager -2 The NRC staff has no additional questions regarding this example.
Sincerely, IRAI Joel S. Wiebe, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391
Enclosure:
Audit Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LP-WB Reading File RidsNrrDorlLpwb RidsNrrPMWattsBar1 RidsNrrPMWattsBar2 RidsNrrLABClayton RidsAcrsAcrnw_MailCenter RidsRgn2MailCenter (RHaag, EGuthrie) RidsOgcRp JHeinly ADAMS ACCESSION* ML092930010 ,
OFFICE LP-WB/PM LP-WB/PM LP-WB/LA LP-WB/BC NAME JWiebe JHeinley BClayton LRaghavan DATE 10/20109 10/20109 10/20109 10/21 109 OFFICIAL RECORD COpy