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Category:Inspection Report
MONTHYEARIR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 IR 05000259/20234022023-06-12012 June 2023 Material Control and Accounting Program Inspection Report 05000259 2023402, 05000260 2023402 and 05000296 2023402 IR 05000259/20230912023-05-0808 May 2023 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter; NRC Inspection Report 05000259/2023091 IR 05000259/20230012023-05-0303 May 2023 Integrated Inspection Report 05000259/2023001, 05000260/2023001 and 05000296/2023001 IR 05000259/20234402023-03-23023 March 2023 Special Inspection Supplemental Report 05000259 2023440 and 05000260 2023440 and 05000296 2023440 Cover Letter IR 05000259/20234012023-03-0808 March 2023 Security Baseline Inspection Report 05000259 2023401 and 05000260/2023401 and 05000296/2023401 IR 05000259/20230902023-03-0202 March 2023 NRC Inspection Report 05000259/2023090 and 05000260 2023090 and Preliminary White Finding and Apparent Violation IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 IR 05000259/20220042023-02-0707 February 2023 Integrated Inspection Report 05000259/2022004, 05000260/2022004 and 05000296/2022004 IR 05000259/20220032022-11-0909 November 2022 Browns Perry Nuclear Plant - Integrated Inspection Report 05000259/2022003, 05000260/2022003 and 05000296/2022003 IR 05000259/20220122022-09-20020 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000259 2022012, 05000260 2022012 and 05000296 2022012 IR 05000259/20220112022-09-16016 September 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000259/2022011 and 05000260/2022011 and 05000296/2022011 IR 05000259/20224022022-09-0606 September 2022 Security Baseline Inspection Report 05000259/2022402 and 05000260/2022402 and 05000296/2022402 Cover Letter IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 IR 05000259/20220022022-08-0808 August 2022 Integrated Inspection Report 05000259/2022002, 05000260/2022002 and 05000296/2022002 IR 05000259/20224202022-07-19019 July 2022 Security Baseline Inspection Report 05000259/2022420, 05000260/2022420 and 05000296/2022420 ML22181A9562022-06-29029 June 2022 Bf Report 2022-401 Base Public Cover Letter ML22173A1622022-06-21021 June 2022 Replacement Steam Dryer Visual Inspection Results (U3R20) IR 05000259/20220012022-05-12012 May 2022 Integrated Inspection Report 05000259/2022001, 05000260/2022001, 05000296/2022001 and Exercise of Enforcement Discretion IR 05000259/20220102022-03-30030 March 2022 Triennial Fire Protection Inspection Report 05000259/2022010 and 05000260/2022010 and 05000296/2022010 and Apparent Violation IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 IR 05000259/20210042022-01-31031 January 2022 Integrated Inspection Report 05000259/2021004, 05000260/2021004 and 05000296/2021004 IR 05000259/20214032022-01-19019 January 2022 NRC Inspection Report 05000259/2021403, 05000260/2021403 and 05000296/2021403 IR 05000259/20214022022-01-18018 January 2022 Brows Ferry Nuclear Plant - Security Baseline Inspection Report 05000259/2021402 and 05000260/2021402 and 05000296/2021402 IR 05000259/20210032021-11-0909 November 2021 Integrated Inspection Report 05000259/2021003, 05000260/2021003, 05000296/2021003 and 07200052/2021001 IR 05000259/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000259/2021401 and 05000260/2021401 and 05000296/2021401 IR 05000259/20210112021-08-24024 August 2021 Temporary Instruction 2515/TI-193 Inspection Report 05000259/2021011, 05000260/2021011, and 05000296/2021011 IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 ML21217A2832021-08-0505 August 2021 Resident Integrated Inspection Report 2021-002 IR 05000259/20213012021-07-28028 July 2021 NRC Operator License Examination Report Nos. 05000259/2021301, 05000260/2021301, 05000296/2021301 IR 05000259/20210102021-07-26026 July 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010 IR 05000259/20204012021-05-26026 May 2021 Security Baseline Inspection Report 05000259/2020401 and 05000260/2020401 and 05000296/2020401(U) IR 05000259/20210012021-04-28028 April 2021 Integrated Inspection Report 05000259/2021001, 05000260/2021001 and 05000296/2021001 IR 05000259/20200062021-03-0303 March 2021 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006 IR 05000259/20200042021-01-28028 January 2021 Integrated Inspection Report 05000259/2020004, 05000260/2020004, 05000296/2020004, 07200052/2020002 and Exercise of Enforcement Discretion IR 05000259/20204022021-01-0808 January 2021 Material Control and Accounting Program Inspection Report 05000259/2020402, 05000260/2020402 and 05000296/2020402 IR 05000259/20200032020-11-10010 November 2020 Integrated Inspection Report 05000259/2020003, 05000260/2020003 and 05000296/2020003 IR 05000254/20200032020-11-0909 November 2020 Integrated Inspection Report 05000254/2020003; 05000265/2020003 and 07200053/2020001 IR 05000259/20200112020-10-26026 October 2020 Biennial Problem Identification and Resolution Inspection Report 05000259/2020011, 05000260/2020011 and 05000296/2020011 IR 05000259/20204042020-09-29029 September 2020 NRC Security Inspection Report 05000259/2020404 and 05000260/2020404 and 05000296/2020404 and Apparent Violation (U) IR 05000259/20200052020-08-18018 August 2020 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005 IR 05000259/20200022020-08-0606 August 2020 Brown Ferry Nuclear Plant Integrated Inspection Report 05000259/2020002, 05000260/2020002, 05000296/2020002, and 07200052/2020001 IR 05000259/20200102020-06-19019 June 2020 Triennial Inspection of Evaluation of Changes, Test and Experiments Baseline Inspection Report 0500259/2020010 and 05000260/2020010 and 05000296/2020010 IR 05000259/20200012020-05-0707 May 2020 Integrated Inspection Report 05000259/2020001, 05000260/2020001, and 05000296/2020001 2023-08-29
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions 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 ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 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 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 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 ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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5DV r aP: " i i lit TENNESSEE YALLEY AUTHOR1TY CHAT-.ANOOoA TEr'r csSEE 374o'r Ps.ip'" Au/us['.!r.Nor;san C.Noseley, Director Cffice of Inspection and'nforcement l:.5.".uclear Pegulatory Commission Region ll-Suite Bl8 230 Pcachtree Street,?~1i.Atlanta;Georgia 30303 P t
Dear?fr,
?koseley: 'This is in response to F.J.l.ong's August 5,)976, letter, XF.:Xi:RFS 50-259/76-17, 50-260/76-37,~hicir f.ransLitte6 for our rcviev an lP.Inspection Reporr..(same nu>rber).'Re have revie~ea that report and do not consider on)part of it to be proprietary.
Very ugly you)s, r 1-J~.e-~D.i.Gi llelana/Assistant Hanager of Power
~O 4~V<P,R 8800 P 0':y+0 00 In Reply Refer To: IE: II:RFS 50-259/76-17 50-260/76-17 UNITED STATES NUCLEAR'EGULATORY COMMISSION REGION II 830 PEACHTREK STREET, N'SUITE 818 ATLANTA, GEORGIA 30303 AUG Tennessee Ualley Authority ATTN: Mr.Godwin Williams, Jr.Manager of Power 830 Power Building Chattanooga, Tennessee 37401 Gentlemen:
This refers to the inspection conducted by Messrs.F., S.Cantrell and R.F.Sullivan of, this office on July 7-9 and 20-21, 1976, of activities authorized by NRC Operating License Nos.DPR-33 and DPR-52 for the Browns Ferry Units 1 and 2'acilities,.
and to the discussion of our findings held with Mr.H.J.Green at the conclusion of the inspection.
Areas examined during the inspection and our findings are'discussed in the enclosed inspection, report.Within these areas, the inspection consisted of-selective examination of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no items.of noncompliance were disclosed.
An infraction identified through your internal audit program is shown in the details of the enclosed inspection report.The appropriate report was made and corrective action initiated or completed and no additional information, is needed for this.item at this time.In accordance with Section 2.790 of the NRC's"Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in'the NRC's Public Docu-ment Room.If this report contains, any information that you believe to be proprietary, it is necessary that you submit a written application to this office requesting that such information be withheld from public disclosure.
If'no proprietary information is identified, a written statement to that effect should be submitted.
If an application is submitted, it must fully identify the bases for, which information is claimed to be proprietary.
The application should be prepared so that information sought to be withheld is incorporated in a separate paper Tennessee Valley Authority and referenced in the application since the application will be placed in the Public Document Room.Your application,, or written statement, should be submitted to us within 20 days.If we are not contacted as specified, the enclosed report and this letter may then be placed in the Public Document Room.Should you have any questions concerning this letter, we will be glad.to discuss them with you.Very.truly yours, F.J.,Long, Chief Reactor Operations and Nuclear Support Branch Enclosure:
IE Inspection Report Nos.50-259/76-17.and 50-260/76-17 l~g~'
~I i~>
~4~P,4 4~0u.(4 P O Cy O+ip+O W~*y4 UNITED.STATES NUCLEAR REGULATORY COMMISSION REGION II 330 PEACHTREE'STREET, N.W.SUITE 8I8 ATLANTA, GEORGIA 30303 IE Inspection Report Nos.50-259/76-17 and 50-260/76-17 Licensee: Tennessee Valley Authority 830 Power Building Chattanooga, Tennessee 37401 Facility Name: Browns Ferry 1 and 2 Docket Nos.: 50-259 and 50-260 License Nos.: DPR-33, DPR-52 Location: Limestone County, Alabama Type of License: 3293 Met, BWR,(GE)Type of Inspection:
Routine, Unannounced Dates of Inspection:
July 7-9 and 20-21, 1976.Dates of Previous Inspection:
June 19, 1976 4 I Inspectors-in-Charge:
F.S.Cantrell,,Reactor Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch (July 7-9, 1976)R.F.Sullivan, Reactor Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch (July 20-21, 1976)Accompanying Inspector:
None Other Accompanying Personnel:
None Principal Inspector:
~-0 JZc~R.F.Sullivan, Reactor Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Reviewed by: H.C.Dance, Chief Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Date g)7g Da e IE Rpt.Nos.50-259/76-17 aad 50-260/76-17 SUMMARY OF FINDINGS I..Enforcement Items None II.Licensee Action.on Previousl Identified Enforcement Matters Not inspected.
III.New Unresolved Items None IV.Status of Previousl Re orted Unresolved Items Not inspected.
V.Unusual Occurrences None VI.Other Si nificant Findin sNone a VII..Mana ement Interview The results of the inspection presented in the details of this report were discussed with Mr.Green and members of his staff on July 9 and'1.
IE,Rp t.Nos.50-259/76-17 and 50-260/76-17 DETAILS I Prepared by: ,R.F.Sullivan, Reactor Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Dates of Inspection:
July 20-21, 1976 Revdewed by: (H.C.Dance, Chief Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Date 1.Persons Contacted 2~H.J.Green-Plant Superintendent J.F.Groves-Acting Assistant Plant Superintendent J.B'.Studdard-Operations Supervisor.R.Hunkapiller-Assistant'Operations Supervisor T.G.Campbell-DPP Outage Director J.C.Mewbourne-Assistant Shift Engineer , E.G.Thornton-'Assistant Shift Engineer Unit 1 Fuel Reloadin The reloading of Unit 1 reactor was still in progress during this inspection visit and selected phases were observed by the inspector on both day and night shifts.Minor delays'ere being encountered with equipment problems on the refueling floor but they had no affect on safety of fuel handling.By the end of the inspection on July 21, 1976, 659 of the 764 fuel bundles had'been loaded in the core., No deficiencies in the loading operations were noted by the in-spector.3.Unit 2 Core Verification The inspector reviewed results of the, core verification check which was performed in accordance with step 6.2".1'4 i'n the fuel loading procedure, SRV3.Underwater TV was used to make a tape record of fuel bundle locations and'rientations.
When plant results personnel examined'the tape on July 13, 1976, they discovered a loading error.The positions of fuel bundles TZ622 and'TZ456, two diagonally adjacent fuel bundles, were reversed.The error was reported to i'
IE Rp t.Nos.50-259/76-17 and 50-260/76-17 I-2 plant management and was formally investigated.
PORC reviewed the incident and concurred in the conclusion that the existing safety analysis covered such an error and that no new safety consideration resulted.A special procedure was prepared, reviewed and approved to correct the error which was accomplished without difficulty.
The inspector reviewed records and had'iscussions which confirmed that the internal review system performed in accordance with re-quirements.
Corrective action included contacts with fuel, handlers and supervisors to reemphasize the importance of positive verifica-tion of location and orientation.
The inspector stated-that he considered the loading error a failure to adher to the loading procedure, which included an independent verification, to be contrary to Technical Specification 6.3.A.2 and that he further considered this matter a licensee identified non-compliance item.4.Outa e Or anization For Modifications An outage organization.,has been established at the Browns Ferry facility to be responsible for the overall.supervision, planning and scheduling, and QA surveillance for modification and addition activities which take place following fire restoration.
The fire restoration outage organization is, being phased out although certain of the personnel are being transferred to the permanent outage organization which will report.to the plant superintendent.
Those outstanding commitments from the'Recovery Plan're carried on the current scheduling list with identified due dates which includes those required to be completed prior to operation and those prior to the first refueling outage.The same items are also carried on the Master Exception List maintained by QA and reviewed by PORC prior to going to a new step or phase in operation.
Other commitments falling in the category of non-.hardware items.such as new procedures, administrative controls and training requirements, as well as minor maintenance items, are also included on the Master Exception List.The inspector concluded that TVA had provided sufficient internal controls to give assurance that required commitments would be fulfilled on a timely.basis.
IE Rpt.Nos.50-259/76-17 and 50-260/76-17 II-1 DETAILS II Prepared by: I F.S.Cantrell, Reactor I ector Reactor,Projects Sectio No.1 Reactor Operations and Nucl'ear Support Branch gc Da e.Dates of Inspection:
July 7-9, 1976 Reviewed by: H.C.Dance, Chief Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch F>~Date 1.Persons Contacted Tennessee Valle Authorit TVA H.G.Green-Plant Superintendent G.Dewease-Assistant Plant'Superintendent"R.Hunkapiller-Assistant Operations Supervisor J.Pitman-Instrument Superintendent W.E.Brown-Assistant Shift Engineer L.L.Kenndy-Shift Engineer J.Cox-Operations Superintendent A., Pedersen-Startup Engineer 2~Puel Loadin Puel loading operations for Units 1 and 3 were observed both on the refueling floor and in the control rooms at various times on the day shift on July 7, 8 and 9, and on the evening shift.July 8 to verify compliance with technical specifications and fuel loading procedures." No items of noncompliance were identified; however, one weakness was identified in.that the door to the roof of the reactor building is not locked (to prevent locking someone on the roof)and this area is not checked for occupancy prior to making the subcriticality check that is required periodically while loading new fuel to Unit 3.(The fuel loading procedure requires all personnel to be,off the refueling floor during-subcriticality checks).The plant superintendent stated."in
the exit interview that the necessary controls would'e establ'ished to assure control of access to the rod during subcriticality checks.
IE Rpt.Nos.50-.259/76-17 and 50-260/76-16 3.Vent Hole In Core S ra Header The, inspector asked if a vent hole had been added to the core spray header based on a recommendation from GE to eliminate a potential pipe cracking problem.The GE operations superintendent stated that core.spray pattern test confirmed that a vent hole had been drilled at the high point of the core spray headers between the shroud and the reactor vessel for Unit 3.A.record, search is in progress to determine if Units 1 and 2 core spray headers had similar vents.