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# | {{Adams | ||
| number = ML18283B611 | |||
| issue date = 10/10/2018 | |||
| title = Responding to Letter of 8/5/1976, Referring to IE Inspection Reports for 50-259/76-17, 50-260/76-17, Letter Advising No Proprietary Information Is Contained | |||
| author name = Gilleland J | |||
| author affiliation = Tennessee Valley Authority | |||
| addressee name = Moseley N | |||
| addressee affiliation = NRC/RGN-II | |||
| docket = 05000259, 05000260, 05000296 | |||
| license number = DPR-033, DPR-052, DPR-068 | |||
| contact person = | |||
| document report number = IR 1976017 | |||
| document type = Inspection Report, Letter | |||
| page count = 11 | |||
}} | |||
=Text= | |||
{{#Wiki_filter: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.}} |
Revision as of 09:09, 31 July 2019
ML18283B611 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 10/10/2018 |
From: | Gilleland J Tennessee Valley Authority |
To: | Moseley N NRC/RGN-II |
References | |
IR 1976017 | |
Download: ML18283B611 (11) | |
Text
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.