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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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TVA EMPLOYEE CONCERNS REPORT NUMBER: WP-25-SQN SPECIAL PROGRAM REPORT TYPE: Welding Project REVISION NUMBER: 1 TITLE: Improper Weld Repair REASON FOR REVISION: MADE THE FOLLOWING EDITORAL CHANGES:
Added revision note on cover sheet, numbered pages, and corrected operations report number for SRP consaants SWEC
SUMMARY
STATEMENT: N/A PREPARATION PREPARED BY:
Original signed by G. L. Pitz1 12-16-86 SIGNATURE DATE REVIEWS PEER:
Original signed by J. E. Rose 12-16-86 SIGNATURE DATE TAS: TECHNICAL REVIEW ONLY a *U- / '
l* U~hW__
DATE
/' M SIGNATURE CONCURRENCES Original signed by CEG-H: J. F. Lewis 12-29-86 n SRP: \) w N. (d. and/ l= l3 -87 n@$ SIGNATURE DATE f SIGNATURE
/
/-/3[7 N/A DATE Ob ECSP MA)(AGER DATE MANAGER OF NUCLEAR POWER CONCURRENCE (FINAL REPORT ONLY) s'
- *SRP Secretary's signature denotes SRP concurrences are in files, b$m a.n.
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WELDING PROJECT EMPLOYEE CONCERN EVALUATION REPORT REPORT NUMBER: WP-25-SON, R1 DATE: 12-04-86
SUBJECT:
EFFECT OF WELD REPAIRS NOT MEETING ASME CODES CONCERN (S) CONSIDERED: 2850162005 PREPARED BT A A' AsuzM t . b. T2t /2//<f[ OC, WP o' /
REVIEWED BY \ iG.. . 17.,[fu / & Q , OC , WP REVIEWED BY '
4eal=4 / f[/ 'T!85
, QA, WP O C REVIEWED BY $ rims id Y , .>>M
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, PROGRAM MANAGER APPROVED BY Revision 1, Reviend Report Format 2830T l 07870 l
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EMPLOYEE CONCERN
SUMMARY
SHEET Report Number: WP-25-SQN uR 1, Report
Title:
EFFECT OF WELD REPAIRS NOT MEETING ASME CODES I. CONCERN CONSIDERED: 2850162005 II. ISSUES INVOLVED.
- 1. Repairs by welding using overlays and patches. (The portion of this concern addressing repairs using furmanite has been addressed by Operations Report Number 308.03-SQN).
III. STATEMENT ON CONCERN / ISSUE VALIDITY Validity: Y X ,N , Substantiated: Y ,N X IV. EFFECT ON HARDWARE AND/OR PROGRAM Nons V. JUSTIFICATION:
Wold overlay repairs at Browns Ferry and patch repairs at Sequoyah were performed in accordance with TVA's ASME Section XI Repair and Replacement Program using detail weld procedures and welders qualified in accordance with 6SME Section IX.
VI. RECOMMENDATION AND/OR CORRECTIVE ACTION NEEDED None VII. REINSPECTION NEEDED: Y ,N X VIII. ISSUE CLOSURE Closure is based on this report.
IX. ATTACHMENTS
- 1. Text of Employee Concern - 2850162005 2830T Page 1 of 1
, o EMPLOYEE CONCERN Report Number: WP-25-SQN, R1 Report
Title:
EFFECT OF WELD REPAIRS _NOT MEETING ASME CODES I. SCOPE OF EVALUATION This engineering ovaluation relatos to the potentially generic employee concern 2850162005, which states the following:
"TVA makes repairs to their nuclear plants which are not in accordance with ASME Codos, such as overlays, patchos, and even furmanito (sophisticated glue)."
II. ISSUES ADDRESSED BY CONCERN The concern regarding temporary repairs is a shared concern with the Operations Employee Concerns Task Group. This report only addresses repairs by welding using overlays and patches. The portion of this concern addressing repairs using furmanite has been addressed by Operations Report Number 308.03-SQN.
III. CONCERN VALIDITY OR SUBSTANTIATION A. Weld Overlays Wold overlay repairs to Intorgranular Stress Corrosion Cracking (IGSCC) flaws in Boiling Water Reactor stainless steel piping were first applied on Quad Cities unit 2 Reactor Water Cleanup piping in oarly 1982. Since that timo, over 300 of these repairs have boon applied worldwide. This includes 42 overlays on Drowns Ferry unit 1 primary piping, one overlay on Drouns Ferry unit 2 primary piping, and two overlays on Browns Ferry unit 3 jot pump instrument nozzlo safo ends. The overlays on tho Browns Ferry units are designed to provide safety margins required by the ASME Codo using Subarticle IWD-3640 of the ASME Section XI Codo as a guido. Tho wolding ;
aquipment, personnel, and detail weld procedures utilized for these overlays wore qualified in accordance with ASME Section IX Codo requirements and additional requirements recommended by the '
industry. The overlays were applied in accordance with the Section XI Repair and Replacement Program which includos ANI and ANII hold points and final sign off in compliance Section XI Articlo IWA-4000, Repair Procedures. The use of overlays is widely accepted by the industry and N7C. The published documents which contain the NRC position for overlay repairs to IGSCC degraded piping in operating plants include NRC Genoric Lottor 84-11 and NUREG-1061 (Volumes 1 and 3). In addition, publication of Revision 2 of NUREG-0313 is currently ponding and its technical provisions havo boon prosonted to the ACRS. This document will consolidate the regulatory position reprosantad by the previous documents and updato it to includo recent regulatory actions and ruscarch results. 1ho results of the ovorlay repair proceduros for Browns Forry unit I woro reported to i
pago 1 of 3 4
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i*,
- Wp-25-SQN, R1 NRC in late 1983. The NRC then issued a Confirmatory Order and Safety Evaluation (Docket No. 50-259) which granted approval for unit 1 to be returned to power and operated in its repaired configuration. The results of the overlay repair procedures for Browns Ferry units 2 and 3 were also reported to NRC. The NRC has not yet granted approval for unit 2 to be returned to power; however, the NRC did issue a Safety Evaluation report (Docket No.
50-296) which granted approval for unit 3 to be returned to power and operated in its repaired configuration.
In summary, this portion of the employee concern is valid but not substantiated for the following reasons.
- 1. Overlays are designed to provide safety margins required by the ASME Code using Subarticle IWB-3640 of ASME Section XI pa a guide.
- 2. Personnel and procedures are qualified in accordance with ASME Section IX and additional requirements rocommandod by the industry.
- 3. All weld overlays are applied in accordance with the TVA Section XI Repair and Replacement Program.
- 4. Weld overlays are widely used and accepted by the industry and NRC.
- 5. The NRC has issued two Safety Evaluation Reports (Docket Numbers 50-259 and 50-296) which granted approval for Browns Ferry units 1 and 3 to be returned to power and operated in their repaired configurations.
B. Patches ,
TVA has utilized reinforcement patches as temporary repairs to ASME Code Class 3 and ANSI 031.1 raw water piping systems whore pipe wall thinning below acceptable thicknossos due to corrosion and/or cavitation has occurred. Piping subject to wall thinning is monitored ultrasonically on a continuing basis by plant Survoillance Instructions. Wall thickness values that are below minimum wall thickness established by Division of Nuclear Engincoring (DNE) are ropaired on a temporary basis by the installation of a rainforcement patch.
For SQN, acceptable wal.1 thickness values for the various piping diameters of the ERCW system have been generically addressed by DNE calculation N2-67, Essential Raw Cooling Water Corroded Piping Qualification. Patchos were installed using woldors and dotail wold proceduros qualified in accordanco with ASME Section IX and documented in accordance with the ASME Soction XI Ropair and Replacement Program for SQN. DNE performed an Unroviewod Safety Question Determination (USQD) on the structural intogrity of the reinforcement patch installations and their offect on the ERCW system. DNE concludod that the addition of temporary patchos does Pago 2 of 3
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- s. .
WP-25-SQN, R1 not significantly affect the ERCW piping analysis and provides adequate structural integrity based on the following:
- 1. The patch does not significantly change the piping cross-sectional stiffness or weight.
- 2. The patches are of the same thickness as the original pipe wall thickness.
3, The installation welds are sized such that the process pipe will not fail during any plant condition.
In summary, this portion of the employee concern is valid but not substantiated for the following reasons:
- 1. Reinforcement patches are designed with adequate safety margins such-that the piping will not fail during any plant condition.
- 2. The impact of the patch installations has been reconciled with the ERCW piping analysis.
- 3. The patches are installed using welders and detail weld procedures qualified in accordance with ASME Section IX, and documented in accordance with TVA's ASME Section XI Repair and ;
Replacement Program.
IV. . CONCLUSIONS To date, TVA has performed weld overlay repairs at Browns Ferry and reinforcement patch repairs to raw water piping at Soquoyah. In all cases, design verification of the repairs was well documented and structural integrity of the affected systems demonstrated. The repairs were performed in accordance.with TVA's ASMC Soction XI Repair and Replacement Program using detail weld procodures and woldors qualified in accordance with ASME Section IX. Therefore, no corrective action is
, roquired and the subject concern is closed, i
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REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY ' PAGE -
FREQUEf!CY - REQUEST OFFICE OF NUCLEAR P0HER RUN TIME - I6:
CNP - ISSS - RUM EMPLOYEE C0riCERN PROGRAM SYSTEM (ECPS) RUN DATE - 11/
LIST OF EMPLOYEE CONCERN INFORMATION CATEGCRY: HE NON CA/QC HELDING SUBCATEGORY: 50805 IMPROPER HELD REPAIR S GENERIC :. KEYWORD A H APPL QTC/NSRS P KEYHORD B CONCERN SUB R PLT B B.S W INVESTIGATION S CONCERN KEYHORD C g NUMBER CAT CAT D LOC FLQB REPORT R DESCRIPTION KEYHORD D XX 1c0-001 HE 50805 N SQN NNNN SR SEQUDYAH: AN UNDETERMINED NUMBER OF HELDING .
T50153 K-FORM HELDS MAY HAVE BEEN IMPROPERLY REPAI REHORK
'l RED. DETAILS KNGHN TO QTC, HITHHELD OPERATIONS
$ .
- DUE TO CONFIDENTIALITY. CONSTR. DE HELDS PT. CONCERN. CI HAS NO FURTHER INFO RMATION. NO FOLLOHUP REQUIRED.
30303 S NPS YYYY SS TVA MAKES REPAIRS TO THEIR NUCLEAR P k 2350162005 OP HE 50505 REPORT LANTS HHICH ARE NOT IN ACCORDANCE HI TH ASME CODES, SUCH AS OVERLAYS, PAT
~
CHES, AND EVEN FURMATITE (SOPHISTICA '
TED GLUE).
2 CONCERNS FOR CATEGORY HE SUBCATEGORY 50805
. .: .