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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
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TTA EMPIATRE CONCERNS REPORT NUMBER: C017303-SQN SPECIAL PROGRAN REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 3 (FINAL REPORT)
TITLE: Instrument Line Clamps PAGE 1 OF 5 1
REASON FOR REVISION:
Incorporate TAS and SRP comments. Revision 1 Incorporate line management response and finalize report Revision 2 Incorporate SRP rejection comments and finalize report Revision 3 ,
PREPARATION PREPARED BY:
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hfA$? Yk ECSP MANAGidt' DATE MANAGER OF NUCLEAR POWER DATE l CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotes SRP concurrences are in files.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: C017303-SQN SPECIAL PROGRAM REVISION NUMBER: 3 PAGE 2 0F 5 I. INTRODUCTION, The concerns evaluated are related to instrument line clamps which were improperly installed (IN-85-016-003) and substituted (EI-85-047-001).
These concerns were evaluated at Watts Bar Nuclear Plant (WBN) and determined to be potentially generic to SQN during the WBN evaluation.
II.
SUMMARY
OF PERCEIVED PROBLEMS Instrument line clamps were either improperly installed and/or damaged during or after installation. Some instrument line clamps are altogether missing. Unacceptable clamp substitutions were made in local instrument panel applications.
i j III. EVALUATION METHODOLOGY 1
A. Reviewed Significant Condition Report SCR SQNCEB8612, to uetermine if it is applicable to the areas of concern.
4 B. Reviewed the preliminary findings of the Bolt Torque Survey and interviewed the responsible Division of Nuclear Engineering (DNE) coordinator to determine if the work adequately addresses the areas of concern.
C. Reviewed Special Maintenance Instruction SMI-0-317-25 RO,
" Inspection and Corrective Maintenance of Small Diameter Instrument
- and Sensing Lines," and interviewed the responsible mechanical maintenance coordinator to determine if work adequately addressed the areas of concern.
- D. Reviewed Construction Specification N2C-946, " Requirements for Tightening of Non-High Strength Bolts in Friction-Type Connections,"
to determine if this specification was adequate and addressed the areas of concern.
l E. Reviewed Modification and Additions Instruction, M&AI 09,
" Inspection of Bolted Connections," to determine if future work would adequately address the areas of concern.
IV.
SUMMARY
OF FINDINGS A. Significant Condition Report SCR SQNCEB8612, identified a potential problem related to bolt tightening instructions. Sequoyah Construction Procedures; SQN Inspection Instruction Number 1
" Inspection of Bolted Connections," dated August 8, 1973, and SQN Inspection Instruction Number 66, " Inspection of Supports," dated i January 7, 1977, both gave tightening instructions for
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- TVA 3MPLOYRE CONCERNS REPORT NUMBER: C017303-SQN SPECIAL PROGRAM REVISION NUMBER: 3 PAGE 3 0F 5 IV.
SUMMARY
OF FINDINGS (Continued) hangers, supports, and miscellaneous steel which were vague; i.e.,
"show no slack and handtight." The lack of specific tightening instructions could cause non-high strength bolt connections to be unqualified.
B. In response to SCR SQNCEB8612, DNE onsite coordinated a sample program which reviewed the bolt torque on a number of installed supports. This program specifically identified that forty-nine percent of the 302 clamps sampled were loose (i.e., undertorqued).
Over fifty-three percent of the 183 instrument line clamps sampled were found loose. In addition, this sample program inadvertently identified an unspecified number of missing clamps (especially instrument line clamps). When these missing clamps were identified, a work request was issued to correct the discrepancy.
C. Special Maintenance Instruction, SMI-0-317-25 RO, was initiated on March 27, 1986 to walkdown all accessible unit 1 and 2 instrument lines. This included all instrument sensing lines, sampling lines, and radiation monitoring lines, as well as, any associated drain lines. The work instructions and acceptance criteria were as follows:
- 1. Check supports for any loose (i.e., without slack and as a minimum, handtight) bolting or missing clamps.
- 2. Install new clamps, bolts, nuts, spring nut, and etc., when determined to be missing. Tighten all such items found to be loose.
- 3. Inspect maintenance work performed.
- 4. Document all work performed.
According to the responsible coordinator, the scope of this SMI includes verification that the appropriate size clamp was used on the instrument lines. Local instrument panel applications were also included within the scope of this SMI.
The responsible coordinator estimated that this SMI was approximately 95-percent complete outside containment and only just begun inside j containment, when terminated. The reason for termination was i knowledge of the changing torque requirements, as defined in Construction Specification N2C-946, for bolted connections in supports for piping and tubing. Therefore, either a new SMI or a revision to the existing SMI will be initiated to incorporate the new torque requirements.
TVA EMPLOYEE CONCERNS REPORT NUMBER: C017303-SQN SPECIAL PROGRAM REVISION NUMBER: 3 PAGE 4 0F 5 IV.
SUMMARY
OF FINDINGS (Continued)
D. Construction Specification N2C-946, dated June 25, 1986, defines the requirements for reinspection and correction of certain friction-type bolted connections using non-high strentth bolts in supports for piping and tubing. This specification applies to unistrut-type clamps supporting safety-related piping and tubing. Safety-related covers systems under the Appendix B, QA program including category 1(L) seismic supports. The construction or installation restart
- requirements are as follows
- 1. Tightening or reinspection of clamps on tubing is not required before restart of the units. This work shall be complete for unit 2 and common supports before the return to service from the unit 2, cycle 4 outage and for unit 1 and common supports before the return to service from the unit 1 cycle 5 outage.
- 2. Before plant restart, all unistrut-type clamps on critical L '
supports, on all piping systems required for safe shutdown.
shall be inspected and corrected.
- 3. At the discretion of the Sequoyah Power Plant Superintendent (Maintenance), the inspection and correction of all clamps in 1
some plant areas or all of a certain type clamp may be implemented before restart.
The construction quality control for unistrut-type clamps assures that unistrut-type clamps shall be inspected in accordance with note 60 on drawings 47A050-18 and-18A. Clamps which require corrections shall be reinstalled in accordance with note 58 on drawing 47A050-17.
, E. Modification and Additions Instru: tion, M&AI 09, was revised on June 26, 1986 to incorporate the change in design requirements mentioned in Construction Specification N2C-946. M&AI 09 governs i
j the installation and inspection on all future bolted connections and adequately addresses the areas of concern.
Conclusion Based on the sample program and the documentation from the Special Maintenance Instruction, SMI-0-317-25, R0, the concerns are substantiated.
However, both the ongoing Special Maintenance Instruction, (SMI-0-317-25,
, R1 or similar instruction) ard the Modification and Addition Instruction, M&AI 09, will ensure that all the instrument line clamps are adequately
] installed and inspected.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: C017303-SQN SPECIAL PROGRAM REVISION NUMBER: 3 PAGE 5 0F 5 The schedule for the construction or installation restart requirements, per Construction Specification N2C-946, has only been partially justified. DNE onsite has justified (by piping analysis) the use of loose instrument line clamps, but no justification exists for the altogether missing instrument line clamps. Therefore, the schedule for the restart requirements has not been totally justified.
V. ROOT CAUSE The root cause of these employee concerns (IN-85-016-003 and EX-85-047-001) is a combination of inadequate installation / inspection procedures and changing design requirements.
I VI. CORRECTIVE ACTIONS The following is the line management's planned corrective action. l 1
The corrective action is a restart ites. l l
CATD 17303-SQN-01 lR3 1
A sample survey of instrument lines on critical systems will be l conducted by Mechanical Maintenance. DNE will evaluate the resulting l data to determine if sufficient justification for restart exists under l present conditions. If sufficient justification exists, then any l corrective action will be performed prior to restart. l VII. GENERIC APPLICABILITY These employee concerns are potentially generic to all TVA nuclear facilities.
VIII. ATTACHMENTS Attachment A Listing of concerns indicating Safety Relationship and Generic Applicability
C017303-SON-R3 ,',
ATTACHMENT A EI-85-047-001 CO 17300 N WBN YYYY SR UNIT 1 ELEVATION 676, 3/4" PIPE CLAMPS HAVE BEEN USED T50162 REPORT IN PLACE OF THE REQUIRED 1/2" PIPE CLAMPS, IN INSTRUMENT PANEL APPLICATIONS. CI HAD BEEN TOLD BY OTHER PERSONNEL THAT THIS TYPE OF SUBSTITUTION HAD BEEN DONE THROUGHOUT THE PLANT. CONSTRUCTION DEPT CONCERN.
CI HAS ?0 FURTHER INFORMATION. FOLIAWUP REQUIRED.
- IN-85-016-003 CO 17300 N WBN YYYY I-85-165-WBN SS TUBING NOT CLAMPED PROPERLY. THIS IS A SITEWIDE 1 T50030 REPORT CONDITION. TUBE 3/8" 6 S.S. INSTRUMENT LINES. UNIT
- 1. CLAMPS ARE BENT, CROOKED, TIGHT OR LOOSE. f CONDITION WAS NOTICED ABOUT A YEAR AGO.
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l Enclosure 4
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