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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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o TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-22 cnd -29 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 1 TITLE: SQN Calibration Control REASON FOR REVISION: To incorporate TAS and SRP conunents SWEC
SUMMARY
STATEMENT: The items in this report were identified by the Nuclear Regulatory Comenission (NRC) and were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. Concerns A02850226002-001 and A02850415004-001 will be ready for NRC closure following completion of corrective actions in progress. ,
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Title:
SQN Calibration Control Source Document: NRC Report 327, 328/85-05 SWEC Concerns: A02850226002-001 A02850415004-001 Report Numbers: SWEC-SQN-22 SWEC-SQN-29 B
Evaluator: kN lohQ[C i>!T ffh J. J. Knight 1'y i Date Reviewed By: ((/h K. R. Gass AL // '/- ei, Date Approved By: h 1.2 [9 / rg, A. G. DebbaMr Daf.e f 1730T l
Reports SWEC-SQN-22 and 29 SQN Calibration Control I. INTRODUCTION During the time period January 21-25, 1985 the Nuclear Regulatory l Commission (NRC) conducted a routine, unannounced inspection of the l Sequoyah Nuclear Plant (SQN) calibration control program (Reference 1). l During this inspection, NRC identified one violation (327, 328/85-05-01) lR1 which, along with later follow-up comments by NRC (Reference 2), was I addressed as two issues in the Stone & Webster Engineering Corporation I (SWEC) systematic analysis. These issues are as follows: l
.(1) A02850226002-001 Mechanical Measuring and Test Equipment (M&TE) Maintenance Untimely (2) A02850415004-001 M&TE Out of Calibration These two SWEC issues are combined in this report.
II. VERIFICATION OF THE SWEC ISSUES A. Background SQN Administrativo Instruction AI-31 (Reference 3) specified that when a calibration report received from TVA Central Laboratories is stamped "out of tolerance," an evaluation and investigation shall be made within 60 days. The purpose of this is to ensure that instruments are promptly recalibrated when required and that any measurement taken with out-of-calibration equipment is evaluated and corrected. Contrary to requirements, the NRC inspection found that 43 of 52 outstanding evaluations filed in the mechanical maintenance shop tool room exceeded the 60-day limit. Eight selected calibration reports stamped "out of tolerance" had been received at the plant from 129 to 497 days without completing the required evaluations. In a follow-up memorandum (Reference 2) to TVA, NRC stated their concern that systems or components may have been adjusted or verified using M&TE later found out of calibration without determining the actual safety significance of the condition for up to 60 days. TVA was informed that other facilities in Region II were determining the prior use and safety significance of out-of-calibration M&TE in a one or two weeks timeframe.
B. Corrective Actions Taken Corrective actions undertaken by SQN (Reference 4) included the following:
- 1. All delinquent reports were completed.
- 2. The computer tracking system for M&TE was revised to flag action items for the upcoming weet so that the appropriate section can be notified of any upcoming due dates.
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.3. A section instruction letter was written to establish.
. guidelines for tracking and maintaining M&TE. These include management control deadlines for each section having a part in +
the evaluation.
- 4. AI-31. " Control of Measuring and Test Equipment" (Reference 3) lR1 was revised to include safety evaluations as part of the M&TE out-of-tolerance program. Lines of authority and responsibility for handling out-of-tolerance M&TE were established in this procedural revision.
SQN initiated and completed a six month evaluation of the M&TE out-of-calibration problem and reported results of the evaluation
, to the NRC November 1985 (Reference 4c). Their status report.
Indicated a reduction in the overall time required to complete. '
evaluations with slightly less than 30 days as the average elapsed time and with 50 percent accomplished under 15 days. This was attributed by SQN to the new tracking system and the monthly reports generated by the system which increased visibility for management attention. Trend analysis was also initiated on METE equipment to determine which instruments could no longer maintain desired toleranc< and should be retired and replaced.
Although improvements were reported in November 1985, additional l improvement was still needed. TVA's quality assurance audit l QSQ-A-86-003, dated February 28, 1986 identified a deviation i
.(QSQ-A-86-003-D02) for not completing out-of-tolerance l investigations in a timely manner. The preliminary findings of l the quality assurance surveillance follow-up to this audit, dated l December 3, 1986, were reviewed with ECTG. These findings will be l reported later in December 1986. This surveillance found that l i
further improvements had been accomplished in the overall time i required to complete evaluations with "most" now under 15 days, but '
that additional improvement was still needed. 1 I lR1 M&TE out-of-tolerance investigations conducted in accordance with 1 SQN administrative instruction AI-31 (reference 3) include a safety l evaluation "to determine if the effects / consequences of using 'l t out-of-tolerance test equipment to perform the tasks listed in the I evaluation package create an unsafe condition for plant operation." l The evaluation packages include the documented evidence of these l r evaluations. The December 3, 1986 quality assurance surveillance l I
identified general compilance but isolated instances where the i evaluation may not have been properly accomplished. I
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[ SQN's Nuclear Performance Plan commitment to timely and effective l out-of-calibration investigations for M&TE is included in section l II.4.3.4 (reference 6). l C. Verification Methodology The SWEC concerns identified for Employee Concerns Task Group lR1 (ECTG) verification were stated as follows: l Page 2 of 4 l _ ._. ._ _ . , _ _ . _
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RIMS Number Issue RIMS Item A02850226002 43 out of 52 outstanding evaluations -001 filed in the Mechanical Maintenance Shop Tool Room exceeded 60 day limit. M&TE equipment.
102850415004 Concern that systems or components may -001 have been adjusted or verified using M&TE later found out of calibration.
A review was conducted of Sequoyah Compliance Correspondence NRC inspection reports and status reports, and the applicable SQN procedure concerning M&Tr calibrations. Calibration data May-October 1985 lR1 maintained by the SQN Materials Unit was reviewed to determine progress in the reduction of average time to perform evaluations. The 1986 l quality assurance audit and surveillance data concerning calibrations lR1 was reviewed with quality assurance personnel. l D. Verification Analysis Based on the ECTG verification activities described in II-C. it was determined that SQN corrective actions are being implemented; and l that the SWEC issues on calibration are being resolved. At the time l of this ECTG Verification, the NRC violation remained open; however. lR1 the SQN plant responses have been found acceptable to the NRC l (reference 5) and corrective actions are in progress. l E. Completion Status Based on SQNs implementation of a suitable tracking and reporting system for calibrations, management controls including notifications and periodic reviews, procedural revisions, and trending activities, the SQN M&TE calibration program is assessed to be progressing satisfactorily in most cases. These issues will be considered l complete and ready for NRC closure following additional evidence of lR1 program adequacy. These SWEC items remain open. ,
l III. REFERENCES
- 1. NRC Inspection Report Nos. 50-327/85-05 and 50-328/85-05 dated February 22, 1985, from R. D. Walker to H. G. Parris (SQN CATS Number 85449).
- 2. NRC Memorandum, " Report Nos. 50-327/85-05 and 50-328/85-05" dated lR1 April ll, 1985, from R. D. Walker to H. G. Parris.
- 3. AI-31, " Control of Measuring and Test Equipment," Revision 2. lR1 Current revision 6 is dated October 14, 1986. l Page 3 of 4
= 4. TVA Memorandum (a) "Sequoyah Nuclear Plant Units 1 and 2 - NRC
- -0IR, Region II Inspection Report 50-327/85-05 and 50-328/85 Response to Violation," dated March 22, 1985; (b) " Supplemental Response to Violation," dated May 10, 1985, from J. A. Domer to J.N. Grace," and (c) " Supplemental Response to Violation," dated November 15, 1985, from R. H. Shell to J. N. Grace.
- 5. NRC Memorandum, " Report Nos. 50-327/85-05 and 50-328/85-05" dated l January 3, 1986, from R. D. Walker to H. G. Parris. IR1 1
- 6. TVA Nuclear Performance Plan, Volume 2, dated July 17, 1986. l 6
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