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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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TVA ENPLOYEE CONCERNS REPORT NUMBER: 205.3(B)
SPECIAL PROGRAM ,
REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 1 NON-RESTART JUSTIFICATION
SUMMARY
TITLE: CONTROL OF DESIGN CALCULATIONS Calculation Records Retention
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PAGE 1 0F 2 REASON FOR REVISION:
Revised to incorporate TVA Engineering, TAS, and SRP comments.
PREPARATION h'i h. /1"f8/.
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SIGNATURE DATE REVIEWS y / E *- 5-R SIGNATURE DATE l
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56' . / /ZfMfAff WN" SIGNATURE DATE CONCURRENCES l 8701090524 861224 7 -
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SIGNATURE DATE SRP: 'R M SIGNATURE *
&dd DATE APPROVED BY:
/ /t'hL' /$-Ni-Th N/A ICSP MANA8ER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE
- SRP Secretary's signature denotes SRP concurrences (are in files. FINAL REPORT ONLY) 12/05/86 - 02000
SEQUOYAH NUCLEAR PLANT ENGINEERING RELATED EMPLOYEE CONCERNS
! SPECIAL' PROGRAM t
NON-RESTART JUSTIFICATION-
SUMMARY
SU8 CATEGORY / ELEMENT 2b5.3(B)
- The issues identified in this element refer to possible programmatic deficiencies having to do with the retention and-storage of design calculations. The issues are documentation and records related.
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The documentation and records requirements stipulated by 10CFR50 Appendix B, and ANSI N45.2.9, are reflected in the appropriate engineering' procedures. These procedures were reviewed and in general
- they adequately address quality record requirements and indicate management awareness and commitments to these requirements.
.c Issues concerning the existence, quality and scope of design calculations
'were addressed in Sequoyah Element Reports 205.1 and 205.2 as restart issues. The programmatic deficiencies identified in those report findings are being addressed prior to restart.
. ('C')::,
The storage and retention of design calculations as quality records, while an essential part of the plant quality program, do-not impact the performance or the quality of constructed systems. Concerns which address the technical adequacy of design calculations are addressed in other Sequoyah Element Reports as restart issues (e.g., 220.3, Design of Supports). Consequently, the programmatic issues in this element would not, of themselves, have an impact on plant safety.
. Design calculation issues requiring resolution prior to restart are i addressed accordingly in the above noted Sequoyah Element Reports.
Future problems in this area can be prevented through conformance to
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existing procedures and practices covering the retention and storage of design calculations, assisted by Engineering Assurance surveillance.
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' ATTACHMENT: List of Issues for Programmatic ELEMENT N0. 205.3 (B)
Date: 12/05/86
. ([h 02080 - Page 2 l
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SUBCATEGORY 205 - CONTROL FOR DESIGN CALCULATIONS ELEE NT NUMBER 205.3 LIST OF PROGRAMATIC ISSUES APPLICA8tE EPFLOYEE CONCERNS SQN RESTART - NO DA1E: 11/05/86 FLEENT DESCRIPTION Calculation Records Retention WI-85-100-043 IN-85-110-004 ELEENT l RESPON- ]
MfERE ISSUES ADDRESSED SIBLE GENERAL APPROACH / METHODOLOGY TOR ELEMNT REPORT CONCERN NUMBER (S)
WI-85-100-043 1. Some design cales are never prepared 205.1 JD issue &
There are problems in design Review baseline documents (QA Program Manual, calculations, in that some are 2. Some design cales are inadequate in 205.1 JD 1.
scope FSt.R) to determine policy and procedures for never prepared, some are in- development and control of design calculations.
adequate in scope and quality,
- 3. Some design cales are inadequate in ^ 205.1 JD and some are not stored as '
- 2. Review Engineering Department and Project
} quality records. There is quality procedures that implement the identified inadequate interface and calculation policies for development and control of design calculations, 4 There is inadequate control of design 205.2 JD which impacts traceability of calcs control fo design calculations. Consider the ,
l adequacy of the procedures.
design requirements. Cl has no further information. 5. There is inadequate interface 205.2 JO lcs 3. Review results of audits (QA, INPO, NRC) to Anonymous concern via letter. coordination with desi determine that design calculations have
_(e.g., 8 ranch / project)gn ca j
' _4} been performed to support existing design, i 205.3
-) JD i
- 6. Some design cales are not stored as quality records Other Issues 201.6 02 See element reports where addressed.
- 7. Design requirements traceability impacted by inadequate design cales NOTE: In issue 3 quality is defined as compliance with procedures, as opposed to technically error free calculations.
0897d-38
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SUBCATEGORY 205 - CONTROL FOR DESIGN CALCULATIONS 205.3 LIST OF PROGRAMMATIC ISSUES ELEMENT NUMBER APPLICABLE f,MPLOYEE CONCERNS SON RESTART - NO DATE: 12/05/86 ELEMENT DESCRIPTION Calculation Records Retention WI-85-100-043 IN-85-110-004 ;
ELEMENT WHERE RESPON-ISSUES ADDRESSED SIBLE GENERAL APPROACH / METHODOLOGY FOR ELEMENT REPORT CONCERN NUMBERfS)
Issue 1 IN-85-110-004 Lack of awareness by TVA DE
- h. TVA management is ignorant of requirements of ANSI N45.2.9 for 205.3 Jb retention of Design Calculations as Examine TVA procedures covering retention of Management (names given) of design calculations for evidence of compliance requirements to document the Q permanent Plant Records with ANSI N-45.2.9 and management awareness of load carrying capabilities documentation requirements.
of Pipe Supports for Future 2. There is a lack of awareness by 220.3 SC reference. TVA Management TVA DE management of requirements to document the load carrying issue 2 ignorant of requirements of ANSI N45.2.9 for retention capabilities of pipe supports for See Element Report 220.3 for the technical of Design Calculations as future reference. details on documentation regarding load permanent Plant records. carrying capabilities of pipe supports.
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REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY' PAGE -
62 FREQUENCY - REQUEST OFFICE OF NUCLEAR POWER RUN TIME - I2:57:19 C) ONP - ISSS - RHM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS) RUN DATE - 12/02/86 LIST OF EMPLOYEE CONCERN INFORMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 20505 CALCULATION RECORD RETENTION
() S GENERkC KEYHORD A H APPL QTC/NSRS P KEYHORD B CONCERN SUB R PLT BBSH INVESTIGATION S CONCERN KEYHORD C HUMBER CAT CAT D LOC FLQB REPORT _ R DESCRIPTION KEYHORD D
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IN 110-004 EN 20503 S HBN YYYY SR LACK OF AWARENESS BY TVA DE MANAGEME RECORD COLLECTION T50074 EN 21201 K-FORM NT (NAMES GIVEN) 0F REQUIREMENTS TO DESIGN REVIEW DOCUMENT THE LDAD CARRYING CAPABILIT- CONSTRUCTION O IES OF PIPE SUPPORTS FOR FUTURE REFE CONST MANAGEMENT RENCE. TVA MANAGEMENT IGNORANT OF R EQUIREMENTS OF ANSI N45.2.9 FOR RETE NTION OF DESIGN CALCULATIONS AS PERM O ANENT PLANT RECORDS.
HI 100-043 EN 20106 S HBN YYYY SR THERE ARE PROBLEMS IN DESIGN CALCULA DESIGN PROCESS T50215 EN 20501 REPORT TIONS, IN THAT SOME ARE NEVER PREPAR NONCONFORMANCE O EN 20502 ED, SOME ARE INADEQUATE IN SCOPE AND .' ENGINEERING EN 20503 QUALITY, AND SOME ARE NOT STORED AS REPORTS QUALITY RECORDS. THERE IS INADEQUA TE INTERFACE AND CONTROL OF DESIGN C O ALCULATIONS, NHICH IMPACTS TRACEABIL ITY OF DESIGN REQUIREMENTS. CI HAS NO FURTHER INFORMATION. ANONYMOUS C ONCERN VIA LETTER.
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2 CONCERNS FOR CATEGORY EN SUBCATEGORY 20503 O
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