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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 ENPLOYEE CONCERNS REPORT NUMBER: 241.4(B)
SPECIAL PROGRAN
' /;f' REPORT TYPE: SEQUOYAH ELENENT REVISION NUM8ER: 0 Q NON-RESTART JUSTIFICATION SUMARY TITLE: Amphenol Connectors PAGE 1 0F 2 i
REASON FOR REVISION:
4 PREPARATION PREP Y-2- $' -
N l$r W G V SIGNATURE DATE REVIEWS PEft:
SIGNATURE L ! M[S DATE Om
Nd**/ SIGNATURE whhs DATE l CONCURRENCES n m j n b. Y & lO/7llF6 CEG-H: 2 [)H I I'l#
SIGNATURE SRP: 1 }) /
SIGNATURl*
~~14 /2-Wh DATE
/ DATE I APPROVED 8Y:
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- 8*88 N/A ECSP NANAGEF DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotes SRP concurrences are in files.
I 8612170133 061210
! PDR ADOCK 05000327
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. ENGINEERING RELATED EMPL]YEE CONCERNS SPECIAL PROGRAM NON-RESTART JUSTIFICATION
SUMMARY
SUBCATEGORY / ELEMENT . 241.4( B)
This conccrn is considered specific to SQN. It is not considered a restart issue since the "old" vendor supplied defective Amphenol connector assemblies on the actuators of the standby diesel generator have already been replaced with new corrected connector assemblies (Ref.
MR Nos. A539668 thru A539671). Since, the issue of the concern has been corrJcted, there will be no failure to the safety related standby diesel generator caused by the connectors.
ATTACHMENT: List of Issues for Electrical ELEMENT NO. 241.4(8)
Date: 09/09/86 a -
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01550
....g . ., , . - . .
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r LIST OF ELE ~~ ' CAL ISSES
- 241,4 BY: J. Wheeler F: * *
.S ELEENT NUMBER Dats: 09/09/86 n '
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SQN REST C
Anphenos. Connectors ELEENT
('
s WiERE - RESPON-ADDRESSED SIELE GENERAL APPROACH /ETHODOLOGY FOR ELEENT REPORT ,
ISSUES CONCERN NUMBER (S) 241.4 JW 1. Review Report BW-85-001 BW 001 1. Inadequate installation of vendor 2. MTEAm.cqw.tcoge6(TWC W'W M OC
" Installation method of amphenol supplied amphenol connectors on t asSE3s AteiEdv M connectors on actuators of actuatogs of the standby diesel 3.gG LEAD eCA,ED FOR REVIEW DOCUENTS NEED standby diesel generator could generator could contribute to contribute to unreliable opera- unreliable operation of the 1. Report BMP-85-001 tion of the diesels. diesels.
-4 0'
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0918d-26
i OPERATIONS CATEGORY Enclosure 3 l
OPERATIONS (OP) ELEMENT REPORTS NOTES /=X----is l
ECTG WRITER'S GUIDE 1
Issue I. Title The brief introduction 1.0 touches on the source of Characterization Very brief introduction the concerns.
Summary I. Title 1. The Conclusions are I 2.0 towards the end of the Very brief introduction findings.
III. Finding (Conclusions) 2. The Conclusions services as a summary -
of the findings.
i i
Cover Sheet 1. The printed name of the g 3.0 Evaluators original evaluator (s) appears on the cover sheet.
- 2. The peer reviewer and l CEG-H approval signa-l tures are also on the cover sheet.
4.0 Evaluation II. Specific Evaluation Process Methodology Findings III. Findings 5.0 1980T
Enitccra 3 ,
OPERATIONS (OP) ELNENT REP 02TS NOTES /CONNENTS ECTG WRITER'S GUIDE 6.0 Root Cause IV. Root Cause 1. At the element level (Collective Significance) the Root Cause is often not identifible.
- 2. Collective significance is not addressed at the element report level.
7.0 Attachments / II. Specific Eva'uation l 1. A list of the concerns List of Concerns Methodology with text are included within this section.
- 2. Other reports are sometimes attached.
1
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Exc1coura 3 ECTG WRITER'S GUIDE NSRS/ERT* WELD PROJECT (WP) REPORTS- NOTES /CONNENTS -
1.0 Issue Background Info Issues Addressed Characterization (Section I) By Concerns (Section II) 2.0 List Of Concerns Background Info Scope of Evaluation (Section I) (Section I and Att-1) 3.0 Evaluators Coversheet Coversheet 4.0 Evaluation Scope Not Delineated As Part Process (Section II) Of The WP Reports however it is addressed as part of the Weld Projects Program Manual 5.0 Findings Findings Validity or (Section III) Substantiation (Section III) 6.0 Root Cause** Conclusion and Validity or *** Note that recommendations l are not included in element reports under the current ECTG program.
and Conclusion Recommendations Substantiation ** Overall Root Cause will (Section IV)*** (Section III) not be considered at this report level.
'The Weld Project has endorsed a number of ERT Reports and general issue level reports as adequately addressing the concerns at this level for SQN.
ENGINEERING CATEGORY Enclosura 3 Page 1 of 2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT 1.0 Issue 1. Characterization of Issue (s)
Characterization 2.0 Summary 9. Discussion, Findings and Conclusions 3.0 Evaluators Cover Sheet Information 4.0 Evaluation 8. Evaluation Process Process 5.0 Findings 9. Discussion, Findings, and Conclusions 6.0 Root Cause (Collective Significance)M* ** Overall Root Cause will not be considered at this report level.
- 7.0 Attachments / Attachments as required l List of Concerns Other items included 2. Have issue (s) been identified in Engineering Element in another systematic Reports analysis?
- 3. Document nos., ta ncs.,
locations or other specific descriptive identifications stated in element.
4 Interview files reviewed
- 5. Documer.ts reviewed related to l
the element I
1992T l
. ENGINEERING CATEGORY Enclosuro 3 Paga 2 of 2 ECTG WRITER'S GUIDE ELEMENT REPORT FORMAT Other items included in Engineering Element 6. What regulations, licensing Reports commitments, design require-(cont'd) ments, or other apply or control in this area?
- 7. List requests for information, meetings, telephone calls, and other discussions related to element, l
l t
l l
L
Enclosure 4 Page 1 of 3 p EMPLOYEE SEQUOYAH CONCERN ELEMENT REPORT NUN 8ER ISSUE Engineering 20103 WI-85-100-019 Incorporation of l- (Initial) IN-85-886-001 Requirements and WI-85-100-044 Commitments in Design Engineering 21303 WI-85-100-019 Inadequate Electrical (Initial) Design Criteria Engineering 22202 OW-85-003-001 Box Anchors with (Initial) Excessive Welding
, Engineering 22303 IN-85-886-N04 Local Instrument (Initial) Seismic Qualification
\
Engineering 22600 .WI-85-100-023 Design of Lighting (Initial) Fixture Supports Engineering 23001 EX-85-027-001 Fire Damper Latching (Initial) Test Engineering 24000 WI-85-100-009 Cable Derating (Initial) XX-85-122-027 (Design) and Cable XX-85-122-028 Coating Derating XI-85-122-029 IN-85-289-006 IN-86-254-005 IN-86-262-002 IN-86-036-001 IN-85-272-004 SWEC-03 A02-841116-010-001 Fire Protection /
(Final) A02-841116-010-002 Prevention A02-841116-010-003 A02-841116-010-004 A02-841116-010-005 NOTE: An initial report was not necessary. This will be the only submittal for SWEC-09.
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Enclosure 4 Page 2 of 3 EMPLOYEE SEQUOYAH CONCERN
- ELEMENT REPORT NUMBER ISSUE Operations 30302 IN-85-281-003 Location of Cold Leg (Final) IN-85-142-006 Accumulator and RWST Level Transmitters NOTE: Initial report transmitted 11/4/86.
Welding WP-16-SQN, R2 SQM-5-001-001 (WE 50700)* Performance of (Final) SQM-5-001-002 (WE 50700)* Preweld Inspections WBM-5-001-001 (WE 50700)*
BEM-5-001-001 (WE 50700)*
BEN-5-001-002 (WE 50700)*
BFN-5-001-002 (WE 50700)*
WI-85-030-007 (WE 50700)*
IN-85-212-001 (WE 50703)*
BFN-5-001-001 (WE 50100)*
4 WBM-5-001-002 (WE 50700)*
- Data base subcategory as shown in 9/26/86 printout.
NOTE: Initial reports transmitted 9/3/86 and 9/17/86.
Engineering 23502 IN-85-064-002 Exposed 480V Bus at (Final) Panel Top NOTE: An initial report was not necessary. This will be the only submittal for EN 23402.
Engineering 23504 IN-85-749-001 Exposed HV Cable (Final) Routed Without Raceway--Personnel Hazard NOTE: An initial report was not necessary. This will be the only submittal for EN 23504.
Engineering 23706 WI-85-060-N02 Casing of Current (Final) Transformers NOTE: An initial report was not necessary. This will be the only submittal for EN 23706.
-.n. ,,n, . . ,n , . , , , - . - , , . , , _ . . , ,,-....-..,,._n., , , , , - ,_, -- ,_, , , - - , . , . .
Enclosure 4 Page 3 of 3 EMPLOYEE SEQUOYAH CONCERN ELEMENT REPORT NUMBER ISSUE Engineering 24104 BNP-85-001 Amphenol Connectors (Final)
NOTE: An initial report was not necessary. This will be the only submittal for EN 24104.
2891T
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