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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] |
Text
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, . 1 '
. TVA EMPLOYEE CONCERNS REPORT NUMBER: 237.6 SPECIAL PROGRAM REPORT TTPE: Rationale For Non-Inclusion REVISION NUHBER: 0
(..
as Restart Item TITLE: CasinE of Current Transformers PAGE 1 0F 3 REASON FOR REVISION:
PREPARATION PREPARED BY:
T. L. Server (see Sheet 2 for signature) 10-10-86 SIGNATURE DATE C. W. Jordan (see Sheet 2 for signature) 10-10-86 REVIEWS PEER:
SIGNATURE DATE
$ ' lE <~ N SIGNATURE DAT1 CONCURRENCES WW CEG-H: G. . McNutt 10-24-86 SRP' u i l} d$/2 4-h SIGNATURE DATE SIGNATURE
? h ECSP MANAMR l$~$'$ N/A DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY) 2085T
- SRP Secretary's signature denotes SRP concurrences are in files.
8612170126 861210 PDR ADOCK 05000327 P PDR , __
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' f. ,
SEQUOYAH NUCLEAR PLANT ENGINEERING RELATED EMPLOYEE CONCERNS SPECIAL PROGRAM NON-RESTART JUSTIFICATION
SUMMARY
l SUBCATEGORY / ELEMENT 237.6 The employee concern regarding current transformer (CT) gasing and the resulting need for sampling is not a restart item for the following reasons:
- a. Sampling of the cts' oil for gas content is a planned activity.
- Therefore, the unavailability of one of the offsite sources will be-known in advance and precautions can be taken to minimize any adverse effects. < -
- b. The cts are part of the transmission system and not part of the s class 1E safety systems of SON.
- c. Multiple offsite sources exist at SQN, therefore loss of one source due to failure of a CT will not jeopardize plant safety or operation. Additionally, complete loss of offsite power is a design 43;, basis condition.
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p.
A t.
ATTACHMENT: List of Issues for Electrical ELEMENT NO. 237.6 0 .Date: 0040/86.
Evaluator -- -
Date ___ _M 0l2A Resp. Mgr .
Date l 0
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ECEG-HkbQ u- 1 4
r [v,$h Date IO'1Y O
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01720
M N mm nr r+ .m-LIST U ELECTRICAL ISSUES
-AT3 ELEE NT N 3" 7.6 BY: T. $arver A+ SGN RESTART - NO Date: 09/09/86 ,
e's, ,
?f Gasing of Current Transformers ELEENT iMERE RESPON- %
!$ SUES ADDRE SSED SIBLE CENERAL APPROACH /ETH000 LOGY FOR ELEEhT REPOST ,
CONCERN NUMBER (S)
- 1. Current transformer is *gasing" 237.6 15 1. Review TVA program for monitoring of CT gases.
WI-85-060-N02
'TVA's prchlem with gasing of (generating explosive gases within) current transformers has led to which leads to outages of Itnes and 2. Estabitsh ef fects of f ailure.
outages of Itne and bus ties to bus ties. Check todustry sources for similar occurrences, obtain oli samples and detern.ine 3.
gasing condition.*
- 2. Outages are required to obtain oil 237.6 TS sanples to monitor gasing conditions. 4. Review TVA plans to evaluate the need for manual sampling.
- 5. Explore industrial response to problem.
- 6. Compare TVA's approach / solution with industries.
DOCUEhTS NEEDED FOR REVIEW
- 1. TVA studies / report
- 2. Suppiter studies / reports
- 3. Current articles and publications on this subject.
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