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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 EMPLOTEE CONCERNS REPORT NUMBER: 304.02 SQN
. SPECIAL PROGRAN REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 3 TITLE: Electrical Penetration Breached REASON FOR REVISION:
To Incorporate SRP Comments TAS Conuments and Sequoyah Revision 1 Corrective Action Response.
To Incorporate SQN Corrective Action Response Revision 2 To Incorporate Editorial Comuments From TAS Revision 3 PREPARATION PREPARED BY:
P. L. Shepherd 11-13-86 SIGNATURE DATE
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- SRP Secretary's signature denotes SRP concurrences are in files.
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m TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OPERATIONS CEG Subcategory: Cable and Conduit i
Element: Electrical Penetration Breached Report Number: 304.02 - SQN, Revision 3 IN- 85-207-002 l
Evaluator: P. L. Shepherd _ 11-13-86 P. L. S ephe Date Reviewed by: //b'f$dfil' OPSCFgM ber
//~lY~Sb Date Approved by: f. . %v II-s/ -f L W.R. Lager,grpn Date 1604T l
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i I. Electrical Penetration Breached l
! This report evaluates the concern that a steel fish-tape is being used l to breach penetration seals in lieu of fiberglass or wooden rods.
- II. Specific Evaluation Nethodology This element consists of one concern identified at WBN and determined to be generic to Sequoyah.
IN-85-207-002 " Crafts are using steel fish-tape in lieu of fiberglass l or wood rods to breach penetration seals. This may cause damage to existing cables in the breached penetration. This practice of using
! steel fish-tapes violates procedure NAI-14 and Construction Management lR3 I
(known) memorandum of approximately July 1984. This is a construction department concern, and additional information is on file, withheld due to confidentiality."
The K-form was reviewed to determine the specific areas of concern.
Referenced documents were researched to determine the requirements, and other historical documents including NSRS and Quality Technology Company (QTC) (ERT) reports were reviewed. Cognizant engineers and craft in Unit A of the Modifications Branch of the Division of Nuclear Construction (NU CON) at Sequeyah (SQN) were interviewed to determine current practices being used at SQN. Cognizant engineers in the Division of Nuclear Engineering (DNE) were interviewed to clarify current requirements along with any pertinent history.
III. Findings NSRS Report I-85-702-WBN, " Breaching Electrical Penetrations,"
(Reference 4) documents the results of the investigation of concern IN-85-207-002 at WBN.
The SQN procedure that applies to the subject concern is Modifications j and Additions Instruction M&AI-13 (Reference 1). The review of this instruction revealed different requirements for breaching equipment being used on cable tray penetrations and conduit seals. According to the instruction, the use of a steel fish-tape is acceptable for breaching cable tray penetrations but a nonconductive probe must be used to breach conduit seals.
A review of all previous revisions of M&AI-13 showed this: l
- 1. A 1/2" conduit with a wooden conical nose was used as a breaching I tool from December 4, 1979 until January 21, 1982 (Revisions 0, 1, IR1 and 2) l
- 2. Revision 3 was effective from January 21, 1982 until l February 22, 1982, and required that the breaching tool be l nonmetallic. l Page 1 of 3
1- .
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III. Findings (continued)
- 3. From February 22, 1982 until the current revision (Revision 4, 5, I and 6) metallic breaching tools were authorized for use under i special conditions. l The author of NEAI-13 Revision 3 used, SQA 119 Attachment 1, dated IR3
-August 18, 1981, to initiate the procedure revision. During an l interview with this author he was asked his reasons for his use of the l words "any tool made of nonmetallic material" should be used as a lR1 breaching tool. His response was he was trying to change from the tool I described in Revisions 0, 1, and 2 to "any" tool. He stated that he did I not have a specific reason (such as cable insulation damage) for l stating nonnotallic other than good practice. I l The change request that resulted in Revision 4 of N&AI-13 dated l February 22, 1986, requested the ". . . use of metallic breaching tools I under special conditions. . . ". The current Revision 6 of N&AI-13 lR1 uses the words "At the discretion of the responsible engineer a l metallic breaching tool may be used". l According to interviews with Electrical Modifications personnel, l 1/2" conduit, fish-tape and various nonmetallic breaching tools have l been successfully used to breach penetrations since 1979 in accordance lR1 with M&AI-13 without any known cable insulation damage. This same fact l was stated in Employee Concerns Task Group's (ECTG) C010900 SQN Report. lR3 It was determined from the interviews with the site modifications personnel that they prefer to use a nonmetallic probe to breach all penetrations / seals where possible and only use a steel fish-tape where
, space restrictions prohibit the use of a longer, unflexible probe. No j violations of the current site instructions were discovered from these r interviews.
However, during this evaluation it was discovered that Modifications and, Additions Instruction M&&I-4 " Control, Power, and Signal Cables."
l Revision 8, dated December 31, 1985 (Reference 2) does not reference l M&AI-13 and does not show any responsibility for the craft to be aware of the requirements of M&AI-13. Also Electrical Design Standard DS-E13.5.1, " Raceways - Electrical Penetration Fire Stops and Pressure Seals, " Revision 0, dated December 5, 1977 gives guidelines on breaching penetrations on nuclear plants built after WBN.
Conclusions Based on the findings, this concern was determined to be not valid at i SQN. The use of a nonmetallic probe does not preclude cable insulation 1 damage resulting from the misuse of the probe by the craft. A metallic lR1 i
tool can be used to breach penetrations safely, without damaging cable l i
insulation as indicated by six years of modification work at SQN in I accordance with N&AI-13. l IV. Root Cause No root cause could be determined by this evaluation.
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V. Generic Applicability This concern is specific to Watts Bar and could apply to Browns Ferry and Bellefonte Nuclear Plants depending upon the requirements established in their procedures. There are no upper-tier document I requirements governing the use of breaching tools. The quality of IR1 workmanship at SQN does not indicate the need for more specific l requirements than those included in site procedures. l VI. References
- 1. Modifications and Additions Instruction N&AI-13. " Electrical Pressure Seal, Fire Stop Barrier and Flame Retardant Cable Coating, " Revision 6, dated January 28, 1985
- 2. Modifications and Additions Instruction N&AI " Control, Power, and Signal Cables, " Revision 8, dated December 31, 1985
- 3. TVA General Construction Specification Number G-38, " Installing Insulated Cables Rated up to 15,000 Volts " Revision 7, dated January 15, 1986
- 4. NSRS Investigation Report I-85-702 'JBK, " Employee Concern IN-85-207-002 - Breaching Electrical Penetrations," dated November 22, 1985
- 5. Electrical Design Standard DS-E13.5.1, " Raceways - Electrical Penetration Fire Stops and Pressure Seals," Revision 0, dated December 5, 1977 VII. Immediate or Long-Term Corrective Action M&AI-4 was revised on August 13, 1986 to incorporate the reference to l M&&I-13. IR1 SQN Corrective Action Plan response to (CATD Number 30402-SQN-01) lR2 accepted. l I
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e-REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY PACE -
FREQUENCY - REQUEST OFFICE OF NUCLEAR POWER RUN TIME - Il RUN DATE - 10I i[) ONP - ISSS - RhM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS)
LIST OF EMPLOYEE CONCERN INFORMATION CATEGORYs OP PLANT OPER. SUPPORT SUBCATEGORY: 30402 ELECTRICAL PENETRATION BREACHED KEYHORD A
() S H
GENERIC APPL QTC/NSRS P KEYHORD B 1
CONCERN SUB R PLT BBSH INVESTI0ATION S CONCERN KEYHORD C NUMBER CAT CAT D LOC FL45 REPORT R DESCRIPTION KEYHORD D
'O OP 30402 N HBN NNYN I-85-702-NBN NS CRAFTS ARE USING STEEL FISH TAPE IN INSTALLATION IN 207-002 SPECIFICATIONS T50157 REPORT LIEU OF FIBERGLASS OR HOOD RODS TO B REACN PENETRATION SEALS. THIS MAY C ELECTRICAL AUSE DAMAGE TO EXISTING CABLES IN TH CABLE i() E BREACHED PENETRATION. THIS PRACTI CE OF USING STEEL FISH TAPES VIOLATE-S PROCEDURE MAT-14 AND CONST. MGNT.
() (KNOWN) MEMO OF APPROX. JULY 1984.
CONSTR. DEPT. CONCERN. ADDITIONAL I NFORMATION IN FILE, HITHHELD DUE TO CONFIDENTIALITY. NO FOLLOHUP REQUIR
() ED.
1 CONCERNS FOR CATEGORY OF SUBCATEGORY 30402 GD ,
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