|
---|
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
- _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
'* TVA EMPLOYEE CONCERNS REPORT NUMBER: 301.15-SQN
. . 4, SPECIAL PROGRAN REPORT TYPE: Sequoyah Nuclear Plant - Element REVISION NUMBER: 2 ,
TITLE: Hardware Not Properly Identified RRASON FOR REVISION:
To incorporate SQN Corrective Action Plan. Revision 1 To incorporate NRC comments. Revision 2 PREPARATION PREPARED BY:
G. Darrell Gardner 88f/ SMI/f'/
SIGNATURE DATE REVIEWS A lY Yf SIGNATURE s//:rll 4
'DATE j
TAS:
bhd
@b '"
~ SIGN 5TURE 3/17b 7
/ IIATE
) CONCURRENCES j
/
{CeG-n:Ykr*~~ bksth W/J/81 i SIGNATURE DATE SRP: (w- 7M SIGNATURE
' [l d.Vb)ak-TCSP MANAGER 1hl DATE N/A MANAGER OF NUCLEAR POWER DATE
' CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotos SRP concurrences are in files.
??HHT 0703260379 070319 P,DR ADOCK 05000327 PDR
a .
o.
.. W 9 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OPERATIONS CEG Subcategory: Mechanical Equipment Reliability and Design Element: Hardware Not Properly Identified Report Number: 301.15-SQN Revision 2 XX-85-102-005 Evaluator: G. Darrell Gardner 5//f/f7 G. Darrell Gardner Da'te Reviewed by: / # ff// 5Yff OPS CBC Member Date
- Approved by: a! # O//J/8[
g V. R. Lager 6ren 'Date 2195T
x .
Revision 2 I. HARDWARE NOT PROPERLY IDENTIFIED This report evaluates the issue that hardware is not properly identified in the field. The issue was identified for Browns Ferry Nuclear Plant (BFN) and was evaluated generically for Sequoyah Nuclear Plant (SQN).
II. SPECIFIC EVALUATION METHODOLOGY The following issue was identified by Quality Technology Company (QTC) for BFN and was determined generic to SQN:
XX-85-102-005 Brown's Ferry: Hardwaro is not properly identified in the field. A person needs a drawing to identify it. Nuclear Power Dept concern.
CI has additional information.
i The scope of this issue for SQN is perceived as relating to incorrect l or missing equipment identification tags. The Nuclear Regulatory l Commission (NRC) expurgated file for this issue was reviewed and no additional information was obtained. The SQN Special Maintenance Instruction (SMI) for system walkdowns was reviewed to determine actions underway at SQN to identify problems with equipment tags. An interim report prepared by the Office of Nuclear Power Configuration Management Survey Team was also reviewed to provide supplemental information related to component identification. Results of the evaluations at Watts Bar Nuclear Plant (WBN) and BFN were also reviewed. Interviews with the walkdown manager at SQN and with the Corporate Configuration Manager were conducted for supplemental l
Information.
l III. FINDINGS SQN SMI 0-317-30 (Reference 1) requires equipment tags to be checked against the flow and control drawings during system walkdowns. The l- walkdown manager at SQN confirmed that this was being done. According
' to the manager, several hundred missing tags have been identified. Not many casos have been identiflod where tags were incorrect. Those cases are being documented and corrective actions initiated in accordance l with tho SMI. The manager stated that not all systems are being l reviewed; only those systems or portions of systems identiflod by the l
Division of Nuclear Engineering (DNE) in walkdown packages are being
! vorified against the design drawings, i
l l
l Page 1 of 4
Rsvision 2 The Configuration Management Survey and Analysis Report (Reference 2),
Section II.C states that proper identification of items and documents .
will enable TVA management to ensure that:
Items are designed, manufactured, installed / erected, tested, operated, and maintained in accordance with the design criteria and licensing commitments.
The report notes in section III.C.1 that procedures exist for all sites, except BFN, which provide general instruction for assigning identification numbers to components, however, there is no consistent review process to ensure that unique ids are assigned in accordance .
with prescribed standards. As a result, multiple data bases (with different owners) exist (instruments tabs, Equipment Qualification IR2 identification System (EQIS), Q-lists, drawings, etc.) which contain i data discrepancies.
According to the Corporate Configuration Manager, Division of Nuclear Services, and a consultant in that office, the interim report has been included as an appendix to the new corporate Configuration Plan which is in review at this time. This new plan provides various task activities for plant sites and other central organizations to provide for new numbering schemes and new rules for maintaining cata bases.
Conclusions The issue that hardware is not properly identified was validated for SQN. The walkdown effort at SQN has identified numerous missing equipment tags and some casos of incorrect tags have been identified and are being corrected.
Tho scopo of the walkdown offort does not include verifying that data bases and drawings reflect the correct component identifiers. Although not specifically evaluated, traceability for testing and maintenance activities and proper operation of plant equipment may be compromised and are not precluded by the current situation. For these reasons, this issuo is considered safoty-related and may represent a significant condition adverse to quality. The new corporate configuration plan will addrons the issues related to drawing / data base discrepancies.
IV. ROOT CAUSE No root causo could be dotormined for missing oquipment tags at SQN.
The fact that multiple or incorrect ids exist is perceived to result from the lack of a contral point for control and review of ID assignments.
Page 2 of 4
.* Revision 2 3
i V. GENERIC APPLICABILITY l
Evaluations have been conducted at SQN, WBN, and BFN with similar findings. The' issue is considered generic to Bellefonte based on these findings, however, since BLN is presently in a limited construction phase, the new corporate configuration plan should be adequate to address and resolve these issues. For this reason, an evaluation at Bellefonte Nuclear Plant (BLN) will not be conducted by the Employee Concerns Task Group (ECTG).
VI. REFERENCES
- 1. - SQN SMI 0-317-30 Revision 2. " System Walkdown," August 11, 1986
- 2. TVA Office of Nuclear Power Interim Report, " Configuration Management Survey and Analysis Report," March 1986 VII. INMEDIATE OR LONG-TERM CORRECTIVE ACTIONS ;
l Corrective Action Tracking Document (CATD) OP-30115-SQN-01 requested l SQN to provide a plan to determine the extent of missing or incorrect l tags and propose corrective measures or detail measures already in l progress. l l
L Sequoyah's Corrective Action Plan (CAP) stated that the plant would: l l l l
Complete before Restart, tagging deficiencies identified and l classified as " Restart" by TVAs Design Baseline and Verification l l
Program (DB&VP). Corrections before Restart will be limited to components l Identified by the main control flow and control drawings and corrocted l under the DB&VP program. l l l Further discussion with a responsible individual in the Modifications l Group revealed that the work scope referenced by the CAP is limited to l resolution of discrepancies between the tags and the primary flow and I control drawings for safety-related equipment. Correctivo actions' l
, include tag replacements or drawing revision as necessary. The DB&VP l does not include all plant drawings, nor manuals and procedures, thus lR2
- the "fix" provided is not all-encompassing. It is, however, sufficient l l to ensure that the plant's nuclear safety is not degraded by tagging l l discrepancies. l l
l l The plant further proposed to: l l
l l Initiate a long-term CAP to reflect the unique identification I of mechanleal, electrical, and instrumentation components on the l necessary drawings to allow the components to be reflected in l procedures and identified in the fleid. l I
Discussion with the modifications representative indicated that tho I t
goal of this effort is to institute a uniquo equipment identification l l (UNID) system slallier to that employed by BLN. This project is I t i
j scheduled for completion in January 1988. I Page 3 of 4 I ;
l l
i-R:visien 2 CATD OP 30115-NPS-01 was written to the corporate configuration manager's office to address the resolution of data base and drawing .
discrepancies. Because the latter issue is generic, the corrective IR2 action response from the corporate configuration manager will be included in subcategory report 301 rather than in this report.
e 1
9 Page 4 of 4 c _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
O PAGE -
- ECPS120J-ECPS121C TENNESSEE WALLEY AUTNORITY RUN Tile -
REFERENCE OFFICE OF NUCLEAR POIER FREQUENCY - REQUEST RUN BATE -
EMPLOYEE CONCERN PR00 Raft SYSTEft (ECPS) *
(3 ONP - ISSS - RHM
' LIST OF EMPLOYEE CONCERN IIIFORMATI0Il CATEGORY: OP PLANT OPERe SUPPORT SUBCATEGORY: 30115 IMPROPER NameMARE IDEIITIFICATION e KEYMORD A S GENERIC KEYtIORD B g H APPL QIC/NSRS P KEYNORD C SUB R PLT BBSH INVLSTIGATION S CONCERN KEYHORD I CONCERN R DESCRIPTION NUMSER CAT CAT D LOC FLQB REPORT NS DRONIt'S FERRY: NARONARE IS NOT PROPE TA0GIIIG XX 102-005 OP 30115 N BFN YYYY I-85-733-BFN geOllC000FORMAIK REPORT RLY IDEllTIFIED IN TNE FIELD. A PERS OPERATIDstS T50172 ON NEEDS A BRAMIDIS TO IDENTIFY IT. GENERAL 100 CLEAR PetfER DEPT C080CERN. CI NAS 3 ADDITIOllAL INFORetATICII. NO FOLLON U P REGUIRED.
f 3 1 CONCERNS FOR CATEGORY OP SUBCATEGORY 30115 G
. i h
O C
G G.
'3 e
4 9
.1 _ _ _ _
I
- - - - .< , , , _ , _ -