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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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l TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTHER SITES CEG Element
Title:
Electrical Problem, Radiological Protection, and Security Violation SWEC Concerns: A02850910002-001, -002, -003, -004 Source Document: NRC Inspection Report Nos. 50-327, 328/85-26 Report Number: SWEC-SQN-41 Evaluator: Q '
/D[/kN J. J. Knightly Date Reviewed By: ((. /o-/5 V 6 K. R. Gass Date Approved By: I_I T' /e//f!f6 A. G. Debbage( D' ate /
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8612090728 861120 PDR P
ADOCK 05000327-PDR -
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Rsport SWECrSQN-41 Electrical Problem, Radiological Protection, and Security Violations I. Introduction During the routine NRC inspection at Sequoyah July 6 - August 5, 1985-(reference 1), two violations and two concerns were identified which were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis:
A. A02850910002-001, Improper Fix for an Electrical Problem (Violation 328/85-26-11)
B. A02850910002-OO2, Failure to Perform Whole Body Frisk (Violation 327, 328/85-26-03)
C. A02850910002-003, Potential Security Violation (NRC concern)
D. A02850910002-004, Potential Security Violation (NRC concern)
Information on the background, the corrective actions taken, the verification methodology and analysis, the completion status, and any pertinent references is included in this report.
II. Verification of SWEC Issues A. A02850910002-001, Improper Fix for Electrical Problem
- 1. Background
- - The violation occurred due to the unit operator inserting a 4
paper wedge in the rod position indication module to reduce vibration in a loose connection instead of initiating a i maintenance request (MR) to correct the problem. The MR should have been issued in accordance with Sequoyah Standard Practice SQM-2, " Maintenance Management System," and the condition
! reported per Sequoyah Administrative Procedure AI-12, " Adverse Conditions and Corrective Actions." -
The inspector identified this as violation 328/85-26-09, later re-designated 85-26-11 per TVA discussion (reference 2).
- 2. Corrective Actions Taken I
(a) A maintenance request (MR AS45763) was initiated, and the loose connector was tightened (b) A training letter (reference 3) September 30, 1985 was issued to all Operations
- Section personnel. The letter concerned the violation and the proper method for correcting equipment problems.
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Page 1 of 5 l
- 3. V4rification Methodology The SWEC concern identified for Employee Concerns Task Group (ECTG) verification was stated as follows:
RIMS NUMBER ISSUE RIMS-ITEM l n02850910002 Improper fix for an -001 electrical problem led to a violation. Inadequate l procedural compliance and !
lack of training are evident.
ECTG reviewed the Sequoyah compliance licensing files for internal and external correspondence related to this issue.
This review of the pertinent documentation formed the basis for this verification activity.
- 4. Verification Analysis Corrective actions were implemented as described in II.A.2 above. The TVA corrective action response was found acceptable to the NRC (reference 4), and the violation was closed (reference 5). NRC stated that the item was closed following an audit of SQN's identification of items requiring Maintenance Request initiation.
- 5. Completion Status Based on SQN corrective actions, compliance with requirements, and NRC closure of the item, no further action on this item is required . The SWEC concern is closed.
B. A0285091002-002, Failure to Perform Whole Body Frisk
- 1. Background The NRC inspector identified two individuals using a hand and foot monitor at the exit from a regulated zone, but failing to perform a whole body frisk. Following notification by the inspector, SQN health physics personnel recalled the individuals, performed a whole body frisk, and surveyed areas entered by the individuals after leaving the contaminated zone. It was determined that the individuals were not contaminated. The incident was identified as an NRC violation 327, 328/85-26-03 (failure to perform a whole body frisk).
- 2. Corrective Actions Taken SQN stated (reference 2) that a radiological incident report was issued to each individual; the responsible section supervisor issued a formal warning letter to each individual; and both individuals attended refresher training on frisking requirements. Several steps were taken to improve the Health Physics program:
Page 2 of 5
i
- Ths HP s;ction assign:d a HP technicinn to th2 maintenance
[ section to provide additional training for supervisors and h; craftsmen to increase their awareness of HP practices and
!; procedures.
The HP Staff initiated daily observations of known radiation work permit areas to ensure proper frisking techniques, a The QA staff began surveillance for personnel monitoring including the issuance of deviation and corrective action notification as required. Following identification by NRC i of an additional exas.ple of the violation, NRC required (reference 8) additional SQN corrective action. SQN
! responded (reference 6) that (1) signs had been posted at j the main egress stations detailing proper frisking i techniques (2) clocks had been installed at those stations
! to assist with frisking time requirements (3) QA j surveillances were continuing and (4) assignment of the HP
! technician to the Maintenance Section was continuing. The j SQN corrective actions were accepted by the NRC (reference 7).
- 3. Verification Methodology The SWEC concern identified for ECTG verification was stated as follows:
RIMS NUMBER ISSUE RIMS ITEM A02850910002 Failure to follow prescribed --002 radiological direction resulted in a violation.
Failed to do a whole body frisk.
ECTG reviewed the Sequoyah Compliance Licensing files for internal and external correspondence related to this issue.
This review of the pertinent documentation formed the basis for this verification activity.
- 4. Verification Analysis The ECTC review found that the NRC violation was closed in NRC inspection Report 86-15 dated April 4, 1986 (reference 5). NRC f noted at this tin that they reviewed the SQN quality assurance p audits of surveillances for personnel dosimetry and frisking.
/ It was noted that SQN audits for strict compliance to Health Physics practices had improved and the inspector observed an increased awareness among plant personnel of proper placement t of dosimetry and frisking techniques.
}
- 5. Completion Status j Based on the SQN corrective actions, compliance with j requirements, and NRC closure of the item, no further action is 1 required. This item is closed.
1 1 ,
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C. 002850910002-003 and -004, Potsntial Sicurity Concerns
- 1. Background Two security concerns were identified during the July 6 -
August 5, 1985 inspection (reference 1). These were to be l
reviewed by NRC Region Il security inspectors for potential violations. These concerns involved movement of naterials into the protected area and the visibility of the protected area boundary. These items contain safeguards information and no additional background information will be provided in this report.
- 2. Corrective Actions Taken During NRC follow-up review (reference 9) September 3-6, 1985, the security inspectors determined that no violations had occurred. These items were withdrawn from the NRC tracking system.
- 3. Verification Methodology The SWEC concerns identified for ECTG verification were stated as follows:
RIMS NUMBER ISSUE RIMS ITEM A02850910002 Identification of -003 security observations for review as potential violations required.
These concerns involved movement of mail into the protected area.
A02850910002 Identification of -004 potential violations concerning visibility of the protected area needed for review.
ECTG reviewed the Sequoyah Compliance Licensing files for internal and external correspondence related to these issues, and the NRC status and tracking system for the issues. This review of the pertinent documentation, in addition to discussion with SQN public safety personnel, formed the basis for this verification activity.
D. The ECTG review indicated that the NRC security concerns related to movement of materials into the protected area and the visibility of the protected area boundary were satisfactorily resolved.
Documentation of the review and withdrawal of the concerns is included in NRC Inspection Report 327, 328/85-30 (reference 9),
s i
Page 4 of 5
E. Completion Status Based on SQN compliance with requirements and NRC withdrawal of the concerns, no further actions on these items is required. The SWEC concerns are closed.
III. References
- 1. NRC Inspection Report Nos. 50-327/85-26 and 50-328/85-26, dated September 6, 1985, R. D. Walker to H. G. Parris
- 2. TVA letter, "Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE Region II Inspection Report 50-327/85-26 and 50-328/85-26," dated October 7, 1985, J. A. Domer to J. N. Grace
- 3. SQN Training Letter, "SQN-CATS #85378, NRC Violation 50-328/85-26-11", dated September 30, 1985, J. M. Anthony to Operations Personnel
- 4. NRC letter, " Report Nos. 50-327/86-26 and 50-328/86-26", dated November 1, 1985, R. D. Walker to H. G. Parris
- 5. NRC Inspection Report Nos. 50-327/86-15 and 50-328/86-15, cated April 4, 1986, J. A. Olshinski to S. A. White j 6. TVA letter, "Sequoyah Nuclear Plant Units 1 and 2 - NRC-OIE l Region II Inspection Report 50-327/85-26 and 50-328/85 Supplemental Response", dated January 3, 1986, J. W. Hufham to J. N. Grace
- 7. NRC letter, " Report Nos. 50-327/85-26 and 50-328/85-26", dated i February 3, 1986, J. A. Olshinski to S. A. White
- 8. NRC Inspection Report Nos. 50-327/85-38 and 50-328/85-38", dated December 12, 1985, D. M. Verrelli to H. G. Parris
- 9. NRC Inspection Report Nos. 50-327/85-30 and 50-328/85-30, dated October 1, 1985, R. D. Walker to H. G. Parris l
Page 5 of 5
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TVA EMPIhYEE CONCERNS REPORT NUMBER: SWEC-SQN-41 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 l
TITLE: Electrical Problem Radiological Protection, and I Security Violation REASON FOR REVISION: N/A SWEC
SUMMARY
STATEMENT: The items in this report were identified by the Nuclear Regulatory Comunission (NRC) and were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. All items evaluated within this report were verified to be adequately addressed and were closed by the NRC.
PREPARATION PREPARED BY:
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- SRP Secretary's signature denotes SRP concurrences are in files.
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