Final Deficiency Rept Re 781213 Concrete Void Beneath Equipment Batch Reactor Bldg.Void Repaired on 790709 by Placing Grant Between New Concrete & LinerML19262A632 |
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Wolf Creek |
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Issue date: |
09/25/1979 |
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From: |
KANSAS GAS & ELECTRIC CO. |
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Shared Package |
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ML19262A631 |
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References |
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NUDOCS 7912070175 |
Download: ML19262A632 (4) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20112G3871996-06-0404 June 1996 Potential Part 21 Rept Re Capscrews W/Trace Code of K7 Mfg by Cardinal Industries (Now Known as Accutech) & Distributed by Energy & Process Corp for Plant CP S/N 0194012.Pump/motor Would Remain Operational Throughout Worse Case Scenario ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20086G2931991-11-21021 November 1991 Part 21 Rept Re Failure of Model 763 & 763A Static Pressure Transmitters.Caused by Short Circuit in Connector Pin to Adjacent Mounting Screw.Engineering Drawings & Mfg Work Instructions Changed & Stock Purged of Subj Transmitters ML20059N5191990-10-16016 October 1990 Part 21 Rept Re Rod & Bearing Assembly Failures Noted by Wolf Creek Nuclear Operating Corp During Testing.Rept Will Be Issued Outlining Root Cause & Corrective Actions to Prevent Recurrence ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20246J0631989-08-29029 August 1989 Part 21 Rept Re Namco Refusal to Certify Design & Matls for Replacement Namco Limit Switches Supplied by Masoneilan. Initially Reported on 890825.Switches Put on QC Hold Until Final Disposition of Switches Determined ML20244D2901989-06-0101 June 1989 Part 21 Rept Re Buchanan 724 Terminal Blocks Supplied by Limitorque Corp,Rather than Correct Buchanan 524 Terminal Blocks.Caused by Error in Order Processing.Training Held to Ensure That Procedures Followed Correctly ML20235Y4811989-03-0303 March 1989 Part 21 Rept Re Cracked Welds Discovered on Striker Plates of GE Circuit Breakers.Initially Reported on 890130.GE Advised Util That Striker Plates Subj to Impact Loading Only When Breaker in Racked Out & Operated in Test Position ML20195F6191988-11-18018 November 1988 Part 21 Rept Re GE Magne-Blast Circuit Breakers.Initially Reported on 881116.Welds on All safety-related Breakers Will Be Repaired Prior to Entry Into Hot Shutdown ML20151W7841988-08-16016 August 1988 Part 21 Rept Re Cracking of Slides Used in Four Way Valves Furnished on Actuators for MSIVs Due to Brazing/Heat Treating of Slide Matl.All Sites Using Actuators Will Be Formally Notified by 880826.List Encl ML20151B4291988-04-0101 April 1988 Part 21 Rept Re Inconsistencies in Gould,Inc Certificate of Compliance Received W/Class 1E Fuses Procured from Planned Maint Sys Due to Fuses Not Being Qualified for Certain Specs.Initially Reported on 880329.Fuses Remain on Hold ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. 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Initially Reported on 850426.Fire Dampers Found in Discrepant Condition Will Be Reworked in Order to Assure Integrity & Proper Functioning ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20116D3201985-04-22022 April 1985 Part 21 Rept Re Ruskin Mfg Co Welds Used to Join Damper to Damper & Damper Section to Mullion Plates.Welds Not in Accordance W/Approved Design Drawings.Drawing 5415 Revised to Indicate Weld Spacing.Drawing of Weld Spacing Encl ML20115J1361985-04-15015 April 1985 Forwards Insp Procedure for Investigating Emergency Diesel Generators for Fractured or Cracked Welds to Determine If Part 21 Problem Exists,Per Jg Borman ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed NRC-85-3024, Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware1985-03-22022 March 1985 Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware ML20102B9531985-02-13013 February 1985 Supplemental Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213. Coated Concrete Surfaces Inside Containment Will Perform Satisfactorily Under DBA Conditions ML20107B6931985-02-0707 February 1985 Final Deficiency Rept (53564-K161) Re Uncertainties in Resistance Temp Detectors Calibr.Westinghouse Evaluation Demonstrated That Revised Resistance Temp Detectors Uncertainty Acceptable ML20101T1211985-01-25025 January 1985 Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213.Destructive Adhesion Tests Performed on Locations Selected by Sampling Plan to Verify Acceptability of Coatings ML20104B1471985-01-18018 January 1985 Final Deficiency Rept Re Insp of Structural Steel Welds. Initially Reported on 840918.Structural Concerns Identified & Corrective Action Repts Issued to Have Shims Less than 1/4 Inch Thick Placed Flush W/Mounting Frame ML20104A8671985-01-13013 January 1985 Final Deficiency Rept Re Standby Diesel Generator B Left Bank Turbocharger.Initially Reported on 840504.Caused by Loose Lock Nut on Left Bank Turbocharger Lubricating Oil Pump Centrifuge.Damaged Turbocharger Repaired & Inspected ML20104A8171985-01-13013 January 1985 Final Deficiency Rept Re Subcooling Core Monitor Alarm & Caution Relays.Initially Reported on 840821.Interposing Relays & Diodes Added to Sys to Minimize Potential for & Suppress Effects of Any Arcs Generated ML20114C9141985-01-13013 January 1985 Final Deficiency Rept (53546-K158) Re ASME Hangers & Component Supports.Initially Reported on 841212.Insulation Contractors Revised Procedures & Retrained Personnel to Preclude Further Tampering of Supports ML20104B9241985-01-13013 January 1985 Final Deficiency Rept Re Water Damaged Limitorque Motor Operators.Initially Reported on 840203.Caused by Leakage During Sys Flushing & Hydrostatic Testing Activities.Seals Added Inside Conduit & T-drains Installed in Operator ML20114D1081985-01-13013 January 1985 Final Deficiency Rept (53564-K118) Re safety-related Field Procurement by Constructor.Initially Reported on 840103. Complete Review of Constructor safety-related Purchase Orders Completed.All Nonconformance Repts Resolved ML20114C8441985-01-13013 January 1985 Final Deficiency Rept Re Microbiologically Induced Corrosion in Hxs.Initially Reported on 840601.All HXs Utilizing Lake Water for Cooling Medium Eddy Current Inspected for Microbiologically Induced Corrosion ML20114C7981985-01-13013 January 1985 Final Deficiency Rept Re Removal & Replacement of ASME Components in Support of Cleaning & Flushing Activities. 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Initially Reported on 840717.Replacement of safety-related Equipment W/O QA Program Will Be Repeated Per QA Program ML20101M1031984-12-0707 December 1984 Final Deficiency Rept Re ITE-Gould Containment Cooling for Mechanical Interlocks.Initially Reported on 840316. Instruction Manual Revised to Change Installation Instructions of Size 5 Mechanical Interlock Assembly ML20101D3011984-12-0505 December 1984 Forwards Status Rept for Oct & Nov 1984 Re 10CFR50.55(e) & Part 21 Items ML20100R5131984-12-0101 December 1984 Final Deficiency Rept Re Standby Diesel Generator Lube Oil keep-warm Pumps Supplied by Crane-Deming.Pumps Will Be Designed for Reliability.Interim Pumps Reliable for Use Until ASME Rated Pumps Available ML20100C1161984-11-19019 November 1984 Deficiency Rept Re Pressurizer PORVs Preoperational Test Discrepancies.Special Operations Procedure Will Be Performed to Resolve Existing Test Discrepancies ML20099K7801984-11-16016 November 1984 Final Part 21 & Deficiency Rept Re Turbine Driven Auxiliary Feedwater Pump Governor Valve Stem Guide Bushings.Initially Reported 841017.Investigation Revealed That Defictive Parts Described by Terry Corp Installed at Facility ML20099K8291984-11-13013 November 1984 Final Part 21/deficiency Rept Re Pressurizer PORV Failing to Close During Preoperational Test.Initially Reported 841011. Resolution Will Be Provided by 841119 ML20099H1601984-11-0909 November 1984 Final Deficiency Rept Re ex-core Neutron Detector Field Cabling.Initially Reported on 841009.All Damaged Triaxial Cables & Connectors Repaired &/Or Replaced.All Insulation Panels Verified to Be Properly Reinstalled 1996-06-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
[Table view] |
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REPORT OF CONCRETE VOID, This final report is mado pursuant to 10CFR50.55(e) regarding a concrete void under the equipment hatch in the Wolf Creek Reactor Building.
(a) DESCRIPTION OF THE DEFICIENCY On December 13, 1978, when the forms for the sixth ring pour of the Wolf Creek Reactor Building were raised, a void beneath the equipment hatch was revealed.
The void the equipment hatch extended about 2 feet downward from the bottom of centerline. The width of the void was approximately six feet and the depth extended through the thickness of the wall, which is approximately eight feet.
(b) IDENTIFICATION OF THE FIRM CONSTRUCTING THE PACILITY Concrete placement for all Power Block Buildings at Wolf Creek is performed by Daniel International.
(c) ANALYSIS OF SAFETY IMPLICATIONS 9
it Because of the dimensions and location of the void described above, is impossible that the void could remain unseen and thus remain unre-paired until the structure would go into service. However, if it is postu-lated that the void remained undetected, it would have most probably been detected at the time of tendon tensioning (which occurs prior to operation) because of axcessive deformations as a result of tendon load. Repair of the void will meet all design requirements and no adverse effect to the health and safety of the public will result because of this void. .
(d) A DESCRIPTION OF THE CORRECTIVE ItCTION, ORGANIZATION RESPONSIBLE FOR THE isCTION, AND MEASURES TO PREVENT RECURRENCE The void was documented on Daniel Nonconformance Report 1SN0719C and forwarded to the Architect / Engineer, Bechtel Power Corporation, for evalaation and disposition. Before proceeding with the repair work, details of the repair were approved by the Architect / Engineer and sent to NRC Region Il personnel for review and concurrence.
A5 ' by 8' section of the equipment hatch liner was removed to facilitate the removal of unsound concrete and the placemen't of new concrete. Some localized areas which were near the void but underneath the remaining equipment hatch liner alse became suspect. A second nonconformance report NCR ISUO853C was initiated to document the possible existence of additional voids. Obse vation holes were drilled but, upon inspection,'no such voids were found and this non-conformance report was closed. On May 31, 1979, concrete was placed into the void area and later the cutout section of the hatch liner war welded back into position. -
On July 9, in accordance with the approved repair disposition, grout was placed between the new concrete and the liner utilizing two 7" dieneter stand-pipes to provide a head pressure. The grout.was agitated until it flowed from each of eleven 3/4" vent holes. None of the observation, standpipe, or vent holes were located in the part of the liner which will serve as the
" pressure boundary" for the containment buildin,, . After the grout was set, the standpipes were removed and fill plates welded into the standpipe holes.
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Nonconformance Report ISN0719C was closed on July 25 af ter completion of the above repair, which was performed by Daniel International. The ability of the Reactor Building to perform its designed function has not ocen, adversely affected by the void and subsequent repair.
To prevent recurrence of similar deficiencies, a Daniel ad hoc committee was formed to address the points that were described in Mr K V Seyfrit's letter to Mr G L Koester, dated December 19, 1978. A total of 10 recommendations were subsequently developed to provide improved control of future concrete placements.
These ten recommendations nave been been implemented as follows:
RECOMMENDATION 1 Implement a formal program for training responsible personnel in project procedural requirenents.
IMPLEMENTATION 1 The Daniel Wolf Creek department managers have developed and implemented an upgraded program for the training of project personnel in the requirement of the procedures applicable to their jobs. This program encompasses concrete placement activities as well as all other activities affecting quality.
RECOMMENDATION 2 Provide additional training in concrete placement and consolidation require-ments to applicable construction and quality control personnel to assure their knowledge for placing and consolidation of concrete.
IMPLEMENTATION 2 All const ruction supervision involved in concrete activities were trained in Daniel Procedure WP-IV-lO6 (Concrete Pre-placement, Placement, and Post-placement) .
Gang-box sessions were held for the additional training of con-crete craft labor.
RECOMMENDATION 3 Assign a Technical Superintendent-Concrete for the project to direct con-struction personnel in preplanning their work.
IMPLEMENTATION 3 Daniel Procedures AP-II-02, WP-IV-106, and QCP-IV-106 have been revised to incorporate the position of the Technical Superinter. dent-Concrete, The person filling this position reports directly to the Cons _ruction Manager and is responsible for reviewing concrete pours prior to placement and pre-paring special instructions to aid concrete placement personnel.
RECOMMENDATION 4 QC management should conduct regularly scheduled meetings with their sub-ordinate supervision to discuss work forecasts and potential and real problem areas.
Also, QC maaagement should be required to participate in project planning meetings.
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. IMPLEMENTATION 4 The QC Manager holds weekly meetings with the Discipline QC Engineers to discuss forecasts, audit findings, trends, and other areas relating to their responsibilities. This information is passed on to supervisors by the Discipline QC Engineers during regularly scheduled meetins. Representativer from the QC department attend the project planning meetings, which are held each week.
RECC:"ZNDATION 5 Revise WP-IV-lO6 and QCP-IV-106 (Concrete Preplacement, Placement and Post-placement) to address preplanning and special written instructions for difficult concrete placement activities.
IMPLEMENTATION 5 WP-IV-106 was revised to include the details of preplanning and preparation of special written instructions by the Technical Superintendent-Concrete. QCP-IV-lO6 was revised to catablish lines of commun. ation between QC and the Technical Superintendent-Concrete.
RECO:O'ENDATICN 6 A Quality Assurance audit of on-going training of craf t personnel should to conducted in the near future.
IMPLE!SNTATION 6 Daniel QA performed an audit of the training of craft personnel on January 29, 1979. KGLE QA has since audited this training twice and found implementation of the program to be adequate.
RECO:CiENDATION 7 Additional special formal and informal training for craft personnel should be conducted and documented as specifi ed by the Technical Superintendent-Concrete.
IMPLEMENTATION 7 Gang-box training sessions are being conducted with the concrete placing /
and curing personnel by the Technical Superintendent-Concrete and the Concrete Superintendent. The persons who will make the placement use this session to view the difficult areas and ask any questions they may have regarding the place- '
[
ment. These meetings are documented by the signatures of the re ponsible foremen on copies of the special instructions which require this type cf training.
RECO:0:ENDATION 8 s
The Project Manager and the Regional Manager, Power Group should neet
/
with QC personnel te reaffirm their independence and authority.
IMPLEMENTATION 8 The Project Manager and the Regional Manager, Power Group, held a meeting with site Quality Control personnel on January 24, 1979 and re-affirmed the ,
independence and authority of the QC department. This meeting was documented and is part of the QC department personnel training record.
/
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RECO:OiENDATION 9 Add to the Daniel Quarterly Quality Assurance Committee Meeting Agenda an item to review the independence and authority of the QC department. This meeting is a joint meeting between KG&E and Daniel.
IMPLEMENTATION 9 The independence and auti.ority of QC has been discussed and confirmed by Daniel and KGEE Management at dhe Daniel QA Committee meetings of February 15, June 6, and September 12, 1979.
RECC i'ENDATION 10 Suhmit formal requests to the Architect / Engineer when required to facilitate placcment of concrete.
IMPLE GNTATION 10 Field Change Requests (FCR 's) or Construction Variance Requests (CVR 's) have been submitted to the Architect / Engineer when changes were needed to facilitate the placement of concrete. This is now a procedural requirement of WP-IV-106.
CONCLUSION The implementation of the committee's recommendations were verified through audits oy the Daniel and KG&E Quality Assurance Deparbments. After KG&E verification, Work Hold Agreement #03, which suspended all safety related concrete placement, except for repair of the void, was released on March 5, 1979. Concrete placement resumed in all buildings except the Reactor Building, which was placed on hold by Werk Hold Agreement #05 because of NRC questions regarding the strength of the Reactor Building basemat concrete. On March 8, 1979, Stop Work Order #04 was issued when it was determined that concrete crews had failed to exactly follow the placing instructions that had been provided by the Technical Superintendent-Concrete.
ment.
The Technical Superintendent-Concrete '.as not present during tne place-This Stop Work Order was released on March 22 after extensive retraining of craf t personnel and replacement of the Concrete Superintendent and Technical Superintendert-Concrete. On July 16, after resolution of the basemat issue, Work Hold Agreement #05 was released and concrete placement was resumed in the Reactor Building.
July.
An audit was performed by 2GSE QA on concrete placement activities during The audit determined that the quality program for the proper placement and consolidation of safety related concrete is adequate and is being effectively implemented. In addition, on-going surveillances are being made of individual concrete pours.
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