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| {{#Wiki_filter:s*s , 7 h&w>*(412) 471-4300 435 Sixth Avenue | | {{#Wiki_filter:s s |
| *Pittsburgh, Pennsylvania 15219 November 19, 1979 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION: Mr. Boyce H. Grier, Director
| | 7 h&w> |
| | (412) 471-4300 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 November 19, 1979 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION: Mr. Boyce H. Grier, Director |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Significant Deficiency 79- J3 Gentlemen: | | Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Significant Deficiency 79- J3 Gentlemen: |
| On November 2,1979, Duquesne Light Company, in accordance with the requirement of 10CFR50.55(e), notified your office of the omission of reinforcing steel in the containment crane wall of Beaver Valley Power Station Unit #2. | | On November 2,1979, Duquesne Light Company, in accordance with the requirement of 10CFR50.55(e), notified your office of the omission of reinforcing steel in the containment crane wall of Beaver Valley Power Station Unit #2. Following our notification, we received your action letter of November 7,1979. This letter is to confirm our completion of the items / plan listed in that action letter. |
| Following our notification, we received your action letter of November 7,1979. | | To organize our response, we have utilized the same paragraph numbers as shown in your letter for our direct response actions and include a summary of our conclusions and the corrective action we intend to imple-ment. |
| This letter is to confirm our completion of the items / plan listed in that action letter. | | : 1) The localized crane wall "stop Work" order of October 23, 1979, was expanded to stop work on all Category I concrete placements November 7, 1979 (DLC-SQCL-#0592A). |
| To organize our response, we have utilized the same paragraph numbers as shown in your letter for our direct response actions and include a summary of our conclusions and the corrective action we intend to imple-ment.1) The localized crane wall "stop Work" order of October 23, 1979, was expanded to stop work on all Category I concrete placements November 7, 1979 (DLC-SQCL-#0592A). | | : 2) A detailed Field Construction Prom 'ure (FCP-ll3) " Removing Sec-tion of Reactor Containment Crane M '1" was issued November 2, 1979. This procedure reflects the disposition of N&D #1159 and will be amended as required for each stage of the repair work as the disposition of the N&D is expanded. |
| : 2) A detailed Field Construction Prom 'ure (FCP-ll3) " Removing Sec-tion of Reactor Containment Crane M '1" was issued November 2, 1979.This procedure reflects the disposition of N&D #1159 and will be amended as required for each stage of the repair work as the disposition of the N&D is expanded. | | : 3) Quality Control activities are already in process during this stage of the repairs. Their activities are governed by Inspection Report N&D #1159A. This Inspection Report will also be amended to be compatible with the various stages of the disposition instruc-tions as they are obtained. |
| : 3) Quality Control activities are already in process during this stage of the repairs. Their activities are governed by Inspection Report N&D #1159A. | | 1391 119 79112 e0 301 |
| This Inspection Report will also be amended to be compatible with the various stages of the disposition instruc-tions as they are obtained. | | .3 |
| 1391 119.79112 e0 301 | | |
| .3 | | Page 2 November 19, 1979 |
| ..Page 2 November 19, 1979
| | : 4) A review of the drawings and Inspection Reports related to the crane wall placement has been made. This was a detailed review of all drawings affecting the erection of the crane wall. Two separate teams were formed performing the review independently of each other; one team from DLC-SQC and one team from a com-bined construction group, each team consisting of three pairs of reviewers. |
| : 4) A review of the drawings and Inspection Reports related to the crane wall placement has been made. | |
| This was a detailed review of all drawings affecting the erection of the crane wall. | |
| Two separate teams were formed performing the review independently | |
| -of each other; one team from DLC-SQC and one team from a com-bined construction group, each team consisting of three pairs of reviewers.
| |
| Resulting from this review, we found that the specific problem | | Resulting from this review, we found that the specific problem |
| 'of the relationship betweea the elevation stated on the fab-ricator's drawings, detailing the rebar and the rebar requirements shown for specific elevations on the engineering drawings, had occurred once before, and reported on cur N&D #710 dated August 16, 1978.This.rebar omission was evaluated by the engineers and the condition was found acceptable. | | 'of the relationship betweea the elevation stated on the fab-ricator's drawings, detailing the rebar and the rebar requirements shown for specific elevations on the engineering drawings, had occurred once before, and reported on cur N&D #710 dated August 16, 1978. This.rebar omission was evaluated by the engineers and the condition was found acceptable. This earlier N&D was considered an isolated case and consequently, was not subject to trend analysis. An additional similar rebar " elevation" definition pro-blem was found applying to an area not yet placed at the same ele-vation as that reported on N&D #1159 which was the subject of 10CFR50.55(e) action. |
| This earlier N&D was considered an isolated case and consequently, was not subject to trend analysis. An additional similar rebar " elevation" definition pro-blem was found applying to an area not yet placed at the same ele-vation as that reported on N&D #1159 which was the subject of 10CFR50.55(e) action. | | This review, however, was not limited to a search for identical problems, but was conducted to identify all differences between the fabricator's and engineers' drawings. This review has resulted in eight additional discrepancies, seven of which were resolved prior to or during the review, and one which has not yet been resolved. |
| This review, however, was not limited to a search for identical problems, but was conducted to identify all differences between the fabricator's and engineers' drawings. | |
| This review has resulted in eight additional discrepancies, seven of which were resolved prior to or during the review, and one which has not yet been resolved. | |
| The unresolved problem relates to sets of three #7 dowels from the crane wall to each stairwell wall required by the engineers' drawing with sets of two #7 dowels required by the fabricator's drawing for the North stairwell wall. | | The unresolved problem relates to sets of three #7 dowels from the crane wall to each stairwell wall required by the engineers' drawing with sets of two #7 dowels required by the fabricator's drawing for the North stairwell wall. |
| There is some evidence that the dowels in question were installed in accordance with the engineers' drawings but the Inspection Report, although very detailed in its content, does not specifi-cally reference the applicable engineers' drawing that shows these dowels. | | There is some evidence that the dowels in question were installed in accordance with the engineers' drawings but the Inspection Report, although very detailed in its content, does not specifi-cally reference the applicable engineers' drawing that shows these dowels. |
| : 5) The Inspection Procedure IP-6.2.3, effective date November 15, 1979, has been amended to clarify the application of the fabrica-. tor's and engineers' drawings during the inspection. | | : 5) The Inspection Procedure IP-6.2.3, effective date November 15, 1979, has been amended to clarify the application of the fabrica- |
| : 6) Additional training to the QC Inspectors has been given and recorded.fhis training emphasized the application of the two types of drawings during the inspection required by IP-6.2.3. | | . tor's and engineers' drawings during the inspection. |
| | : 6) Additional training to the QC Inspectors has been given and recorded. fhis training emphasized the application of the two types of drawings during the inspection required by IP-6.2.3. |
| 7)' Two audits of the S&W design verification and drawing checking system were performed, one by DLC-QA and one by S&W Engineering. | | 7)' Two audits of the S&W design verification and drawing checking system were performed, one by DLC-QA and one by S&W Engineering. |
| a) The QA audit was set up to determine the adequacy of the 1391 120 | | a) The QA audit was set up to determine the adequacy of the 1391 120 |
| ., Page 3 November 19, 1979 original drawing verification program.
| | |
| The review was performed on 59 Engineers' drawings and 47 Fabricator's drawings, covering 11 basic areas of activity -- 4 areas of the Containment, 3-- Auxiliary Building, 2 - Service Building, and one each for the Main Steam Cable Vault and Fuel and Decontamination Building. | | Page 3 November 19, 1979 original drawing verification program. The review was performed on 59 Engineers' drawings and 47 Fabricator's drawings, covering 11 basic areas of activity -- 4 areas of the Containment, 3-- Auxiliary Building, 2 - Service Building, and one each for the Main Steam Cable Vault and Fuel and Decontamination Building. The results of this review indicate that the original drawing verifica-tion was satisfactory. |
| The results of this review indicate that the original drawing verifica-tion was satisfactory. | | b) S&W Engineering conducted a review comparing the title block elevation with the actual rebar content to establish whether similar problems regarding elevation definition occurred elsewhere. The review was applied to over 200 drawings and covered the Reactor Containment, Safeguards Building, Fuel and Decontamination Building, and Service Building. No further instances other than the three cases reported in Paragraph 4 were found. |
| , b) S&W Engineering conducted a review comparing the title block elevation with the actual rebar content to establish whether similar problems regarding elevation definition occurred elsewhere.
| | CONCLUSIONS Our investigation has led us to conclude that: |
| The review was applied to over 200 drawings and covered the Reactor Containment, Safeguards Building, Fuel and Decontamination Building, and Service Building.No further instances other than the three cases reported in Paragraph 4 were found. | |
| CONCLUSIONS | |
| 'Our investigation has led us to conclude that:
| |
| a) Design changes were not incorporated into the affected fabricator's drawings applicable to the area of concern if the fabrication had either started or had been completed. | | a) Design changes were not incorporated into the affected fabricator's drawings applicable to the area of concern if the fabrication had either started or had been completed. |
| b) Field reviews of the fabricator's drawings and supplementary infor- | | b) Field reviews of the fabricator's drawings and supplementary infor-mation performed by the engineers and installer were not adequately formalized. |
| -mation performed by the engineers and installer were not adequately formalized. | | c) Inspection Plans and construction instructions were not definitive with reference to the use of the engineers' latest design drawing to be used in the final pre-pour check. |
| c)Inspection Plans and construction instructions were not definitive with reference to the use of the engineers' latest design drawing to be used in the final pre-pour check. | |
| CORRECTIVE ACTION a) S&W has instructed the fabricator to assure that in the future that the detailed drawing title accurately describes the area detailed on that sheet and that proper references be made to other detailed drawings covering the same or adjacent areas. | | CORRECTIVE ACTION a) S&W has instructed the fabricator to assure that in the future that the detailed drawing title accurately describes the area detailed on that sheet and that proper references be made to other detailed drawings covering the same or adjacent areas. |
| b) Field Construction Procedure 118, " Engineer Review of Rebar Fabrication Drawings", has been issued to formalize the review program to be applied by engineering on all rebar fabrication | | b) Field Construction Procedure 118, " Engineer Review of Rebar Fabrication Drawings", has been issued to formalize the review program to be applied by engineering on all rebar fabrication |
| ~ drawings. | | ~ drawings. |
| c) Field Construction Procedure 119, " Placement of Refinforcing Steel" and IP-6.2.3, " Pre-Placement, Placement and Post-Placement of Con-crete", have been amended to clarify and emphasize the use of both the fabricator's and engineers' drawings with reference to installa-tion and final pre-pour check. | | c) Field Construction Procedure 119, " Placement of Refinforcing Steel" and IP-6.2.3, " Pre-Placement, Placement and Post-Placement of Con-crete", have been amended to clarify and emphasize the use of both the fabricator's and engineers' drawings with reference to installa-tion and final pre-pour check. |
| 1391 121. | | 1391 121 |
| .*.Page 4 November 19, 1979 In accordance with yo':r request, we will await your concurrence with our plans to suspend our Stop Work Order and resumption of concrete placement activities.
| | |
| -Very truly~yours,-.E.. WOOLEVER Vice President COPIES TO:
| | Page 4 November 19, 1979 In accordance with yo':r request, we will await your concurrence with our plans to suspend our Stop Work Order and resumption of concrete |
| Dr. V.Stello (15) | | - placement activities. |
| Mr. W.G. Mcdonald (1) 1391 122.}} | | Very truly~yours, E. . WOOLEVER Vice President COPIES TO: Dr. V. Stello (15) |
| | Mr. W. G. Mcdonald (1) 1391 122 |
| | .}} |
Final Deficiency Rept Re Significant Deficiency 79-03: Omission of Reinforcing in Containment Crane Wall.Facility Will Await NRC Concurrence W/Plans to Suspend Stop Work Order & Resumption of Concrete PlacementML19210D323 |
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Site: |
Beaver Valley |
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Issue date: |
11/19/1979 |
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From: |
Woolever E DUQUESNE LIGHT CO. |
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To: |
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References |
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NUDOCS 7911260302 |
Download: ML19210D323 (4) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-041, Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods1998-03-0909 March 1998 Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods L-97-059, Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 9802151997-11-14014 November 1997 Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 980215 ML20141K7741997-04-24024 April 1997 Part 21 Rept Re Auxiliary Feedwater Check Valve Failure. 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Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20072S4611994-09-0505 September 1994 Part 21 Rept Re Ssps semi-automatic Tester at Plant ML20073S9541994-06-27027 June 1994 Part 21 Rept Re Incorrect Matl Supply Discovered on Unshipped Order.Pump Div Will Notify Enertech W/ Recommendation That Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20070A1441994-06-22022 June 1994 Part 21 Rept Re Conditions Which Affect Hydraulic Valve Operators Supplied by Bw/Ip to Enertech Co & Listed Utils. 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Customers Should Order Air Filters Mfg After Nov 1989 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 ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20116D1241992-10-29029 October 1992 Supplemental Part 21 Rept Re Byron Jackson River Water Pump Couplings.Initially Reported on 921101.Caused by Lack of Matl Toughness.Replacement Couplings Were Screened to Insure Adequate Toughness & Purchase Spec Amended ML20101R3691992-07-0707 July 1992 Final Part 21 Rept Re Failure of Byron Jackson River Water Pump Couplings.Initially Reported on 911121.Couplings Failed in Svc Due to Lack of Toughness.Couplings Examined & Suspect Matl Removed from Svc ML20079L8031991-11-0101 November 1991 Part 21 Rept Re 910620 Failure of Coupling in River Water Pump 1A Supplied by Byron Jackson.Caused by Mechanical Failure of Shaft Coupling.Metallurgical Analysis of Suspect Coupling Will Be Performed & Couplings Replaced ML20082P6871991-09-0404 September 1991 Revised Part 21 Rept Re Failure of Crosby Spring Relief Valves During Testing.Valve Prematurely Lifted During Sixth & Seventh Refueling Outages Due to Use of Stainless Instead of Carbon Steel.Springs,W/New Matl,Installed at Facility ML20077L5661991-08-0505 August 1991 Part 21 Rept Re Crosby Spring Relief Valve Failures Experienced During Testing at Facility.Evaluation Conducted to Determine If Safety Hazard Could Exist.Spring Changed to ASTM-A638 Grade 660,correcting Problem at Facility ML20055E8221990-07-0505 July 1990 Part 21 Rept Re Abb 27/59 Relays Deteriorated Due to Thermal Stress.Initially Reported on 900222.Units W/Listed Identification Numbers to Be Inspected & Replaced If Signs of Overheating Present ML20043A8491990-05-11011 May 1990 Part 21 Rept Re Contactors Used on Diesel Generator Immersion Heater Mfg by Cutler-Hammer.All Contactors W/Date Code Before 890522 Suspect.Dimensions Changed to Correct Problem.Formal Rept Will Be Sent Next Wk ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20236C7981987-10-22022 October 1987 Part 21 Rept Re Defect Concerning Modulating Solenoid Valve Supplied by Target Rock Corp.Valve Has Been Reassembled Using Proper Spiral Pin ML20237H8281987-08-0707 August 1987 Final Potential Significant Deficiency Rept 87-18 Re Failure of Emergency Switchgear & Diesel Generator Room Supply Fans to Start by Actuation of Switches on Alternate Shutdown Panel.Initially Reported on 870803.Control Switch Replaced ML20235M3651987-07-0101 July 1987 Deficiency Rept 87-09 Re Linear Indication on Reactor Vessel Weld.Initially Reported on 870301. Boat Sample Removed by Westinghouse for Vertical Linear Indication.No Addl Repts Anticipated ML20235H1811987-06-17017 June 1987 Final Deficiency Rept 87-16 Re Improper Installation of Bisco LOCA Seals in Conduits Containing Rockbestos Cable. Initially Reported on 870518.Rework on All Seals Completed ML20215C5771987-06-10010 June 1987 Part 21 Rept Re Small Leak in Unit B Cooling Water Header Lower Pipe in Right Bank of Emergency Diesel Generators. Affected Water Header Pipes Replaced W/Upgraded Matl & Unit a Water Header Pipes Visually Inspected for Leakage ML20215A9951987-06-0202 June 1987 Potential Significant Deficiency Rept 87-15 Re Failure of Main Steam Valve Area Supply Fans to Start Automatically. Initially Reported on 870508.Diesel Sequencer Interlock Rewired to Open Dampers.No Addl Repts Anticipated ML20215B0511987-06-0202 June 1987 Significant Deficiency Rept 87-14 Re Lack of Documentation Certifying Modes 5 & 6 N-1 Operation.Initially Reported on 870507.Appropriate Documentation Expected to Be in Place When Full Power License Received.No Addl Repts Required ML20215A3451987-05-29029 May 1987 Final Deficiency Rept 87-10 Re Linear Indications Identified During Preservice Insp of Reactor Vessel Studs.Initially Reported on 870501.Corrective Actions Include Blending/ Grinding of Surface Indications to Remove Distress Marks ML20214U9511987-05-28028 May 1987 Revised Final Deficiency Rept 87-08 Re Containment Isolation Phase B-initiated Timers for Control Room Emergency Pressurization Fans.Initially Reported on 870327.Correct Date for Completion Is 870504 Instead of 870411 ML20216C9341987-05-28028 May 1987 Potential Significant Deficiency Rept 86-14 Re Outside Containment Flood Analysis.Initially Reported on 860917. Outside Flood Analysis Calculation Revised to Elevate Lines Previously Exempted from Analysis ML20214J4911987-05-25025 May 1987 Interim Significant Deficiency Repts 87-16 & 87-17 Re Conduit Sealing of 50 Class 1E Items.All Physical Work Re Re Environ Qualification Program Complete W/Exception of Four Bisco Seals ML20214V0571987-05-21021 May 1987 Final Significant Deficiency Rept 87-07 Re High Head Safety Injection/ Charging Pump Operating Below Min Operating Curve.Initially Reported on 870323.Pump Rotating Assembly Replaced W/Spare Rotating Assembly & Satisfactorily Tested ML20214H4091987-05-14014 May 1987 Final Deficiency Rept 87-13 Re Pressure Locking & Thermal Binding of Westinghouse Gate Valves.Initially Reported on 870415.S&W Review Resulted in Initiation of Advance Change Notice D-0266 to Correct Discs in 10 Valves 1998-09-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
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(412) 471-4300 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 November 19, 1979 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION: Mr. Boyce H. Grier, Director
SUBJECT:
Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Significant Deficiency 79- J3 Gentlemen:
On November 2,1979, Duquesne Light Company, in accordance with the requirement of 10CFR50.55(e), notified your office of the omission of reinforcing steel in the containment crane wall of Beaver Valley Power Station Unit #2. Following our notification, we received your action letter of November 7,1979. This letter is to confirm our completion of the items / plan listed in that action letter.
To organize our response, we have utilized the same paragraph numbers as shown in your letter for our direct response actions and include a summary of our conclusions and the corrective action we intend to imple-ment.
- 1) The localized crane wall "stop Work" order of October 23, 1979, was expanded to stop work on all Category I concrete placements November 7, 1979 (DLC-SQCL-#0592A).
- 2) A detailed Field Construction Prom 'ure (FCP-ll3) " Removing Sec-tion of Reactor Containment Crane M '1" was issued November 2, 1979. This procedure reflects the disposition of N&D #1159 and will be amended as required for each stage of the repair work as the disposition of the N&D is expanded.
- 3) Quality Control activities are already in process during this stage of the repairs. Their activities are governed by Inspection Report N&D #1159A. This Inspection Report will also be amended to be compatible with the various stages of the disposition instruc-tions as they are obtained.
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Page 2 November 19, 1979
- 4) A review of the drawings and Inspection Reports related to the crane wall placement has been made. This was a detailed review of all drawings affecting the erection of the crane wall. Two separate teams were formed performing the review independently of each other; one team from DLC-SQC and one team from a com-bined construction group, each team consisting of three pairs of reviewers.
Resulting from this review, we found that the specific problem
'of the relationship betweea the elevation stated on the fab-ricator's drawings, detailing the rebar and the rebar requirements shown for specific elevations on the engineering drawings, had occurred once before, and reported on cur N&D #710 dated August 16, 1978. This.rebar omission was evaluated by the engineers and the condition was found acceptable. This earlier N&D was considered an isolated case and consequently, was not subject to trend analysis. An additional similar rebar " elevation" definition pro-blem was found applying to an area not yet placed at the same ele-vation as that reported on N&D #1159 which was the subject of 10CFR50.55(e) action.
This review, however, was not limited to a search for identical problems, but was conducted to identify all differences between the fabricator's and engineers' drawings. This review has resulted in eight additional discrepancies, seven of which were resolved prior to or during the review, and one which has not yet been resolved.
The unresolved problem relates to sets of three #7 dowels from the crane wall to each stairwell wall required by the engineers' drawing with sets of two #7 dowels required by the fabricator's drawing for the North stairwell wall.
There is some evidence that the dowels in question were installed in accordance with the engineers' drawings but the Inspection Report, although very detailed in its content, does not specifi-cally reference the applicable engineers' drawing that shows these dowels.
- 5) The Inspection Procedure IP-6.2.3, effective date November 15, 1979, has been amended to clarify the application of the fabrica-
. tor's and engineers' drawings during the inspection.
- 6) Additional training to the QC Inspectors has been given and recorded. fhis training emphasized the application of the two types of drawings during the inspection required by IP-6.2.3.
7)' Two audits of the S&W design verification and drawing checking system were performed, one by DLC-QA and one by S&W Engineering.
a) The QA audit was set up to determine the adequacy of the 1391 120
Page 3 November 19, 1979 original drawing verification program. The review was performed on 59 Engineers' drawings and 47 Fabricator's drawings, covering 11 basic areas of activity -- 4 areas of the Containment, 3-- Auxiliary Building, 2 - Service Building, and one each for the Main Steam Cable Vault and Fuel and Decontamination Building. The results of this review indicate that the original drawing verifica-tion was satisfactory.
b) S&W Engineering conducted a review comparing the title block elevation with the actual rebar content to establish whether similar problems regarding elevation definition occurred elsewhere. The review was applied to over 200 drawings and covered the Reactor Containment, Safeguards Building, Fuel and Decontamination Building, and Service Building. No further instances other than the three cases reported in Paragraph 4 were found.
CONCLUSIONS Our investigation has led us to conclude that:
a) Design changes were not incorporated into the affected fabricator's drawings applicable to the area of concern if the fabrication had either started or had been completed.
b) Field reviews of the fabricator's drawings and supplementary infor-mation performed by the engineers and installer were not adequately formalized.
c) Inspection Plans and construction instructions were not definitive with reference to the use of the engineers' latest design drawing to be used in the final pre-pour check.
CORRECTIVE ACTION a) S&W has instructed the fabricator to assure that in the future that the detailed drawing title accurately describes the area detailed on that sheet and that proper references be made to other detailed drawings covering the same or adjacent areas.
b) Field Construction Procedure 118, " Engineer Review of Rebar Fabrication Drawings", has been issued to formalize the review program to be applied by engineering on all rebar fabrication
~ drawings.
c) Field Construction Procedure 119, " Placement of Refinforcing Steel" and IP-6.2.3, " Pre-Placement, Placement and Post-Placement of Con-crete", have been amended to clarify and emphasize the use of both the fabricator's and engineers' drawings with reference to installa-tion and final pre-pour check.
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Page 4 November 19, 1979 In accordance with yo':r request, we will await your concurrence with our plans to suspend our Stop Work Order and resumption of concrete
- placement activities.
Very truly~yours, E. . WOOLEVER Vice President COPIES TO: Dr. V. Stello (15)
Mr. W. G. Mcdonald (1) 1391 122
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