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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20135D4261997-01-31031 January 1997 Criticality Analysis of Beaver Valley Unit 1 Fresh Fuel Racks ML20236W7411996-12-30030 December 1996 Rev 1,change 1 to Performance Demonstration Initiative (PDI) Program Description ML20196B8951996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961216 Between Cleveland Electric Illuminating Co & Mellon Bank ML20196B8771996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961231 Between Toledo Edison Co & Mellon Bank ML20195C9891996-10-0404 October 1996 BVPS-2 Containment Penetrations Overpressure Protection Analysis/Review Rept ML20116J0771996-07-31031 July 1996 Rev 1 to Beaver Valley Unit 1 1996 Alternate Repair Criteria 90 Day Rept ML20116H9821996-06-30030 June 1996 Fitness-For-Duty Program for Jan-June 1996 ML20097C8371996-01-31031 January 1996 USI A-46 Seismic Evaluation Rept for BVPS Unit 1 ML20097C8431996-01-31031 January 1996 USI A-46 Relay Evaluation Rept for BVPS Unit 1 ML20095J6361995-12-31031 December 1995 BVPS Unit 2 Simulator Four Yr Certification Rept 1992 - 1995 ML20196B7871995-04-21021 April 1995 Pennsylvania Power Co Master Decommissioning Trust Agreement for Beaver Valley Power Station & Perry Nuclear Power Plant ML20087G1101995-02-28028 February 1995 Interim Plugging Criteria Return to Power Ltr Rept ML20080Q3441995-02-23023 February 1995 Protection Against Malevolent Use of Vehicles at Nuclear Power Plants ML20078Q5271994-12-13013 December 1994 Simulator Four Yr Certification Rept 1991-94 ML20196B8501993-07-0101 July 1993 Ohio Edison Co Master Decommissioning Trust Agreement for Perry Nuclear Power Plant Unit One,Perry Nuclear Power Plant Unit Two,Beaver Valley Power Station Unit One & Beaver Valley Power Station Unit Two ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20116G5891992-09-28028 September 1992 SFP Mod for Increased Storage Capacity BVPS Unit 1 ML20090M5281992-03-17017 March 1992 Rev 0 to PRA Individual Plant Exam Summary Rept ML20100P9581992-01-27027 January 1992 Rev 0 to Assessment of Doses in Unit 2 Control Room Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel ML20090B3081991-12-31031 December 1991 Control Room X/Q Values for Beaver Valley Power Station ML20087A1661991-12-30030 December 1991 Simulator Certification Rept,Beaver Valley Power Station, Unit 2 ML20094G7521991-09-0404 September 1991 Offsite Dose Consequences of Locked Rotor Accident at Unit 2 w/18% Failed Fuel Analysis ML20079L1761991-08-31031 August 1991 Plant Safety Evaluation for Beaver Valley Power Station, Unit 2,VANTAGE 5H Fuel Upgrade, for Aug 1991 ML20079A9671991-05-31031 May 1991 Evaluation of Adequacy of Existing Neutron Flux Instrumentation for NUREG-0737,Suppl 1 ML20067E4001991-01-17017 January 1991 Evaluation of Main Feedwater Piping Misalignment & Steam Generator Nozzle Cracking Final Rept ML20066C4861990-12-18018 December 1990 Simulator Certification Rept ML20077Q3241990-11-30030 November 1990 Development of Pressure-Temp Limit Curves for Loop Isolated from Reactor Vessel:Beaver Valley Units 1 & 2 ML20246E8281989-05-0404 May 1989 Dcrdr Second Supplemental Summary Rept ML20246K4541989-04-30030 April 1989 Plant Safety Evaluation for Beaver Valley Power Station Unit 1 Fuel Upgrade & Increased Peaking Factors. Related Info,Including Recommended Mods to Facility Fsar,Encl ML20065G8721988-08-23023 August 1988 Moisture Separator-Reheater Status Rept ML20153G2581988-03-31031 March 1988 Criticality Analysis of Beaver Valley Unit 2 Fuel Racks ML20195H7371988-01-0505 January 1988 Dcrdr Supplemental Rept ML20239A0111987-06-30030 June 1987 Mellon Bank Corp 1987 Second Quarter Rept ML20239A0251987-06-30030 June 1987 Pnc Financial Corp Rept to Shareholders Second Quarter 870630 ML20239A0061987-06-30030 June 1987 First Chicago Corp 1987 Second Quarter Rept ML20215D8941987-06-11011 June 1987 Technical Review Rept,Nrc Region I Insp 50-412/87-34,Review of Beaver Valley Power Station Unit 2 Tech Specs,Onsite Activities Conducted 870330-0410 ML20214V1921987-05-31031 May 1987 Evaluation of RCS for Elimination of Primary Component Support Snubbers ML20214V1951987-05-31031 May 1987 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices ML20214K3491987-05-11011 May 1987 Engineering Assurance Corrective Action Status Rept, In-Depth Technical Audits ML20206E4731987-03-31031 March 1987 Nonproprietary Addl Info on Beaver Valley Power Station Unit 2 SER Confirmatory Issue 032 ML20206T0791987-03-31031 March 1987 Amend 5 to Failure Modes & Effects Analyses Rept ML20205F9881987-03-26026 March 1987 Rev 1 to Books 1-3 to Mechanical Equipment Qualification File 651-01, Environ Qualification of Mechanical Equipment ML20205G0221987-03-24024 March 1987 Rev 4 to Mechanical Equipment Qualification File 091-01 to Environ Qualification of Mechanical Equipment. W/Four Oversize Encls ML20205G0311987-03-24024 March 1987 Rev 5 to Mechanical Equipment Qualification File 001-09 to Environ Qualification of Mechanical Equipment ML20214R2641987-03-13013 March 1987 Draft SER Addressing Qualification & Documentation of Isolators as Acceptable Interface Devices Between Class 1E Instrumentation & non-Class 1E Spds,Per NUREG-0737,Suppl 1. Devices Acceptable ML20207Q0311987-01-31031 January 1987 Dcrdr Supplemental Summary Rept 1999-01-28
[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
[Table view] |
Text
L ENGINEERING ASSURANCE CORRECTIVE ACTION STATUS REPORT IN-DEPTH TECHNICAL AUDITS BEAVER VALLEY UNIT 2 PROJECT DUQUESNE LIGHT COMPANY May 11, 1987 W.A
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4 R.W. Twigg, Jrf M
W.M. Eifere' Audit Team Leader Chief Engineer Engineering Assurance 87-EA-001/EA294 0705280413 070520 PDR ADOCK 03000412 A PDR
1.0 INTRODUCTION
1.1 General I
This report provides the status of corrective action items resulting from an In-Depth Technical Audit of Beaver Valley Unit 2 Project.
1.2 Background
The Audit identified as Project Audit No. 52, and discussed here-in, was a multi-discipline in-depth technical audit i performed to assess the adequacy and implementation of the design process by evaluating the design of the Safety Injection
' System (SIS), related portions of the Recirculation Spray System
! (RSS), and interface aspects of other fluid systems, structures, and electrical systems and components. This audit was performed i
in conjunction with NRC overview. Details of the audit
, findings, Project responses, and corrective and preventive actions are documented in Reference 1.3.1. Project Audit No. 52 l was the last in a series of four In-Depth Technical Audits. A i
subsequent Report (Reference 1.3.2) presents an analysis of the results of all four audits, and discusses the adequacy and implementation of the design process.
t i
1.3 References i
1.3.1 Engineering Assurance Technical Audit Report. Beaver Valley ,
Unit 2 Project, Audit No. 52, August 15, 1986. I I 1.3.2 Phase 11 Report for Evaluation of In-Depth Technical Audit Results, Beaver Valley Unit 2 Project, December 16, 1986.
1.3.3 USNRC, Office of Inspection and Enforcement Inspection Report 50-412/86-23 September 24, 1986. i 1.3.4 Engineering Assurance Corrective Action Audit of Control Systems Setpoint Verification Calcuintions, Beaver Valley Unit 2 l Project, December 17, 1986.
I 1.3.5 Engineering Assurance Corrective Action Status Report In-Depth i Technical Audits, Beaver Valley Unit 1 Proj ect , February 12, i 1987.
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2.0 ACTION ITEM STATUS
SUMMARY
Table 2-1 identifies each Action Item, and its associated type code, resultant code, and status. Table 2-2 presents the definitions of these codes.
All of the Action Items have been closed. The closure of the Action Items was based on the Audit Team's verification of the Project's corrective and preventive actions. For activities with extended corrective action programs, the closure was based on the verification of a sample of documents completed at that time.
In addition, all of the Action Items associated with the Corrective Action Audit of Control Systems Setpoint Verification Calculations (Reference 1.3.4) have been closed.
The audit team has verified that all Licensing Change Notices (LCNs) resulting from the audit have been appropriately incorporated into the FSAR, with the exception of the LCN-1750.
LCN-1750 involved editorial changes to responses to NRC Questions 271.1, 271.2, 271.8, and 271.9 (Action Item M01). In the February Licensing Meeting, DLC advised the Project that changes to NRC questions beyond FSAR Amendment 15 would not be incorporated into the FSAR. As a result of this action.
LCN-1750 has been cancelled. This action is acceptable to the Audit Team as the changes in LCN-1750 merely restated the deleted references to FSAR Tables 3.9B-4 and 3.9B-12 and has no impact as to its technical adequacy.
87-EA-001/EA294 2
TABLE 2-1 ACTION ITEM IDENTIFICATION AND CLASSIFICATION CONTROLS Number Subject Tyge Resultant Status C01 Consistency Between FSAR Section 7.1.2.5 A L C and Table 1.8-1 l
CO2 Consistency Between SWEC and W Documents B NA C C03 Clarification in FSAR Table 1.8-1 A L C t
C04 Documents Affected by Removal of Boron B NA C Dilution Protection Alarm C05 Consistency Between SWEC and W Elementaries B NA C j C06 References in FSAR Table 1.8-1 A L C i
C07 Inconsistencies in FSAR for R.G. 1.118 A L C C08 Consistency Between SWEC and W Documents B NA C i
C09 Solenoid Valves Shown Incorrectly A D C C10 Incorrect Wiring Diagram in Instrument Index A D C C11 RSS Starting Time Consistent in the FSAR B NA C C12 Justification of Setpoint Calculation Method A D C Cl3 Setpoint Calculation Preparation Guidance B NA C C14 Setpoint Calculation Confirmation B NA C C15 Incorrect Reference on Isometric Drawing B NA C
- C16 PAM Instrument Identification Consistency A D C C17 Copper Tube Vents on 3-Way SOVs A H C NOTE
- See Table 2-2 for definitions of Type, Resultant and Status Codes
- Indicates change in Type and/or Resultant Code from that indicated in Table 4-1 of Reference 1.3.1.
2-1-1
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I CONTROLS (Continued) i f Number Subject Typet Resultant Status
! C18 Pressure Transmitters on SIS Accumulator A C .C I
Tank Incorrectly Tagged C19 Flex Hose Extends Into Passageway B* NA* C J
C20 Instrument Stand Rigidity A H* C(5) i C21 Elementary Diagram Referenced E&DCR Prior A D C-l to Issue C22 FSAR/ Logic Consistency A L C l
l C23 Instrument Range Consistency A D C C24 Specification 2BVS-648A Incomplete Data A D C I A D C C25 Shut-off Pressure Listed Inconsistently C26 Interpretation of Line Slope Symbol on B NA C-Isometric Drawing -
C27 Elevation of 2RSS*FT157D Shown Inconsistently A D C i
on Instrument Drawings i
C28 Flow Element Identification Drawings B NA. C C29 Isolator on Impulse Lines B NA C
! C30 Color Code Designation Consistency A ,D C i
! C31 Weight of D/P Switches Listed Inconsistently B NA C-i j C32 Grounding or Shielding Requirements on Vendor B NA C i Documents I
i C33 Instrument Tube Slope Requirements B NA C
! C34 Weights and Shielding not Shown on Vendor B NA C Documents
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C35 Defining " Hand-Tight" Requirements B NA C
! C36 Loop Diagram Symbol A D C i
C37 Documentation for Scale Range B NA C
! C38 Elementary Diagram References and Wire Numbers A D C 1
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2-1-2 ,
l
1 CONTROLS (Continued)
Nurber Subject Tyjge Resultant Status Cb9- ' Elementary Diagram Reference and Wire Number A D C C40 Set Point Calculation Errors A D* C C41 Elementary Diagram References and Torque A D C Switch Wiring C42 References within N&D 15602B A C C C43 Relief Valve Set Pressures B NA C C44 Specification 2BVS-657 Environmental Conditions B NA C C45 FSAR Consistencies Concerning Isolation Valves A L C The following Action Items are from the Corrective Action Audit of Control Systems Setpoint Verification Calculations (Reference 1.3.4).
CA01 Calculation 12241-FWE*6-1-C Identification B NA C of Setpoint Limits CA02 Calculations 12241-CCP*3-0-C and CCP*20-1-C A D C Radiation Effects CA03 Calculation 12241-SWS*12-2-C RTD Accuracy B NA C CA04 Calculation 12241-SWS*12-2-C RTD Seiswie A D C Error CA05 Calculation 12241-HVD*3-3-C Switch B NA C Repeatability CA06 Calculation 12241-SP-2CCP-1 Setpoint Bases A D C 1
87-EA-001/ EA294 2-1-3
TABLE 2-1
' ACTION ITEM IDENTIFICATION AND CLASSIFICATION ,
! ELECTRICAL.
. Number Subject Tyjge Resultant Status E01 One Line Diagram Circuit Identification A D C
! E02 MOV Motor Voltage Qualification B NA C
! E03 Submergence of MOV Limit Switches B* NA* C E04 Verification of Cable Flame Test A L* C EOS Design Criteria Separation Requirement .A D,L C E06 Equipment Qualification Temperature A D C E07 Battery Cell Temperature Justification B* - NA* C E08 Battery Room Ventilation - FSAR A L,C C E09 Electrical Penetration Separation - FSAR A L C ,
E10 Radiation Level for Equipment Qualification .A D C Eli Battery Charger Rating A D C I
E12 Battery Charger Vendor Data B NA C E13 Wiring Symmetry Between Trains B* NA* C 5* E14 Temporary Equipment in Battery Room A C C 4 EIS Cable Wraps - Battery Room A D C
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E16 Lighting Fixture Seismic Qualification A P,D* C
- E17 Battery Room Ventilation - Temporary B NA - C 4 E18 Fire Fighting Access - Cablo. Tunnel B NA. C.
E19 Green Circuit Separation - Criteria A D. C' E20 4KV Service - Sleeve Grounding B NA C ,
E21 Damaged Conduit A P ,H* (l) C E22 Specification ~ Reference A D C 2-1-4
._. . . . - - - , - . . - _ - , , _ , _ _ . . . . . , , , .y. . _ ,_ . _ . _ _ . . .
ELECTRICAL (Continued)
Number- Subject Tyge Resultant Status E23 N&D Cable Pull Calculation Error A D C E24 Cable Tray Arrangement Drawing Consistency A D C E25 Calculation Basis Referenced A D- C E26 Calculation Assumption Justification B NA C E27 Battery Calculation Invalid Input A D* C E28 Calculation Assumption Justification B NA .C E29 Battery Charger Settings B NA C E30 Cable Coefficient of Friction A* D* C E31 Relay Coordination Curve Update A D C* C E32 Hazard Analysis Target Evaluation No. 154 B . NA C E33 Hazard Analysis Target Evaluation No. 130 A C C 3
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e TABLE 2-1 ACTION ITEM IDENTIFICATION AND CLASSIFICATION ENGINEERING MECHANICS Number Subject Tyge Resultant Status M01 FSAR Consistency A L C l M02 FSAR Consistency, Computer Programs A -L,D C M03 FSAR Consistency, Computer Programs A L,D C M04 FSAR Consistency B NA C-MOS ASME Code Applicability Dates A D C M06 HTLOAD Computer Flash Message B NA C M07 Stiff Clamp Local Stress Effects A D* C M08 Stainless / Carbon Steel Contact B NA C M09 Calculation Discrepancies A D C M10 Branch Pipe Qualification A* D*(2) C Mll Calculation Documentation A D,P C M12 Pipe Support Design Criteria Consistency A D C M13 Instrument Tubing Qualification B* NA* C M14 Tubing Calculation Update for New Isometrics B NA C M15 Pipe Clamp Application Qualification A D* C M16 Unmarked Temporary Pipe Support A C C Mi7 Calculation Input Identification A D C-M18 Parallel Snubber Load Sharing A D* C M19 Pipe Clamp Anchor Justification A D* C M20 Hydraulic Snubber Motion Qualification A D,P* C M21 N&D Documentation A C C 4
M22 Recirculation Pump Vendor Analysis B NA C 2-1-6
i ENGINEERING MECHANICS (Continued)
Number Subject Type . Resultant Status M23 Skewed T-Joint Weld Analysis A D C M24 Skewed T-Joint Weld - Standard Method Sheet B NA C M25 Pipe Support Specification Design Criteria A D C M26 Recirculation Spray Cooler Support Calculation A D C M27 Small Bore Equipment Nozzle Loads B NA C M28 Computer Model Cut Off Mode B NA C M29 Distribution of Small Bore Reports B NA C M30 Hydraulic Snubber Application B NA C M31 Invalid Flange Weights A D C 4
M32 Branch /Run Pipe Stress Intensification Factor B NA C M33 Safety /Non-Seismic Interation Criteria A D,P C M34 N&D EMD Mechanical Review B NA C M35 N&D Documentation A C C-4 2-1-7
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TABLE 2-1 ACTION ITEM IDENTIFICATION AND CLASSIFICATION POWER Number Subject Tyge Resultant Status P01 NSSS Valve Positions A D C P02 NSSS Connection Locations- B NA' C P03 Charging Pump Cubicle Access A *(3) C P04 Minimum Wall Calculation A* D* C P05 Radiation Source Term Justification B NA C P06 Camma Dose Calculation Ratio B NA C P07 FSAR/ Specification Consistency A L C P08 E&DCR Affected Documents B NA C P09 RSS Cooler Instruction Manual B NA C-P10 Flow Diagram /P&ID Consistency A- L C Pil HVAC Calculation - Relative-Humidity B NA C P12 Stress Data Package - Inputs A D C P13 Stress Data Package Inputs A D C P14 Power / Electrical Interface B NA C P15 Power / Controls Interface A D C P16 Power /EMD Pipe Stress Interface B -NA C 2-1-8
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TABLE 2-1 ACTION ITEM IDENTIFICATION AND CLASSIFICATION STRUCTURAL Number Subject Type Resultant Status S01 Cable Tray and Conduit Damping Ratio B NA C S02 Seismic Decoupling of Subsystems B NA C S03 Load Combination for T, and R, A* L* (4) C
'SO4 Steel Design Load Combinations B NA C S05 Missile Resistant Craneway Door A D C S06 Masonary Walls B NA C S07 Penetration Temperatures A L,C C S08 Charging Pump Loads A D,P C S09 Containment Penetration Construction B NA C S10 Cable Tray Support Methods B NA. C' S11 Calculation / Drawing Consistency A D C S12 Allowable Steel Stresses A D,L,P*- C S13 Steel Frame Modeling Method A D C S14 Torsion in Steel Members B NA C S15 Missile Door Vendor Calculation A D C-S16 Friction Bolts B NA C
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. TABLE 2-2 ACTION ITEM TYPE, RESULTANT AND STATUS CODES Type Codes A = Resulted in Corrective and/or Preventive Action B = Information Provided by Project Resulted in Closure without need for Project Action Resultant Codes L= FSAR Change D = Design Document Change P = Procedure Change H = Hardware Impact C = Administrative Control T = To be determined after further evaluation NA = Not Applicable Status Codes C = Closed 0 = Open Notes
- 1. The damaged electrical conduit was removed, the cable inspected and the conduit replaced.
- 2. This item was changed to indicate that corrective and preventive actions were required. Although the vent and drain piping was adequately qualified, reference to this qualification had not been included in N-5 memorandums.
- 3. The request to reroute three conduits and a drain line in two of three charging pump cubicles was presented to the BV-2 Change Control Board (CCB). The CCB concluded that this change was not required to license or operate the plant and should be reconsidered by the plant staff after commercial operation.
- 4. This item was changed to indicate that corrective action in the form of a Licensing Change Notice (LCN 1670) has been issued, consistent with the recommendation in enclosure 1 to Reference 1.3.3.
- 5. Design change documents have been prepared and verified. Completion of construction / inspection has not been confirmed.
2-2-1
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