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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20249C0011997-11-30030 November 1997 Reactor Vessel Fluence Analysis Methodology ML20148E7091997-05-31031 May 1997 Vols 1 & 2 to Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Ors,Usi A-46, Per GL 87-02 ML18151A7101996-09-30030 September 1996 Supplemental Info for VA Power Nomad Code & Model. ML20249C4051996-05-16016 May 1996 Rev 0 to CE-0082, Review of Augmented ISI Frequency for Pressurizer Spray Lines ML20249C4031996-04-23023 April 1996 Rev 0 to CE-0081, Review of Augmented ISI Frequency for Reactor Coolant Bypass Lines ML20092A2611995-08-31031 August 1995 EDG Preventive Maint Insp Outage Probabilistic Safety Assessment for August 1995 ML20078P9261994-09-26026 September 1994 Service Water System Operational Performance Assessment 940711-29 ML18153B4221993-07-31031 July 1993 Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station. ML18153B4211993-07-31031 July 1993 Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station. ML20046D1581993-02-28028 February 1993 Virginia Power Sys Transient Analysis Using Version 1 of North Anna Retran Model. ML18152A0711993-02-0101 February 1993 NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept. ML20116A2901992-09-23023 September 1992 Conceptual Engineering Final Rept NP-2653, RG 1.97 Isolation Devices Type 2,North Anna Power Station. W/One Oversize Encl ML20101B0331992-04-30030 April 1992 Suppl to Update of Settlement Monitoring Points & Graphs NAPS - Supplement to Technical Rept CE-0019,North Anna Settlement Data Oct 1989 - Apr 1992 ML20077A6601991-05-0707 May 1991 Summary Rept on Exam of Steam Generator Tube R11-C14,North Anna Power Station,Unit 1 ML18153C3111990-07-26026 July 1990 Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station. ML20011F6221990-02-26026 February 1990 Analysis of Small Steamline Break Performance W/O Low Pressurizer Pressure Safety Injection North Anna Units 1 & 2. ML20248E8641989-09-19019 September 1989 Rev 0 to Evaluation of Settlement Monitoring Program for Main Plant Structures in Support of Proposed Changes to Tech Spec 3/4.7.12. W/One Oversize Figure ML20246J1391989-08-17017 August 1989 Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding EP-2 ML20246J1581989-08-0909 August 1989 Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding MC-1 ML20246J1261989-07-20020 July 1989 Rev 0 to Coordination of Load Ctr Circuit Breakers,EP-1 ML20246J1191989-07-20020 July 1989 Rev 0 to Response to SSOMI Item IC-8 of NRC ML20246J0991989-07-18018 July 1989 Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-2 ML20246J1071989-07-18018 July 1989 Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-7 ML20246J1481989-06-30030 June 1989 RCS Leakage Detection Sys ML20246K3461989-05-0505 May 1989 Technical Evaluation & Safety Analysis:Solid State Protection Sys Slave Relay Testing REA-88-51 ML20245K7311989-04-26026 April 1989 Rev 0 to 890225 Steam Generator Leak Event Rept ML20056A0341989-04-18018 April 1989 Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement ML18151A9661989-04-18018 April 1989 Nuclear Decommissioning Trust Agreement. ML20245A5311988-09-13013 September 1988 Simulator Certification Submittal ML20148J6311988-03-16016 March 1988 Generator Tube Fatigue Evaluation & Remedial Actions Rept ML20147F5621988-03-0202 March 1988 Safety Evaluation in Support of Containment Temp Increase for North Anna Power Station ML20196J2901988-02-24024 February 1988 Rev 1 to Civil Engineering Technical Rept 0005, Differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House ML20148J6401988-02-12012 February 1988 Rev 2 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept ML20091L7041987-10-19019 October 1987 Generator Row 9 Column 51 Tube Failure Analysis ML20235G2441987-09-25025 September 1987 Steam Generator Downcomer Mods Safety Evaluation for North Anna Units 1 & 2 ML20238F6161987-09-15015 September 1987 Rev 1 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20235U6701987-08-0707 August 1987 Loss of Inventory Event 870617-21 ML20235Q0661987-08-0505 August 1987 Metallurgical Svcs Rept FAL-00050 ML20237G9791987-07-29029 July 1987 Rev 0 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept. W/Pages from Facility Updated FSAR ML20235U3431987-07-20020 July 1987 Rev 0 to Chronology Steam Generator Tube Rupture Event North Anna Power Station Unit 1 870715. Related Info Encl ML20238E1611987-07-15015 July 1987 Rept of Emergency Preparedness Events Re Unit 1 Steam Generator Tube Rupture ML20215G5471987-06-17017 June 1987 Safety Evaluation for Change in Methodology & Supporting Analyses ML20235Q0551987-05-21021 May 1987 Investigation Rept FAL-00024, Emergency Diesel Generator Floating Busing Failure ML20206D6721987-03-31031 March 1987 Engineering Analysis Svc & Maint North Anna Power Station Fairbanks-Morse 38 TD8-1/8 Diesel Engines Phase II ML20207B5231986-11-30030 November 1986 Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016 ML20213D7771986-10-31031 October 1986 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices ML20213D7601986-10-31031 October 1986 RCS Loads & Component Support Margins Evaluation for Elimination of Rcs,Main Loop Pipe Break Protective Devices ML20210F6821986-10-17017 October 1986 Reactor Protection Sys Trip Setpoint Drift Characterization 1999-10-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
[Table view] |
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. TECHNICAL REPORT NO. EE-0020 - REVIS DN 0 RESPONSE TO THE NRC LETTER OF JUNE 26, 1989 SERIAL #89-485, APPENDIX C, FINDING IC-7 ELECTRICAL ENGINEERING
-POWER ENGINEERING' SERVICES VIRGINIA POWER
. JULY 14, 1989 Prepared By: -
Date: f//8[89 Independent Review By:_ o Date: '7- / N-89
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1.0 INTRODUCTION
Lg The~ purpose -of this Technicul Report is to respond to the Nuclear, i
L, Regulatory Commission .(NRC) letter of June 26, 1989, Serial' #89-485, Appendix C, Finding IC-7 (Attachment 1).
7 i
l 2.0 METHODOLOGY During- the 1987 ' review by the NRC for equipment qualification'(EQ) compliance at North Anna Power Station, a violation of 10CFR50.49(j)
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was found. 10CFR50.49(j) requires a record of electrical equipment-performance requirements (QDR) under conditions existing during and following' design basis accidents be maintained in an'auditable form.
VEPCO-comitted to. revise the engineering standard that describes the' requirements' for QDR packages by August 31, 1988, and define.
performance requirements and incorporate them into the_QDR packages by December 30, 1989. The specific performance requirement in question during the SSOMI audit related to cable leakage currents and the effect on instrument loops operating in a harsh environment. A review of the standard was performed and a status of performance requirements was made.
A review of previous correspondence from VEPC0 to the NRC on SSOMI topics was performed. It appears that the June 26, 1989 NRC letter was written prior to receiving all of the related VEPC0 correspondence.
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'3.0oRESULTS A review' of STD-GN-0025, " Equipment Qualification' . Standard".(see'-
' Appendix C Section'2.3), revealed 'that performance characteristics-(requirements) had been incorporated into the revision of August 31, 1988.
1 Guidance; on when to perform instrument loop. calculations and what is..
included in a calculation was established in Technical -Report Number' s
EE-0019..
In the VEPC0 letter to the NRC dated May 15,'1989,'(Serial.#89-206C),
calculations were presented which demonstrated that cable leakage currents were included in harsh environment circuits.
4.0 CONCLUSION
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Engineering standards have been developed that provide a methodology for calculating, documenting, and reviewing changes to setpoints.
1
- Setpoint calculations, which included cable leakage current, were 1:
i; _ performed on loops that function in a harsh environment and found to be acceptable.
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O .s 5;0 REFERENCES i.1 i5.l VEPC0 g STD-EEN-0304-11 5,2' VEPC0 STD-GN-0030 5.3 l Attachment 1 - NRC letter to VEPCO dated June 26,'1989,
. Serial #89-485, > Appendix C, Finding. IC-7 15.4 VEPC0 letter to the NRC dated.May 15, 1989, i
. Serial #89-206C' 515':VEPC0fletter to the NRC dated May 19 1988,
, Serias ' #88-230, Violation D' 5.61 VEPC0-STD-GN-0025-f74.WTM.0020-
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51311ar requirements for 30 day reports are identified. in 10 CTR 50.73(a)(2)(ii)(B)or-(v)(B).'
References:
I
-(1) VEPCO Deviation Report 87-1452,. December 22, 1987 VEPCO Design Change 84-43-3 ' Service Water Reservoir Improvements, (2) Final Sys?am Tie-in and Startup/ North Anna Units 1&2" i
'(3)-VEPCODeviationReport 87-1405, December 8, 1987 FINDING IC-6: Inadequate Operator Training and Simulator Modeling.
(Unresolved Item 89-200-05).
Discussio;n 87-1405 associated with
.As a result of the team's review of. Deviation Report'DC 84-43-3, a qu Report 87-1405. identified the failure of a service water. bypass motor-operated VEPC0 investi-valve to close an initiation of a signal from the control room.
' fatiure to chse was that the operator did not realize that the throttleable and that thr. circuitry for the valve does not have a seal-in '
satact, the operator has to continually hold the contact (without a seal-tc handswitch in the open oratosed position to move the valve.to the fully open crclosedposition).
During the inspection, the team determined that reactor operators had receive training on.the new service water reservoir spray and bypass system but that A training did not specifically cover the operation of.the particular valves
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In addition, when the simulator was changed several months -later in 'uestion.
to reflect the service water system changes, the bypass valves were incorrec Theedtemrometas open .
modeled'with seal-in versus throttleable circuitry.
pendtem VEpCG correctias,the s4msteter hypoor vet wheel > switches heemses&4s veesus throttleeMe stres$ err.
Regulatory Basis:
10 CFR Part 55.11 requires reactor operators be trr,ined in the operation plant systems.
References:
.(1) VEPC0 Deviation Report 87-1405, December 8, 1987 FINDING IC-7:
Inadequate Loop Accuracy Calculation for Charging Flow Instrumen (Unresolved Ites 80-200-06)
Discussion:
During the inspection, the team reviewed portions of Design Change 8 pertaining detector.
to the installation of a new charging flow differ C-6 I
new detecttr and its effect en the ovarall instrument loop accuracy. During the review the team found that Calculation EE-0048 perforined for determining the instrument loop accuracy, did not consider the effects of current leakage due the degradation of the cable insulation system in a postulated harsh environment. In a postulated harsh environment, cable insulation resistance decrease which increases leakage currents and cause a corresponding decrease in instrument accuracy. TMs, was a repeat of violation 87-32-03 cited in NRC Inspection Report 50-338/87-32 and 50-339/87-32. During that inspection VEPCO was cited for failing to address the effects of characteristics such as leakage currents on total loop instrument accuracy calculations. In a response to this violation, submitted to the NRC on May 19, 1988, VEPC0 committed to revising Engineering Standard STD-N-0025 by August 31, 1989, as necessary to preclude further violations. This standard had been changed; however, the changes made appeared to be inadequate for ensuring that loop accuracy csiculations would be correctly perforined when changs were made to environmentally qualified systems.
Calculation EE-0048 was performed after the standard was changed.
As a result of this finding, VEPC0 performed a new calculation which included the effects of the cable leakage currents. This calculation showed that the cable added an additional 0.3 percent to the previously assumed error of 5 percent. TMs iten remn6ms open pending VEpCG'st revlam et othee prov$eur changes to the fetility uMob may have affectae insteumontestes loope WettEqP
in a hereb environment; Also, VEp e te regnestee te tsomo e r r M ; :: --
dura fee - ' i pos&thill'tp.e6 adshe$asteumano r errore tr future modifient6eas.
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Regulatory 8 asis:
10 CFR 50.49(d)(1) requires that the qualification file for electrical equipment important to safety specify the performance requirements under conditions exist-ing during and following design basis accidents. 10 CFR 50.49(j)(2) requires that the qualification file for electrical equipment important to safety demonstrate that the equipment meets its specified perforinance requirements.
References:
(1) VEPCO Design Change 87-29-2, "CRDR Instrtssentation Range Changes, Marth Anna Unit 2." November 3, 1988 (2) YEPC0 Calculation EE-0048, " Instrument on Channel Accurscy for Charging and Letdown Flow," Revision 0, February 10, 1989 (3) NRC Inspection Report 50-338/87-32 and 50-339/87-32 November 25, 1987 (4) VEPC0 Letter to MtC. Serial No.88-230, May 19,1988 (5) VEPC0 Response IAC-002, 'IR Loss in Cable " February 16, 1989 (6) VEPCO Standard STD-GN-0025. " Equipment Qualification Standard", Revision 6 Change 2. October 13, 1988.
FINDING IC-8: Inadequate Pest Modification Test Program.
(Unresolved Item 89-200-07):
C-7
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