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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196K5421999-03-22022 March 1999 Rev 2 to VC Summer Nuclear Station,Training Simulator Quadrennial Certification Rept,1996-99, Books 1 & 2. Page 2 of 2 Section 2.4.4 (Rev 2) of Incoming Submittal Were Not Included ML20117F2811996-02-29029 February 1996 Non-proprietary, VC Summer Residual Heat Removal Data Review & Monitoring Criteria Development ML20094C4691995-06-30030 June 1995 Seismic Activity Near VC Summer Nuclear Station, for Perid Period of Apr-June 1995 ML20094C4591995-03-31031 March 1995 Seismic Activity Near VC Summer Station, for Period of Jan-Mar 1995 ML20081J0901995-03-23023 March 1995 VC Summer Training Simulator Quadrennial Certification Rept 1992-1995 ML20064H4551994-03-0707 March 1994 Rev 2 to VC Summer Charging/Safety Injection Pump Runout Flow Evaluation L-93-036, Licensing Submittal to Support Replacement SG TS Changes for Vsns1993-10-31031 October 1993 Licensing Submittal to Support Replacement SG TS Changes for Vsns ML20062K6441993-04-30030 April 1993 VC Summer Spent Fuel Rack Criticality Analysis Considering Boraflex Shrinkage & Gaps ML20045F9561993-01-14014 January 1993 Non-Proprietary, VC Summer Nuclear Station SG TSP Interim Tube Plugging Criteria. Presentation Matls for Nrc/Sce&G/ Westinghouse Meeting on 930114 ML20090G9101992-02-29029 February 1992 Application for Approval to Incinerate Oil Contaminated W/ Very Low Levels of Licensed Radioactive Matl ML20082P2431991-07-31031 July 1991 Nuclear Physics Methodology for Reload Design ML20070R6561991-03-26026 March 1991 VC Summer Training Simulator Initial Certification Rept ML20062G1031990-10-31031 October 1990 Safety Evaluation for VC Summer Nuclear Station Upgrade to Westinghouse 17X17 Vantage+ Fuel ML20059D7021990-06-30030 June 1990 Technical Rept 90-02, Seismic Activity Near VC Summer Nuclear Station for Apr-June 1990 ML20005F4551990-01-0202 January 1990 Application for Approval to Incinerate Oil Contaminated W/ Very Low Levels of Licensed Radioactive Matls. ML19351A6741989-08-25025 August 1989 Cycle 5 Core Operating Limits Rept. ML20246C7731989-05-0202 May 1989 1988 Computer Mathematical Study of Thermal Plume in Monticello Reservoir Generated by VC Summer Station ML20154J5251988-05-31031 May 1988 Safety Evaluation for VC Summer Nuclear Station Transition to Westinghouse 17x17 Vantage 5 Fuel ML20148L3261987-12-31031 December 1987 Seismic Activity Near VC Summer Nuclear Station for Period Oct-Dec 1987 ML20214P2081987-03-0303 March 1987 Rev 1 to Crdr Summary Rept ML20135G6001985-09-16016 September 1985 Discussion of Proposed Control Logic Change for Steam Generator Power-Operated Relief Valves ML20135C0551985-09-0404 September 1985 Method of Analysis & Safe Shutdown Philosophy, 10CFR50, App R Compliance Review ML20115G4031985-04-15015 April 1985 Control Room Design Review Program Plan Rept for VC Summer Nuclear Station ML20115G4231985-04-15015 April 1985 Summary Rept on Reg Guide 1.97,Rev 3,Post-Accident Monitoring Sys ML20101S4381985-01-21021 January 1985 Rev 2 to Control of Heavy Loads at VC Summer Nuclear Station ML20091A8051984-04-30030 April 1984 Virgil Summer Deletion of Reactor Trip on Turbine Trip Below 50% Power,Apr 1984 ML20083Q0641984-04-0909 April 1984 Rev 1 to Licensing Rept on Spent Fuel Storage Racks ML20083H6381983-12-31031 December 1983 Draft Licensing Rept on High Density Spent Fuel Racks for VC Summer Nuclear Station ML20079P4051983-12-31031 December 1983 Licensing Rept on New Fuel Storage Racks ML20081M5301983-11-30030 November 1983 Seismic Confirmatory Program Equipment Margin Study, Final Rept ML20078R4761983-11-30030 November 1983 Draft Final Rept, Seismic Confirmatory Program - Equipment Margin Study ML20081H7281983-10-18018 October 1983 Draft Equipment Required for Cold Shutdown Aslb/Acrs Active Balance of Plant Equipment & Westinghouse Supplied Valves on Piping ML20071F1371983-03-31031 March 1983 Addendum to Experimental Investigation of Relative Response of Accelerograph Pad,Free Field & Structural Foundations at Virgil C Summer Nuclear Station ML20071F5071983-01-17017 January 1983 Divers Rept:Svc Water Intake Tunnel Insp ML20027C6011982-10-15015 October 1982 Independent Seismic Design Verification:Turbine Driven Portion Emergency Feedwater Sys, Final Rept.One Oversize Drawing Encl.Aperture Card Is Available in PDR ML20065G2581982-09-30030 September 1982 Independent Seismic Design Verification Turbine Driven Section Emergency Feedwater Sys,Vc Summer Nuclear Station, Draft Final Rept ML20063P0591982-09-30030 September 1982 Nonproprietary Version of Interim Power Operation Evaluation Rept ML20062D6601982-07-30030 July 1982 Pressurizer Relief Sys Piping & Support Evaluation Rept for VC Summer Nuclear Station,Sc Electric & Gas Co in Response to NUREG-0737,Item II.D.1 ML20054M4751982-07-0909 July 1982 Independent Seismic Design Verification,Turbine Driven Section Emergency Feedwater Sys, Status Rept ML20050B3541982-03-26026 March 1982 Revised Pages to Human Factors Engineering Evaluation & Improvement of VC Summer Nuclear Station Control Room,Phase 1. ML20041C6121982-02-23023 February 1982 to Fire Protection Evaluation ML20041C9171982-02-19019 February 1982 Nonproprietary Version of Revision 4 to Environ Qualification of Safety-Related Electrical Equipment Per NUREG-0588. ML20039F5591982-01-0707 January 1982 Floor Response Spectra from 1979 Monticello Reservoir Event Vs Original SSE Floor Spectra. ML20038A6621981-10-30030 October 1981 Control of Heavy Loads at Nuclear Power Plants. ML20009G0991981-07-31031 July 1981 Model Study of Reactor Containment Sump Flow Characteristics. ML20009G1511981-07-29029 July 1981 Corrected Pages to Control of Heavy Loads at Virgil C Summer Nuclear Station Unit 1, Revision 1 to 6-month Rept on NUREG-0612 ML20005A9841981-06-26026 June 1981 Control of Heavy Loads at Virgil C Summer Nuclear Station Unit 1. ML20126J8671981-03-18018 March 1981 Reactor Bldg Integrated Leak Rate Test (Type a) Final Technical Rept ML19351F4931981-01-31031 January 1981 Comparison of Mgt/Technical Resources to Regulatory Guidance. ML19341A1661981-01-31031 January 1981 Human Factors Engineering Evaluation & Improvement of VC Summer Nuclear Station Control Room,Phase 1. Prepared for Util 1999-03-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D6401999-10-31031 October 1999 Rev 2 to WCAP-15102, VC Summer Unit 1 Heatup & Cooldown Limit Curves for Normal Operation RC-99-0202, Monthly Operating Rept for Sept 1999 for VC Summer Nuclear Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for VC Summer Nuclear Station.With ML20216J4191999-09-24024 September 1999 Part 21 Rept Re 990806 Abb K-Line Breaker Defect After Repair.Vendor Notified of Shunt Trip Wiring Problem & Agreed to Modify Procedure for Refurbishment of Breakers RC-99-0180, Special Rept on 990807,electric Driven Fire Pump XPP0134A Was Declared Inoperable.Caused by Pump Discharge Relief Valve Failing to Open as Normally Expected.Two Temporary Fire Pumps Were Installed to Provide Backup Suppression1999-09-0808 September 1999 Special Rept on 990807,electric Driven Fire Pump XPP0134A Was Declared Inoperable.Caused by Pump Discharge Relief Valve Failing to Open as Normally Expected.Two Temporary Fire Pumps Were Installed to Provide Backup Suppression RC-99-0183, Monthly Operating Rept for Aug 1999 for Virgil C Summer Nuclear Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Virgil C Summer Nuclear Station,Unit 1.With ML20211K6161999-08-31031 August 1999 Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, Dtd Aug 1999 RC-99-0168, Special Rept:On 990804,electric Driven Fire Pump XPP0134A & Diesel Driven Fire Pump XPP0134B,were Removed from Svc to Allow for Plant Mod.Fire Pumps Were Returned to Operable Condition on 990818,after Mod Was Completed1999-08-19019 August 1999 Special Rept:On 990804,electric Driven Fire Pump XPP0134A & Diesel Driven Fire Pump XPP0134B,were Removed from Svc to Allow for Plant Mod.Fire Pumps Were Returned to Operable Condition on 990818,after Mod Was Completed ML20210M7071999-07-31031 July 1999 Rev 1 to VC Summer Nuclear Station COLR for Cycle 12 ML20211C2201999-07-31031 July 1999 Rev 1 to WCAP-15102, VC Summer Unit 1 Heatup & Cooldown Limit Curves for Normal Operation RC-99-0163, Monthly Operating Rept for July 1999 for VC Summer Nuclear Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0137, Monthly Operating Rept for June 1999 for VC Summer Nuclear Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0122, Monthly Operating Rept for May 1999 for VC Summer Nuclear Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for VC Summer Nuclear Station.With ML20206H2971999-05-0505 May 1999 Part 21 Rept Re Common Mode Failure for magne-blast Breakers.Vc Summer Nuclear Station Utilizes These Breakers in Many Applications,Including 7.2-kV EDG Electrical Buses RC-99-0103, Monthly Operating Rept for Apr 1999 for VC Summer Nuclear Station.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for VC Summer Nuclear Station.With ML20206K2421999-04-30030 April 1999 Rev 0 to COLR for Cycle 12 for Summer Nuclear Station RC-99-0087, Part 21 Interim Rept (SSH 99-0001) Re 990218 Failure of Circuit Breaker Located in Cubicle 14 of XSW1DB to Close During Surveillance Testing.Caused by Positive Interlock Angle Was Incorrect.Breaker Was Returned to GE Factory1999-04-15015 April 1999 Part 21 Interim Rept (SSH 99-0001) Re 990218 Failure of Circuit Breaker Located in Cubicle 14 of XSW1DB to Close During Surveillance Testing.Caused by Positive Interlock Angle Was Incorrect.Breaker Was Returned to GE Factory RC-99-0083, Monthly Operating Rept for Mar 1999 for VC Summer Nuclear Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0063, Special Rept:On 990302 & 16,meteorological Site Number One 10 Meter Temp Element Was Declared Inoperable.Caused by Erratic Operation.Cabling & 10 Meter Electrical Connectors Were Replaced1999-03-26026 March 1999 Special Rept:On 990302 & 16,meteorological Site Number One 10 Meter Temp Element Was Declared Inoperable.Caused by Erratic Operation.Cabling & 10 Meter Electrical Connectors Were Replaced ML20196K5421999-03-22022 March 1999 Rev 2 to VC Summer Nuclear Station,Training Simulator Quadrennial Certification Rept,1996-99, Books 1 & 2. Page 2 of 2 Section 2.4.4 (Rev 2) of Incoming Submittal Were Not Included RC-99-0055, Special Rept:On 990302,Meteorological Site Number One 10 Meter Temp Element (RTD) Was Declared Inoperable Due to Erratic Operation.Cause of Original RTD Failure Is Unknown. Equipment Was Declared Operable on 9903121999-03-16016 March 1999 Special Rept:On 990302,Meteorological Site Number One 10 Meter Temp Element (RTD) Was Declared Inoperable Due to Erratic Operation.Cause of Original RTD Failure Is Unknown. Equipment Was Declared Operable on 990312 RC-99-0050, Monthly Operating Rept for Feb 1999 for VC Summer Nuclear Station,Units 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for VC Summer Nuclear Station,Units 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML20203F4511999-02-12012 February 1999 SER Finding Licensee Adequately Addressed GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Virgil C Summer Nuclear Station ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20206R5241998-12-31031 December 1998 Santee Cooper 1998 Annual Rept RC-99-0052, Vsns 1998 Annual Operating Rept. with1998-12-31031 December 1998 Vsns 1998 Annual Operating Rept. with RC-99-0004, Monthly Operating Rept for Dec 1998 for VC Summer Nuclear Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for VC Summer Nuclear Station,Unit 1.With ML20206R5191998-12-31031 December 1998 Scana Corp 1998 Annual Rept ML20198F4241998-12-18018 December 1998 Safety Evaluation Granting Relief Request for Approval to Repair ASME Code Class 3 Service Water Piping Flaws in Accordance with GL 90-05 for VC Summer Nuclear Station RC-98-0223, Special Rept 98-001:on 981130,steam Line High Range Gamma Monitor (RMG-19C) Was Declared Inoperable Due to Indeterminate Alarm.Caused by Failures in Detector & Meter Reset Circuitry.Established Preplanned Alternate Method1998-12-16016 December 1998 Special Rept 98-001:on 981130,steam Line High Range Gamma Monitor (RMG-19C) Was Declared Inoperable Due to Indeterminate Alarm.Caused by Failures in Detector & Meter Reset Circuitry.Established Preplanned Alternate Method RC-98-0222, Monthly Operating Rept for Nov 1998 for VC Summer Nuclear Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for VC Summer Nuclear Station,Unit 1.With ML20155G4551998-11-0404 November 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Use Code Case N-416-1 with Licensee Proposed Addl Exams RC-98-0208, Monthly Operating Rept for Oct 1998 for VC Summer Nuclear Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for VC Summer Nuclear Station,Unit 1.With ML20207J5701998-10-31031 October 1998 Non-proprietary Rev 1 to WCAP-14955, Probabilistic & Economic Evaluation of Rv Closure Head Penetration Integrity for VC Summer Nuclear Plant ML20154Q9571998-10-21021 October 1998 SER Accepting Request Seeking Approval to Use Alternative Rules of ASME Code Case N-498-1 for Class 1,2 or 3 Sys ML20154K7901998-09-30030 September 1998 Non-proprietary Rev 0 to WCAP-15101, Analysis of Capsule W from Sceg VC Summer Unit 1 Rv Radiation Surveillance Program RC-98-0184, Monthly Operating Rept for Sept 1998 for VC Summer Nuclear Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for VC Summer Nuclear Station.With ML20154K8041998-09-30030 September 1998 Non-proprietary Rev 0 to WCAP-15103, Evaluation of Pressurized Thermal Shock for VC Summer Unit 1 RC-98-0166, Monthly Operating Rept for Aug 1998 for VC Summer Nuclear Station,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for VC Summer Nuclear Station,Unit 1.With ML20237A7181998-08-13013 August 1998 SER Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RC-98-0153, Monthly Operating Rept for July 1998 for VC Summer Nuclear Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for VC Summer Nuclear Station,Unit 1 RC-98-0131, Monthly Operating Rept for June 1998 for VC Summer Nuclear Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for VC Summer Nuclear Station ML20248J0191998-06-0404 June 1998 Safety Evaluation Accepting Licensee Inservice Testing Program Interim Pump Relief Request Per 10CFR50.55a(a)(3) (II) RC-98-0113, Monthly Operating Rept for May 1998 for VC Summer Nuclear Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for VC Summer Nuclear Station,Unit 1 RC-98-0100, Monthly Operating Rept for Apr 1998 for VC Summer Nuclear Station,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for VC Summer Nuclear Station,Unit 1 ML20217G7411998-04-22022 April 1998 Rev 1 to VC Summer Nuclear Station COLR for Cycle 11 RC-98-0076, Final Part 21 Rept Re a DG EG-B for Vsns,As Followup to .Power Control Svcs of Engine Sys,Inc Provided Response on 980318.Evaluation Concludes That Failure of EG-B Is one-time non-repeatable Failure1998-04-17017 April 1998 Final Part 21 Rept Re a DG EG-B for Vsns,As Followup to .Power Control Svcs of Engine Sys,Inc Provided Response on 980318.Evaluation Concludes That Failure of EG-B Is one-time non-repeatable Failure RC-98-0084, Monthly Operating Rept for Mar 1998 for Virgil C Summer Nuclear Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Virgil C Summer Nuclear Station,Unit 1 ML20212H1421998-03-0202 March 1998 Interim Part 21 Rept SSH 98-002 Re EG-B Unit That Was Sent to Power Control Svcs for Determination of Instability & Refurbishment of a Dg.Cause of Speed Oscillations Unknown. Completed Hot Bore Checks on Power Case 1999-09-08
[Table view] |
Text
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<J ' '
i SEPARATION AUDIT OF CLASS lE ELECTRIC i
EQUIPMENT AND CIRCUITS REPORT PREPARED FOR SOUTH CAROLINA ELECTRIC AND GAS COMPANY V. C. SUMMER NUCLEAR STATION UNIT 1 I
i BY GILBERT ASSOCLSTES, INC.
f I
~
l E 101180 f0$i ii
, 3 Table of Contents Page
- 1. INTRODUCTION 1
- 2. SCOPE OF AUDIT 1
- 3. SELECTION METHOD 2 1
- 4. AUDIT CRITERLt ,
3 4
, 5. INSPECTION PROCEDURE 3 I
, 6. RESULTS
- 7.
SUMMARY
AND CONCLUSIONS ATTACHMENTS 1 Random Sample Method 2 Procedure to Audit Separation of Class lE Electric Equipment and Circuits (without attachments) 3 List of Class lE and Associated Circuits and Equipment Audited I 4 Summary of Discrepancy Types 4
o i
V. C. SUMMER NUCLEAR STATION UNIT 1 SEPARATION AUDIT OF CLASS lE EOUIPMENT AND CIRCUITS
- 1. INTRODUCTION In response to the United States Regulatory Co= mission (USNRC) request, undated letter fros Mr. B. J. Youngblood to Mr. E. H. Crews, an audit of separation of Class lE equipment and Class lE and associated circuits was performed for the V. C. Su=ner Nuclear Station Unit 1, Docket No .
l 50-395. This report describes the program, procedures and results of g the audit.
The audit was performed by engineering and technical personnel who were not involved in the design and installation of the equipment and systess under audit, cnd who understood the standards, guides and FSAR co= sit =ents relating to the V. C. Su=ser Nuclear Station Unit 1 separation.
- 2. SCOPE OF AUDIT The audit included a 5% sample of plant-wide installed Class lE electrical equipment including control boards and panels, and Class lE I and associated field routed circuits and control boards and panels internal wiring. Listed below are the categories of circuits and equipment in the sample as well as the source used as the basis for identifying equipment or circuits in each category:
A. All Class lE and associated field routed circuits were identified by utilizing Gilbert Associates, Inc. (GAI) circuit su= mary printouts.
A sort by safeguard code was made and included all safety or associated channels; that is, A, B, C, D, E, J , K , L , M , XA , XB , XC ,
XD and XE.
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B. Class lE and associated equipment were identified utilizing FSAR Tables 3.9-7, 3.9-8, 3.11-0, and 3.ll-0a and included:
- 1. Valve operators (motor and solenoid)
- 2. Motors
- 3. Instruments
- 4. Dampers l S. Miscellaneous HVAC (chillers, fan motors)
- 6. Electrical (switchgear, control centers, inverters, i
penetrations, etc.)
1 i
, 7. Control boards and panels (control switches, indicators, recorders, and internal wiring. These items were identified using vendor prints).
- 3. SELECTION METHOD The selection method of equipment or circuits from each of the categories identified in Section 2 was by means of random sampling. The selected sample was obtained by utilizing randcm number tables to achieve a sampIe selected in such a way that each element had equal probability of being
! included in the sample. The random numbers satisfied a uniform distribution over a given interval. The rando'n tables were generated by computer algorithm to provide two (2) tables, one table for population sizes of up to 1000 and another for population sizes of up to 10,000.
This method of selection was chosen as it provided samples which were free from sampling bias. Using the procedure of Attachment 1, a 5%
sample was selected from each of the listed safeguard codes in Section 2.A, and each of the equipment categories in Section 2.B. Thus, the selected samples were not only free from sampling bias but also representative.
I
- 4. AUDIT CRITERIA The criteria and FSAR commitments used as the basis for the audit were as follows:
i A. FSAR Sections 8.3.1.4, 8.3.1.5, Appendix 3A, Reg. Guide 1.75, i Table 8.3-4, Sections 7.1.2.2 and 7.1.2.3.
] B. Electrical Insts .lation Spec. SP-222-044461-000, Rev.10, Sections
- 1 J 1.24, 1.26 and 1.38.
I 1 C. Drawing D-224-521, Rev. 5 k$
+
j D. Construction Guideline S-200-926, Rev. 2
}
E. Project Design Criteria, Section 4, Rev. dated 12/22/75 (For
, Information Only).
4
- 5. INSPECTION PROCEDURE The following is a surmary of the procedure used by the auditors at the plant site in checking separation of Class lE and Associated Circuits and Equipment. The inspection procedure is more-fully described in
^
Attachment 2.
1 A. Each audited field run circuit was " walked 'down" starting from the "From" point to the "To" point. Separation and identification (carking) was verified where a circuit ' entered and exited a tray, contuit, room, or equipment. Separation was also verified at any 1
points of intersection with other raceways.
I B. Confor=ance of the selected equipment to the separation and -
e identification requirements of Section 4 was verified by field inspections and measurements.
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t
. . . - - - _ _ _ _. _ -~_ - - - - . .__ .. ._
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< C. For control boards and panels, the selected sample of modules t (switches, indicators, relays, etc.) and internal wiring was i
physically inspected and traced, respectively, to ensure compliance j with Section 4 criteria.
}
2 l
For each audited item an audit report was completed to either confirm conformance 4
with the criteria or documenting the. discrepancy or discrepancies.
4
!I t
- 6. RESULTS i
A total sample of 564 Class IE and associated circuits and equipment were i
! field audited. Of this number, 394 were field routed circuits; 170 were
) the electrical equipment noted in Section 2.B; and the audit of 17 circuits, i
2 control board modules, and 1 control board internal wire could not be f
4 completed due to access, incomplete construction or other problems and i
were replaced by alternates. Of the total, 155 field routed circuits
{
and 100 electrical equipment we: found to have ao discrepancies. The I remaining audited items had one or more discrepancy detailed below and in i
Attachment 3 with Attachment 4 providing a summary of discrepancy types for each safeguard and associated channels and category of electrical equipment.
't Attachment 4 provides field results and does not include resolutions or documentation completed prior to the audit. This information is de' tailed-i below and in Attachment 3.
i l Generally, the discrepancies were one of the following:
I 4 A. Separation problem. .For field' routed. circuits it-was predominantly-insufficient distance / barrier between their raceways and a raceway of l .
a redundant channel or insufficient separation inside the' equipment.
where they terminated (i.e., "From" or "To" equipment). Insufficient; i
distance / barrier was also the problem for the other electrical equip-.
ment, where this discrepancy was reported.
A 4
- . _ - _ _ , . . . - . . _ .,__a._.~.w.~._ . _ . . . , ,,.a._.,_. - . _ . _
> B. Wrong circuit / equipment identification or color coding.
C. No identification on ends of circuit or "From-To" equipment.
D. No color coding - In cases where a field routed circuit was being audited, the circuit had no discrepancy other than the "From" or "To" equipment was not color coded.
Referring to Attachments 3 and 4, there were 134 circuits with marking, and I
with marking and separation discrepancies. One hundred four (104) of these were cases with marking (i.e., B, C, or D) discrepancies of the circuit's 3
j "From" or "To" equipment only. The remaining 30 cases, in addition to marking discrepancies of the "From" or "To" equipment also had a separation discrepancy.
In all of the preceding 30 cases, the separation discrepancy was unrelated to and not a result of any marking discrepancy. For marking discrepancies, South Carolina Electric and Gas QC memorandum CGSD-902-QC identified and reco==endei.
corrective action for generic equipment tagging and color coding discrepancits prior to this audit.
In total, 87 cases of circuits separation (A) discrepancies were identified in-cluding the 30 noted above. Of this total, 21 were the same discrepancy (i.e.,
g common separation problem; refer to note 6 of Attachment 3) the preceding 21 and an additional 12 separation discrepancies had been identified and documented for correction prior to this audit. Attachment 3 lists this documentation. Of the remaining 54 separation discrepancies, 21 were in cabinets covered by I
WCAP-6892-A and were also previously documented; and 5 have not yet been con-firmed by engineering as discrepancies. Therefore, 28 cases with category A discrepancies were discovered which apparently have not been previously identified.
These cases did not constitute significant violations of the separation criteria identified in Section 4 of this report.
i b
For the Section 2.B equipment, of the 170 audited items,100 had no discrepancies and 3 could not be audited. Of the remaining 67, there were 55 cases with mark-ing discrepancie; umy , 5 cases of marking and separation discrepancies, and 7 cases of separation only discrepancies. As noted above, the marking problems were previously recognized. Of the 12 separation problems, all but 1 were pre-viously identified and documented. Two (2) of the twelva were in cabinets j covered by WCAP-8892-A. The one remaining separation discrepancy, not previously identified also did not constitute a significant violation of Section 4 criteria.
F. SUSD!ARY AND CONCLUSIONS The audit of Class IE and associated circuits and electrical equipment satis-fled the requirements of the USNRC letter f rom Mr. B. J. Youngblood. The audit results indicate a trend towards two (2) types of deficiencies. The first was a lack of color coding as required by the criteria in Section 4 of this report. The second was of possible separation prablems inside certain Westinghouse supplied panels. As previously noted, however, the lack of color coding of the discrepancies found did not contribute to or re-sult in separation discrepancies. Also note that UCAP-8892-A covers-the I
Westinghouse panels and engineering evaluations of discrepancies related i
i to these panels which was initiated prior to this audit is not yet complete.
The remaining discrepancies were randomly occurring and did not constitute l significant violations of the separation criteria.
l l
The nature of the discrepancies founc indicate that the South Carolina Elec-i tric and Gas separation program generally provided an installation that l
l met the requirements of Section 4 separation criteria. In view of this and l
since the sample selection was random and representative, no qualitative benefit would be gained at this time by an overall expansion of the sample.
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However, the following recommendations are made:
A. The established program of equipment tagging and color coding to comply with the requirements of the Section 4 criteria be completed.
B. Complete the engineering evaluations including those of the Westinghouse cabinets noted above.
C. Correct the discrepancies identified by this audit.
i I
A
Attachment 1 Random Sample Methed 4
I The procedure for selecting a random sample is as follows:
- 1. Define the population to be inspected (i.e. , total number of items i
in the category).
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- 2. Assign each item in the population a unique number of one (1) to l N, where N is the population total.
- 3. Determine the sample size: .05 x (population)
- 4. Select the items to be inspected using the Random Sample Tables.
The Random Sample Tables used for this audit are printed from a computer program. Two printouts have been.done, one for a maximum of 1000 population, and one for a maximum population of 10,000. Proceed in an organized manner, by column, skipping over any number beyond the range of the population at hand.
4 i