ML20112J410
| ML20112J410 | |
| Person / Time | |
|---|---|
| Site: | Waterford, 05000000 |
| Issue date: | 03/31/1983 |
| From: | Holloway E, Yost M EG&G, INC. |
| To: | NRC |
| Shared Package | |
| ML20105B661 | List: |
| References | |
| CON-FIN-A-6415, FOIA-84-262 EGG-EA-6200, NUDOCS 8501180272 | |
| Download: ML20112J410 (31) | |
Text
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ELECTRICAL EQUIPMENT AT THE WATERFORD STEAM ELECTRIC l STATION, UNIT 3 l 1 E. R. Holloway M. W. Yost Idaho National Engineering Laboratory i Operated by the U.S. Department of Energy i\ .
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This is an informal report intended for use as a preliminary or working document Prepared for the U.S. NUCLEAR REGULATORY COMMISSION Under DOE Contract No. DE-AC07-761('01570 FIN No. A6415 E G E G roano 8501180272 840524 PDR FOIA WILLIAM 84-262 PDR
. I EGG-EA-6200 '
r F AUDIT OF THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT AT THE WATERFORD STEAM ELECTRIC STATION, UNIT 3 E. R. Holloway M. W. Yost Published March 1983 l EG&G Idaho, Inc. Idaho Falls, Idaho 83415 t
- Prepared for the U.S. NUCLEAR REGULATORY COMMISSION Under DOE Contract No. OE-AC07-761001570 FIN No. A6415
s A8STRACT EG&G Idaho, Inc., and NRC Staff members conducted an onsite audit of the Waterford Steam Electric Station, Unit 3, to determine the environmental qualification of safety-related electrical equipment. Results of the audit are sumarized in this report. e 11
t FOREWORD This report is supplied as part of the " Equipment Qualification Case Reviews" being conducted for the U.S. Nuclear Regulatory Comission, Office of Nuclear Reactor Regulation, Division of Engineering, Equipment Qualification Branch, by EG&G Idaho, Inc., Reliability and Statistics Branch. The U.S. Nuclear Regulatory Comission funded the work under the authorization B&R 20-19-40-41-2. e e 111
9
SUMMARY
On January 4, 5, and 6,1983, a team composed of representatives of the Reliability and Statistics Branch of EG&G Idaho, Inc., and the Nuclear-Regulatory Commission Staff conducted an audit of the environmental qualification of safety-related electrical ecuipment at the Waterford Steam Electric Station, Unit 3 (WSES). The work effort consisted of: (a) a pre-audit review of the licensee's environmental qualification submittal, (b) an audit of the licensee's central files for selected equipment items, and (c) a visual inspection of the equipment items for which the central files were audited. Several concerns that came out of the audit require followuo work by the applicant. Also some comments were made that would make the Qualification Data Evaluation Form a more useful document. It was concluded that the WSES environmental qualification program is acceptacle provided WSES responds appropriately to corcerns. 4 b e tv
s. CONTENTS
. A B S TR A C T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . it F O R EW OR D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111
SUMMARY
.............................................................., jy 1.- I N TR O D U C T I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I
- 2. EVALUATION ........................................................ 2
- 3. CONCLUSIONS ...................................................... 5 4
REFERENCES ....................................................... 6 APPENDIX A--SUMMARIES OF WSES CENTRAL FILE REVIEWS . . . . . . . . . . . . . . . . . . . . 7 APPENDIX B--EQUIPMENT QUALIFICATION CONCERNS AND COMMENTS ............. 15 e V
AUDIT OF THE ENVIRONMENTAL OUALIFICATION OF SAFETY-RELATED ELECTRICAL EOUIPMENT AT THE WATERFORO' STEAM ELECTRIC STATION, UNIT 3
- 1. INTRODUCTION
, On January 4, 5, and 6, 1983, a team composed of representatives of the Reliability and Statistics Branch of EG&G Idaho, Inc., and the Nuclear Regulatory Commission Staff conducted an audit of the environmental qualification of safety related electrical equipment at the Waterford Steam Electric Station, Unit 3 (WSES) to determine compliance with approved NRC regulation and standards. The work effort consisted of: (a) a pre-audit review of the licensee's environmental qualification submittal, (b) an audit of the licensee's central files for selected ecuipment items, and (c) a visual inspection of the equipment items for which the central files were audited. Summaries of the central file reviews are provided in Appendix A. Qualification concerns and comments for individual ecuipment items are provided in Appendix 8.
I
- 2. EVALUATION General areas of concern which remain as a result of both the audit ,
and the pre-audit review are as follows:
- 1. During the review of the environmental cualification submittal and the utility's central files some anomalies were found. These anomalies included inconsistant radiation levels and incorrect equipment locations and model numbers.
- 2. T'ie radiation analysis used to account for some attenuation of radiation was not provided. In particular the analysis showing the Total Integrated Dose (TID) for a0 years plus 1 year post LOCA is <0.85 mead for the General Electric (GE) selector switches. The applicant has agreed to provide this analysis to the staff for review.
- 3. Field verification was not always performed. For example the field verification on the GE selection switches, which are mounted in an enclosure, was not completed. EBASCO stated this item had been turned over to the utility and would require QC authorization to open the enclosure for inspection.
- 4. Below are listed general comments on the " Qualification Data Evaluation Form" (00EF), Figure 1.
- a. -The "QUALIF METH00" column (5) does not give meaningful information. In almost all cases the method is listed as
" COMB. TEST & EXTRAPOL'N" when other methods were possibly used.
- b. The " REPLACEMENT" and " MAINTAIN" sections should briefly indicate what replacement and maintenance is required to maintain equipment qualification.
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- c. The " ENVIRONMENT" columns (1) and (2) do' not always give the highest or most harsh parameters (i.e., highest specified
- temperature and highest qualified temperature). In most cases' only the normal value and a reference for the design
,. basis accident (08A) is given. In some cases the curve
., - referenced for demonstrated qualification is also the
- . reference used for specified environment.
- d. The " OUTS ITEMS" COLUMN (7) usually does not indicate what parameter is outstanding. If qualification nas not been confirmed, the equipment is not qualified and tne ODEF should reflect tne outstanding items.
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- 3. CONCLUSIONS As a result of the audit it was concluded that the WSES environmental qualification program is acceptable. When WSES resolves the concerns noted above and in Appendices A and 8 their prggram should be jomplete and in
. accordance with NRC approved regulations and standards.
9 7
.e 5
e 4 REFERENCES
- l. Response to NUREG-0588, Revision 4A, Waterford Steam Electric' Station' Unit 3. ,
- 2. Interim Staff Position on Environmental Qualification of ,
, Safety-Related Electrical Equipment, NUREG-0588. .
- 3. IEEE Standard for Qualifying Class.lE Equipment for Nuclear Power - ;
Generating Stations, IEEE Std. 323-1974. 4 h i i I e 3 T j .- 6 t I - e
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I APPENDIX A SUMMARIES OF WSES CENTRAL FILE REVIEWS 5 7 a
APPENDIX A , SUMMARIES OF WSES CENTRAL FILE REVIEWS Okonite 600 V Power and Control Cable EPR Insulation This cable is used to supply power to the containment fan coolers, various IE 480 volt motors in and out of containment, and control and instrumentation circuits. The specified accident parameters are: temperature, 413*F; pressure, 44 psig; humidity, 100%; chemical spray 3 1750-2150 ppm boron pH 5-9; radiation,1.97 x 10 rads TID; operability time, 120 days. Environmental testing for this cable was performed by Okonite as specified in Report No. NORN-1 and its appendices. The maximum environmental test parameters are: temperature, 345'F (extended to
>413*F by analysis); pressure, 112 psig; humidity, 100%; chemical spray, 3000 ppm boric acid buffered to a pH of 10.5; radiation 2 x 103 rad TID; test duration; 135 days; thermal aging at 150*F for 21 days 3.nd utilization of Arrhenius methodology showed a qualified life of 40 years. The qualification method was test and analysis.
The applicant states this cable is installed in submerged conduit which is not considered water tight. This concern is being examined by the staff. Reliance Fan Motor, Model Teao, Frame S/N 449T This device is used for containment heat removal and is located.in the reactor building. The specified accident parameters are: temperature, 413'F; pressure, 44 psig; humidity, 100%; chemical spray, 1750-2150 ppm baron and pH of 0-9; radiation, 2.8 x 10 rads TID; and operability time, 120 days. Environmental testing for this device was performed by Joy Manufacturing Company as detailed in Report X604 dated April 6,1977. Prior to testing, thermal aging was. performed at 415'F for 108 hours. The 9
maximum environmental test parameters were: temperature, 415'F; pressure, 78 psig; humidity, 100%; chemical spray, 3000 ppm Boron and pH 10.5; , radiation, 3 x 103 rads TID; test duration, 1 year; the cualification method was test and analysis. It is concluded that the documentation presented in the applicants file supports qualificaton of this item. Comsip Delphi Inc. Hydrogen Analyzer, Model No. K-III This device is used to provide post DBA hydrogen sampling and is located in the reactor building, Wing I. The specified accident parameters are: temperature, 148'F; pressure, atmospheric: humidity, 100%; radiation 6.4 x 10 rads; operability time 120 days. Environmental testing for this device was performed by Engineering Analysis and Test Company Inc. project Nos. 1035-1 Revision 1 and 1035-8 Revision 3 and Instrumentation Research Technology No. 5230-001 P.O. 0647. The maximum environmental test parameters were: temperature, 150*F; 6 pressure, atmospheric; humidity 100%; Radiation, 1 x 10 rads TID; test duration (post LOCA conditions at cabinet location), 100 dcys; The method of Qualification was by test and analysis. The Hydrogen Analyzer, is awaiting confirmatory data to support qualification. Retest or analysis is needed as there were sample pump bearing failures, and diaphragm leaks at 42 days and 100 days respectively, post LOCA. The applicants' review of the qualification files did not address these anomalies, however the applicant did state they were aware of the anomalies and were progressing to their resolution. 'Also maintenance and parts replacement is required to insure continued H2 analyzer qualification. 10 ,
Conax Corporation Electrical Penetration, Model No. 7320-10000-01, Plant No. PEN 104 This medium voltage power penetration provides sealed conductors through containment for reactor coolant pump power and is located in containment at coordinates X - 64.0, Y - 5.0, and Z - 37.5. The specified accident parameters are: temperature, 413*F; pressure, 44 psig; relative humidity, 100%; chemical-spray, 1720-2150 ppm baron and pH 5.0-9.0; radiation, 3.3 x 10 7rads TID; and operabi'ity time of 120 days. Enviromental testing has been performed on a similar model penetration as reported in Canax test report IPS-602. A Conax Telex, 11/10/82, in the qualification package states that,the penetrations tested are similar in material and construction to the Waterford penetrations. The maximum environmental parameters that the penetration was ' subjected to are: temperature 405.5'F; pressure, 72 psig; relative . humidity, 100%; chemical spray, 1720-2150 ppm Boron and pH 7.81; radiation, l.05 x 10 rads TID; operability, 288 hours >300*F. Thermal aging was performed for 168 hours at 250*F, providing a pre-age time of 40 years at 160.8'F. Submergence was not addressed because the penetrations are above flood level. The 00EF for PEN 104 contained errors for chemical spray, radiation, and model number which were found during the audit, but other documentation contained the correct information. The applicant has corrected the erroneous data. The specified environmental temperature was not enveloped by the test temperature, but.the test report contained an analysis demonstrating
, qualification with margin at the lower test temperature. The penetration PEN-104 is qualified for it specified environment.
. 1 General Electric Selector Switch Model No.-CR29400S203E, Plant No. 8/M C8-1
-The selector switches reviewed provide local control of various lE, fans, valves, and pumps'outside the reactor containment..
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The maximum specified accident parameters are: temperature, 150*F; relative humidity, 90%; radiation, 8.9 x 106 rads TIO, and operability time of 120 days. Environmental testing has been performed on a CR2940 series selector , switch model No. CR2940YB202B1 and is reported in GE report 134-18653. The maximum environmental parameters tha' the selector switch was subjected to are: temperature, 267.8'F for 14 days; radiation 1 x 10 6rads TIO. Analysis is provided in the qualification file which shows that 150*F for 132 days is equivalent to 4.1 years at 104*F, therefore the cualified life of the selector switch must be shown to be greater than 44.1 years plus 10% margin. The analysis demonstrated that 267.8'F for 14 days is equivalent to 54.93 years at 104*F. Some of the rooms in which these selector switches are located could 6 have a radiation dose of 8.9 x 10 rads TID. ESACSO has performed an analysis, which was not available, taking into account space attenuation showing that the TIO for 40 years plus 1 year past LOCA will be <.85 mrad for any switch. The applicant has agreed to provide these calculations to the NRC for review. GE stated that condensation of moisture on the insulation surfaces is not permitted when power is supplied. This should not be a problem because the applicant stated that all switches are mounted in NEMA-4 enclosures. Some discrepancies were found between the 00EFs and the zone maps plant coordinates for some of these switches. The applicant has agreed to correct these. During the visual inspection of the selector switches it was - discovered that the field verification had not been performed. _The switches were mounted in an enclosure which had been released to the utility by the Architect Engineer and could not be opened for inspectior unless a QC representative was present. Authorization was obtained during the audit to open the enclosure and it was not apparent from the visual 12
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. inspection that the installed switch was the same model as tested. The J verbal-explanation given by the applicant establishing that the tested and installed switch are equivalent should be placed into the file.
p s In conclusion, the GE selector switches are-qualified for their i
. Specified environment pending the outccme of the NRC review of ESASCO 4 radiation calculations.
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APPENDIX 8 EQUIPMENT QUALIFICATION CONCERNS AND COMMENTS O 15
TABLE 8.1. OEFICIENCY AND STATUS CODES A - Aging deficiency ACC - Accuracy deficiency CS - Chemical spray deficiency H - Humidity deficiency NQ - Not qualified OT - Operating time deficiency OTM - Operating time margin deficiency 0AC - Qualified awaiting confirmatory data QE - Qualified without exception R - Radiation deficiency RAE - Actual radiation environment error RMA - Requires major analysis S - Submergence deficiency SOM - Submergence qualification method deficiency TIP - Testing in progress TLA - Thermal lag analysis required TM - Temperature margin deficiency TR - Temperature rise analysis required V - Not verified O e 17 t
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TABLE B.2. (continued) toulslana f oulgunent Power and flualli kat ion rackage Number iIght fquipment Manufacturer Mmlel Insulation Status Comment s 3.2W) ,Solenold (cont.) ASCO (cont.) 206-812-7u QE V I (cont.) H881204175 Replace NP831646V QAC V NP8344846f QAC V HI2068323F QC 8302C21f Replace WPHI830069RU Replace HV200-926-1 Replace llV200-926-If 8.3W3 Radiation detector General Atomics RD-6 QAC 01.C5,A.It A RD-23 QAC OIM,R.A,il A RD-2A QAC Mild environment Micro processor RM-80 QAC OT.T.R.A.ItA g Radiation detector RD52/RD12 QAC A,1,0lM IL A sk Id Sensors WRGM QAC A.1,0lM.It A 3.3W1 Turbine control Terry Steam Turbine Corporation Turbine model GS-2 Retest system 4.lW) fan motor Reliance if AD, f rame 4491 Of QDff 0885 and 954 require explanation as to submergence is not applicable 4.2W3 Pump motor Allis-Chalmers 500 P56 Of
- 53) C56 QE 324 IS QE 4.3W1 Pimap motor General ilectrIc Sk81104SC25 4t 25811045C25 QE 4.9W3 f an an, tor We5tinghouse IIIC frame 182I Qt IIIC f rame 3248 Of ifIC frame 326I QE IlfC frame 2541 Qt IlfC frame 2n4I QAC V lilC frame 2151 QE lifC frame 213I Of
TABLE B.2. (continued) toulslana [quipment Power and Qualification tight Package Mond>er E quipment Manufacturer Model Insulatlon _ .tatus Comument s 4.9W3 Tan motor (cont.) Westinghouse (cont.) If fC Frame 445I QE (cont.) IffC frame 145I QE 4.lHW3 Fan motor Reliance ITA0 f rame 405T QE [ IIA 0 frame 445! Of 4.llW3 Pump motor Westinghouse Type: life line/ QE OI,IM IBDP 1418 4.1?W3 Pump motor Siemens-Allis Type RG QAC V 4.13W3 Pump motor $lem as-Allis Type GW QAC V,IR 4.14 Pump motor General Electric SkC404Ak23nV QAC V 6.lW3 600 V power / control Okonite EPR Insulation QE RA[ m cable 6.?W3 SkV cable Okontte EPR Insulation QE 6.3W3 theraxouple cable Rochteestos ~ Fire wall lil Q( RAE Coantal cable 600 V power / control c able 6.4W3 5kV power cable An aconda (PR Insulation QE 600 V power, control Anaconda FR-[PR insulatton QE 50M.RAE instriment, and t herm> couple cable 6.6W3 Cable assembly Boston Insulated Wire SR cable and QE Q(TF 0700 Insulation missing Cable seals Boston Insulated Wire Attachment D of Retest specification 2690 Conduit seals Boston Insulated Wire Litton C1:00 series Retest
TABLE B'.'2. (continued) f oulguient toulslana Pouer and Quelli1 cation itaht Package Numdwr Equipment' Manuf acturer Mmlel - Insulattun 5tafus Comment s , 6.nW3 Cable Samuel Mocie, Inc. FR-EPDM QE Sapt, RAE 8.1W3 Flow transmitter Rosemount l153 DA4 RMA A 1953 DAS RMA A 1853 DA6 RMA A 1852 HP6A22PS RMA A 1952 (W4A22P8 RMA A Pressure transmitter Rosemount 1853 GA7 RMA A 1853 AA6 RMA A 1153 DA7 RMA A 1853 GA8 kMA A 1953 GA9 RMA A 1952 GP8A22P8 RMA AR Level transmitter Rosemount 1853 DA5 RMA A,R 1853 DA4 RMA A to 1853 HA5 RMA A l152 DP5A22PB RMA A 1152 DP5(22PR RMA A 1952 DP5A22 RH4 A 1852 DPS RH4 A Differential pressure Rosemount 1853 D43 RMA A transmitter 8.2W3 Flow transmitter III Rarton 764 QAC Pressure transmitter III Barton 763 QAC 764 QAC 5 tevel transmitter III Barton 164 QAC 5 Dif ferential pe essure III Barton 765 QAC tranuellter 9.lWJ- Limit suitcts Namco (Al70-32302 Qt (Al10-32302 QAC V9 It h
s TABLE B.2. (continued) t ouls lana (quipment Power and Qualif ication L ight Package Nuakr Equipment Manufacturer No.sel Insulation Status Comment s 9.lW3 Limit switch (cont) Namco (cont) (AI70-31100 Replace NQ (cont) (AI70-41302 QE (Al?O-42302 QE fA170-41100 Replace NQ (Al?0 42100 Replace NQ [A170-15I00 Replace NQ fA170-14100 Replace NQ r [A700-10100 Replace NQ EA170-Il102 QE (A170-32100 Replace NQ 9.2W3 Limit sullch Namco (A-170-15l00 Replace NQ [Al70-14100 Replace NQ EA180-21302 QE (A180-15302 QE iA180-14302 QE N EAl10-31100 Replace NQ N fA180-31302 QE [Al80-31302 QAC .yh [A180-32302 QE EA180-11302 QE [A180-12302 QE [A170 series Replace NQ inside containment 10.2W3 Electric heating Indeeco 81ast call 60kW RMA 11P call ' 81ast coil 20kW RNA IIP ll.IW1 Hydrogen analper Comstp Delphi, Inc. K-Ill QAC V paewl 13.lW3 Penetrations Conas 7019-10001-01 QE 7320-10002-01 QE RAE 7320 10tK12-04 QE RAE 7320-10002-06 QE RAE 7320-10002-07 Of RAE 7320-10lN13-01 QE 7320-10003-02 Of RAE 7320- 10lkil-02 QE 7320- 10m 3- 18 QE g O .
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. . ~1 TABLE B.2. (continued) toulslana Equigment Power and Qualif icat ion L ip.t Package Nimher Equipnent Manufacturer hulel Insulation Status Comuments 15.lW) Penetrations (cont) Conaa (cont) 7320-l(WW13-04 Of (cont) 1320 10003-05 QE RAE 7320-10003-06 Of RAf 7320 10003-19 Of RAE 7320 10003-20 QE 73?0-10003-00 QC 7320-10003-1I QE 7320-10003 12 QE 1320 10003-13 QE 7320-10001-03 Qt 73M-1000t QAC 7320-10001 Qt 16.lW) Splices Raychem WC5f-N splice XL poly insulation QE RAE,5QM 16.2W3 5plices Okontte I-95 Insulation tape m no. 35 XIN IAP[ QE RAE,5QM w
17.2W3 Terminal blocks GE CRISIS series Qt 30.lW3 E/P transducers Masonellan MMI 8005A Retest A.R,lM F isher Continental Continental 546 Replace W) 35.lW3 Solenold valve Valcor Engineering Corporation V526-6002-5 QAC V V526-5295-9 QAC V V526-6002 15 QAC V V526 6131-5 QAC V V526-5295-7 QAC V V526-5295 7 t)f V526 5295-6 QAC V 35.6W) Solenoid valve larget R*k 818-001 Qf 818-001 QAC V8 818-001 Qt 818-005 OAC v} 818-002 Qt 36.lW3 Flow indkator switch til 8arton 500-1 QAC A.ll 5fk)A-0 , QAC llP,5QM 501-1 QAC A ,il 500A-1 QAC A.ll
TABLE B.2. (continued) . Loulslana fquipnient Power and Qua lif Icat ton tight Padage Mundeer ( quignment Manuf acturer Model Insulation Status Conament s 36.5W3 Level switch Fluid Components Inc. F R12-t t Retest Ile 38.lW3 f/P position Masonellam 8012 Retest IIP ' 39.2W3 theraxouple Weed Instrm:t Co. 15-T.. QAC A,V,0lM,ACC l$-103 QAC A.V.0IM,ACC 15-I13 QAC A V,0lM.ACC 15-101 QAC A.V,0lM.ACC 15-104 QAC A.V,0lM.ACC 15-1104 QAC A,V.OlM.ACC 15-I QAC A,V,0lM.ACC 39.3W3 2l0 Rosemount 104-AFCol RMA A R,01,I 104-1619-6 RMA A.R,01,i 104-Afv-l RMA A.R.0I.T 42.lW3 flydramot or III General Controls Isil-92 Of su e 42.2W3 Pneimmatic operator Gil 8ettis NT-3lt R-5R4-12 QAC 42.3W1 Valve actuator Borg Warner PN39400 Retest IlP 55.3W3 Selector switch General Electric CR2940HS 203f Of R.H,lM 61.lW3 flydrogen recombiner Westinghouse 8 QE Of 12.IW3 Water chiller Carrier 19FA sternetit QI ANOMAL l[$ Cent, liquid chill
- a. Qi4Fll42
- h. Ot4I2137
- c. 907, 900
- d. 911, 913, 916'
- e. 11/8
- f. 1082
- g. 10/8
- h. 910, 989, 958, 921, 1801, 1215, 1216
- 8. 816, all, 818
- j. 9fl4, 985
FON M "
. ii .,i U.$. NUCLEAR REGULATORY COMMISSION
, BIBLIOGRAPHIC DATA SHEET EGG-EA-6200 4 T1TLE AND SuSTITLE 2. / Leave ese,*J Audit of the Environmental Qualification of Safety-Related Electrical Equipment at the Waterford Steam 3. RECiPiENr S ACCES$1CN NO.
. Electric Station, Unit 3
- 7. AUTHOR (S) 5. OATE REPORT CCMPLETED E. R. Holloway, M. W. Yost Mca m March I'"" 1983
.' 9. PE RFORMING ORGANIZATION NAME AND MAILING ADORESS //actuoe I,a Codel CATE REPORT ISSUEO MONTH lvtam March 1983 EG&G Idaho, Inc. , ft ,,,, ,,,,,,
Idaho Falls, ID 83415
- 8. (Leave brans)
- 12. SPCNSCRING CRGANIZATICN NAME ANO MAILING ADORESS (incruce I,o Cooes p
Division of Engineering Office of Nuclear Regulatory Research si. nu uo. U.S. Nuclear Regulatory Commission A6415 Washington, DC 20555
- 13. TYPE C7 REPORT *E miCO Cov e nE O /Inerusere assesJ
- 15. SUPPLEMENTARY NOTES 14 ft,,,,o,,,,,
- 16. A8579 ACT (200 words or lens EG&G Idaho, Inc., and NRC staff members conducted an onsite audit of the Waterford Steam Electric Station, Unit 3, to determine the environmental qualification of safety-related electrical equipment. Results of the audit are summarized in this report, f
, 17 KEY WCRCS AND OCCUMENT ANALY0IS . 17a CESCRiPTC AS t
t l t 170 ICENTIFIERS/CPEN ENCEO TE%tS l l 18 Av AILA81LITY STATEVENT 19 SE CL A'Tv CLASS th,s recorre 1:1 NO CF PACES Unclassi fied i Uniimited 20ggps's#I'$r"#*' l "' s s N aC eomu 335 its an l _ . _ . _ . _ ._ , , _ .}}