ML20112J431
| ML20112J431 | |
| Person / Time | |
|---|---|
| Site: | Midland, 05000000 |
| Issue date: | 03/31/1983 |
| From: | Humphrey T, Stuart V EG&G, INC. |
| To: | NRC |
| Shared Package | |
| ML20105B661 | List: |
| References | |
| CON-FIN-A-6415, FOIA-84-262 EGG-EA-6195, NUDOCS 8501180279 | |
| Download: ML20112J431 (27) | |
Text
{{#Wiki_filter:_ . _ EGG-EA-6195 MARCH 1983 AUDIT OF THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT AT THE
. MIDLAND NUCLEAR PLANT (UNITS 1 AND 2)
T. G. Humphrey V. A. Stuart t Idaho National Engineering Laboratory Operated by the U.S. Department of Energy __? _,
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Q c !, This is an informal report intended for use as a preliminary or working document I i Prepared for the . U.S. NUCLEAR REGULATORY COMMISSION Under DOE Contract No. DE-AC07-76ID01570 FIN No. A6415 y 1 E G n G ,a n. 8501190279 840524 V PDR FOIA PDR WILLIAM 84-262
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hG3-EA-6195 4 AUDIT OF THE ENVIRONMENTAL QUALIFICATICN OF SAFETY-RELATED ELECTRICAL EQUIPMENT AT THE MIDLAND NUCLEAR PLANT (UNITS 1 AND 2) Occket Nos. 50-329 and 50-330 T. G. Humchrey V. A. Stuart Publis ed March 1983 Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc. Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Under 00E Contract No. DE-AC07-76ID01570 FIN No. A6415 i. i
n.; ABSTRACT The' Midland Nuclear Plant (Units 1 & 2) was audited to determine the environmental qualification of safety-related electrical equipment. Results- of the audit are summarized in this report. 4 i i i 4 l ,i. I-I I-NRC FIN No. A6415--Equipment Qualification Case Reviews i ! 11
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SUMMARY
An audit of the environmental qualification of safety-related electrical equipment at the Midland Nuclear Plant (Units 1 and 2) was conducted by a team comprised of representatives of the Reliability and Statistic's Branch of EG&G Idaho, Inc., and the Nuclear Regulatory Commission (NRC) staff. Qualification deficiencies for individual equipment items are provided in Aopendix A. Summaries of the central file reviews are provided in Appendix 8. As a result of the audit it was concluded that when the Midland Nuclear Plant resolves the concerns notec in this report, their qualification program will be complete and in accordance with NUREG-0588. e iii
-r FOREWORD This report is supplied as part of the " Equipment Qualification Case Reviews" being conducted for the U.S. Nuclear Regulatory Commission, 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 Commission funded the work uncer the authorization, B&R 20-19-40-41-2. 7 9 4 iv i i i 1 1
CONTENTS ABSTRACT ........................................................... .. 11
SUMMARY
..................................................... . ... .. i ii
- FORWARD ................................................. ............. iv
1.0 INTRODUCTION
..................................................... 1 2.0 EVA LVAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
3.0 CONCLUSION
S .......................................... . . . .. 2
4.0 REFERENCES
.................................................. .... 2 APPENDIX A--QUALIFICATION DEFICIENCIES FOR INDIVIOUAL EQUIPMENT ITEMS ........................................... ... .. 3
- APPENDIX S--SUMMARIES OF THE MIDLAND NUCLEAR PLANT CENTRAL FILE REVIEWS ..................... ............................. .. . 13 g
v
AUDIT OF THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC,AL EQUIPMENT AT THE MIDLAND NUCLEAR PLANT (UNITS 1 & 2)
1.0 INTRODUCTION
On January 11-13, 1983, a team comprised of representatives of the Reliability and Statistics Branch of EG&G Idaho, Inc., and the NRC staff conducted an audit of the environmental qualification of safety related electrical equipment at the Midland Nuclear Plant (Units 1 & 2). The work effort consisted of: (a) a pre-audit review of the licensee's submittal (Reference 1), (b) an audit of the licensee's central files for selected equipment items, and (c) an onsite visual inspection of the equipment items for which the central files were audited. Qualification deficiencies for individual equipment items are provideo in Appendix A. Summaries of the central file reviews are provided in Appendix B. 2.0 EVALUATION General concerns and comments resulting from both the audit and the pre-audit review of the Midland Nuclear Plant submittal are as follows:
- 1. Some of the NSSS equipment qualification packages were incomolete in that the applicant needs to incorporate either a test report or a test report summary.
- 2. The applicant at the time of the audit claimed that thermal lag analysis indicates temperature rises inside equipment is less than the surrounding environment. This remains an open item pending acceptance by the NRC.
- 3. Some equipment is cualified for 40 years with the exception that the equipment requires periodic replacement of critical components. Other equipment is qualified for 40 years without 1-
exception, yet the footnote requiring periodic replacement of critical components still exists. If exception to the qualified life exists it should be stated. 4 Several anomalies in. the Environmental Qualification (EQ) files were discovered during the audit. These items included, removal of one package due to the associated equipment being located in a mild environment and anomalies on an Equipment Environmental Qualification Sheet (EEQS) were found when compared to its respective test report. These anomalies are to be addressed in the next revision of the EQ submittal.
- 5. A draft field verification report of Class IE equipment located in the plant was presented at the audit. Effort to complete the report and applicable pages submitted into the subject EQ files would enhance the total EQ program.
3.0 CONCLUSION
S As a result of the audit it was concluded that the Midland Nuclear Plant demonstrated a high level of effort toward the EQ program. When the Midland Nuclear Plant resolves the concerns noted above, their EQ program will be complete and in accordance with NUREG-0588. '
4.0 REFERENCES
- 1. Environmental Qualification Report, Revision 1, Midland Nuclear Plant (Units 1 & 2).
- 2. Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, NUREG-0588.
- 3. IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 323-1974.
2
t APPENDIX A l EQUIPMENT CUALIFICATION STATUS O
' 3
APPENDIX A EQUIPMENT QUALIFICATICN STATUS
. The attached tables list the Class IE Equipment and Status for Midland Nuclear Plant Units 1 and 2. The codes below are used for status designation.
Midland Status A Action plan developed Q Qualified per NUREG 0588 R Replace with NUREG 0588 Qualified Equipment T Testing per NUREG 0588 in progress Reviewer Evaluation M E;CSandCDESmodelnumbersdonotmatch Q Qualified R Radiation deficiency T Temperature deficiency RS Qualified replacement scheduled 4 APD Action plan developed TIP Testing in pregress
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- 2. '; . 3 1060C instelation Howns k for instrumentatloss Cahlo Q Q 2.6 lie s i s t a !!cu,_l!;ml".! ra t t!r!L Dul en te r A s s umti ti e s 2.6.1 J233A Itos i s tanco temporatess o I)otectors A Arp 2.1 !!d d j g t lp!!J!g!!) Lgtj t!g._Syg t o!!l 2.1.8 J28 48aA Arua Hadiation Monitors i IIP 2.1. 2 J28 688 lt Asoa Itadiation Moref terleig Cable H lts 2.8 Jrstasjitof s 2 . 11 . 1 J28 4';A Pre s ste ro, l'Iow, arul l ovel Iransmitters I l i l'
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APPENDIX 8 SUMMARIES OF THE MIDLAND NUCLEAR PLANT CENTRAL FILE REVIEWS e 13
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APPENDIX B SUMMARIES OF THE MIDLAND NUCLEAR PLANT CENTRAL FILE REVIEWS DIFFERENTIAL P? SSURE TRANSMITTERS Manufacturer: Bailey Controls Model: N1BQ85221 These differential pressure transmitters provide a monitoring function of the reactor coolant het leg during normal conditions and a reactor trip function for both Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB) accident conditions.
; The required environmental parameters are: temperature, 281*F ,
pressure. 70 psig, radiation, 6.62 x 10 5rads Total Integrated Dose l (TID), humidity, 100*., chemical spray, borated water, accuracy, 0. 0*4, with a response time of 1.25 seconds and an operability period of 2 hours. The environmental qualification tests are reported in the Bailey Meter Company qualification test report numcer QR-3204-E21-20 Revision C with the demonstrated qualification parameters as follow: temperatue, 350*F, pressure 129 psig, humidity, 100*4, radiation, 9.1 x 105 rads TID, with a borated water chemical spray, accuracy, 0.10*4, response time, 126.5 milli-seconds, and a demonstrated operability time of 24 hours. The applicant has stated that a test report or a test report summary is going to be provided in this and all of the NSSS packages that are retained at the central files and will remain an open item until this action is complet6d. Additionally, the applicant has claimed that therma
- lag analysis indicates that the internal temperature W the differential pressure transmitters will not rise above 281*F during the MSLB accident and is therefore enveloped by the demonstrated 350*F with adequate margin.
The required te :perature for the MSLB remains an open item on this i equipment cending an explanation by the applicant. l ! 15
. ._ n
(; LOW VOLTAGE PCWER CABLE Manufac+ aer: Essex International Model: iype I/C-6 AWG, EP Insulation (T007) with Neoprene Jacket (T410) and EP Insulation (TX1406M) with Hypalon Jacket (T712) The low voltage power cable is used throughout the plant, both inside and outside containment. The maximum specified environmental parameters to which the cable may be exposed are: temperature 465*F, pressure 70 psig,, humidity 10C%, 8 radiation 1.96 x 10 radr TID, and barated water spray. The cable is required to remain operational for 100 days and to operate while submerged, post-Design Basis Accident (OCA). Testing of similar cable is reported in " Qualification Test of Aged and Unaged Cable Specimens Under a Simulated LOCA/CBE" June 1979 by Isomedix Inc. Submergence testing is reported in Essex Group, Inc. letters dated September 27, 1977 and November 4, 1980. The environmental parameters to which the cable was tested are: temperature 346 F, pressure 113 psig, humidity 100%, radiation 2.05 x 108 rads TID and borated water spray. Separate samples of cable were also subjected to submergence for periods up to 18 months. The DBA test duration was 34 days extended to 100 days by analysis. The test temperature coes not envelop the MSL3 temperature. The applicant has claimed that thermal lag analysis indicates that the temperature inside the cable will not rise above 305'F during a MSLB and therefore the 346*F test temperature contains adequate margin. The test temperature for MSLB remains an open item on this equipment pending an explanation by the applicant. It is concluded that the Essex low voltage power cable is qualified pending approval of the applicant's thermal lag analysis. Evidence to , support this conclusion is contained in the applicant's files. i l 16 L L
l ACCUSTIC FLOW SENSOR AND TRANSMITTER . Manufacturer: Technology for Energy Corporation /Encevco Model: 2273 AMI (sensor) . ', 504A (transmitter) 2273-C2 (cable assembly) The acoustic flow monitor systems are used to monitor safety valve and power-operated relief valve positions and to provide alarm indication if these valves are open. The flow sensors are located in the primary loco enclosure area and the transmitters are located in the piping penetration rooms. The maximum specified environmental parameters to which these units may be exposed are: temperature 465 F, pressure 70 psig, humidity 10C%, radiation 1.76 x 10 8rads TID, and borated water spray. The system is required to remain operational for 100 days post-0BA. Testing of a unit similar to those installed at the Midland plant is reported in " Final Qualification Report for Environmental and Seismic Testing of the TEC Valve Flow Monitoring System, Revision 2, S/TTR-03" by Technology for Energy Corporation. The environmental parameters to which the unit was tested are: temperature 510*F, pressure, 85 psig, humidity 8 100% RH, radiation 2.22 x 10 rads TID, and borated water spray. The test duration was 33 days extended to 100 days by analysis. The qualifiec life is 40 years provided critical components are replaced at specified intervals. It is concluded that the acoustic flow, monitor systems are pualified provided input and output leads to the transient shield are protected as
, recommended in the test report. Evidence to support this conclusion is contained in the applicants files.
17
ELECTRICAL PENETRATION MODIFICATION Manufacturer: Conax Model: Standard model The Conax penetrations are used to pass electrical energy through the Reactor Building containment wall. They are at various locations at elevations above 617'. The maximum specified environmental parameters to which the penetrations may be exposed are: temperature 465'F, pressure 70 psig, humidity 100%, radiation 1.95 x 108rads TIO, and borated water spray. The penetrations are to remain operational for 100 days post-DBA.
- Testing of similar units is reported in " Design Qualification Report for Feed through/ adapter module assemblies for Amphenol SAMS penetrations, Midland plant Unit 1 and 2," IPS-861 by Conax corporation. The environmental parameters to which these units were tested are: temperature 324*F, pressure 80 psig, humidity 100% radiation 2.24 x 100 rads TIO, and borated water spray. The test duration was 15 days extended to 100 days by analysis. Test parameters envelop the specified parameters by acequate margin with the exception of temperature for the MSLS. The applicant has claimed that thermal lag analysis indicates that the inside temperature of the penetrations will not rise above 251*F during MSLS and therefore the 324*F test temperature contains adequate margin. The test-temperature for MSLS remains an open item on this equipment pending an explanation by the applicant. ,
9 5 18
VALVE CpERATORS , Manufacturer: ITT General Controls Model: NH91 and NH93
= .
These valve operators are used as auxiliary feed water pump discharge valves and capacity control valves for service water to chillers outside of containment. The required environmental parameters are: temperature, 217'F, pressure, 2 psig, humidity, 100%, radiation, 5.4 x 103 rads TID, with a response time of 10.6 seconds and an operability period of'40 hours. Sample valve operators were subjected to environmental tests as reported in ITT General Controls report number 721.77.095 with the following demonstrated environmental parameters: Model, NH91/NH93, temperature, 330'f, pressure, 53 psig, radiation 3.96 x 10 7rads TIO, response time, 10.5 seconds with an operability period of 31 days. Accelerated aging was accomplished by subjecting the sample valves to a temperature of 60*C for 2160 hours to simulate 40 years at normal ambient temperatures. It has been stated by the applicant to change information in the EQ report to conform with the test documentation in the next revision of the EQ report. The qualified life is 40 years provided critical components are reolaced at specified intervals. It is concluded that the identified ITT General Controls valve operators are qualified for the specified environment and that evidence of qualification is contained in the appliants files. e e 19
(; TERMINAL'8 LOCKS Manufacturer: Multi-Amp, States Division " Model: NT, ZWM These terminal blocks are to be used throughout the plant outside of containment for electrical terminations. The applicant has stated however, they are not aware of specific locations where these terminal. blocks are installed. The required environmental parameters are: temperature, 249'F, pressure, 2 psig, humidity, 100%, radiation, 1.3 x 10 7rads TID, and an operability period of 100 days. The environmental qualification tests performed on sample terminal blocks-are reported in WYLE Laboratores nuclear environmental qualification test report number 44354-1. The maximum environmental qualification i parameters were achieved by type testing and analysis as follow: ! temperature, 264*F, pressure, 46.3 psig, humidity,100%, radiation, 7 9.0 x 10 rads TID, and an operability time of 100 days. Accelerated aging was performed by subjecting sample terminal blocks to 82*C for 163 hours simulating a 40 year life at a normal ambient temperature. It has been shown that the test parameters envelop the required parameters with acequate margin. It is concluded that the States Division terminal blocks are environmentally qualifiec for 40 years and evidence cf qualification is contained in the applicants files pending verification of correct installation in accorcance with qualification requirements by the resident NRC inspector. 20
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[,RC pcRu 335 U.s. NUCLEAR REGULATORY COMMISSION BIBLIOGRAPHIC DATA SHEET EGG-EA-6195 4 TITLE AND SU8 TITLE 2. Iteme atesel Audit of the Environmental Qualification of Safety-Related Electrical Equipment at the Midland Plant 3. RECIPIENT S ACCESSION NO.
. (Units 1 and 2)
- 7. AUTHORISI 5. DATE REPORT CCMPLE TED T. G. Humphrey, V. A. Stuart March I*" 1983
- 9. PERFORMING ORGANIZATION NAME AND MAILING ACORESS //ncivar Isa Coort CATE REPORT ISSUEO
** March I** 1983 EG&G Idaho, Inc. s. <i.,.e e, Idaho Falls, 10 83415
- 8. (Leave Na'al
- 12. SPONSORING ORGANIZATION NAME AND MAILING ACORESS trac / var lea Cooel , ,
Division of Engineering Office of Nuclear Regulatory Research is, piu so. U.S. Nuclear Regulatory Commission A6415 Washington, DC 20555
- 13. TYPE OF REPORT en Rico Covs mso linewswe asesi
- 15. SUPPLEVENTARY NOTES 14. ILeave an'es
- 86. ABSTR ACT 1200 woras or rent The Midland Nuclear Plant (Units 1 & 2) was audited to determine the environmental qualification of safety-related electrical equipment. Results of the audit are summarized in this report.
17 KEY WOROS ANO OOCUMENT ANALYSIS 17a CESCRIPTORS 170 ICENTIFIE RS.OPEN ENCEO TERVS 18 AV AILA81LITY STATEVENT 19 SE CURITY CLA3S tra,s recorrs 2f NO 08 PACES Unciassified Un1imi ted 23 My's fYC SS,fa.: sees 22.8meCE l Nec #cmM 335 ett ate { k _}}