ML20112J489
| ML20112J489 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 07/31/1983 |
| From: | Humphrey T, Stuart V EG&G, INC. |
| To: | NRC |
| Shared Package | |
| ML20105B661 | List: |
| References | |
| CON-FIN-A-6415, FOIA-84-262 EGG-EA-6339, NUDOCS 8501180298 | |
| Download: ML20112J489 (25) | |
Text
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EGG-EA-6339 4
JULY 1983 AUDIT OF THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT FOR THE STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM T. G. Humphrey V. A. Stuart Idaho National Engineering Laboratory Operated by the U.S. Department of Energy 3i
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j This is an informal report intended for use as a preliminary or working document kokI[8ff98840524
'i WILLIAMS 4-262 pop Prepared for the Q
E U E 6 1daho u.S. NUCLEAR' REGULATORY COMMISSION M
Under DOE Contract No. DE-AC07-761001570 FIN NO. A6415 y
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EGG-EA-5339 AUDIT OF THE ~ ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT FOR THE STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM Occket Nos. 50-482 and 50-483 T. G. Humphrey V. A. Stuart Published July 1983 Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Under DOE Contract No. OE-AC07-76ID01570 l
FIN No. A6415 f
ABSTRACT The Standardi:ed Nuclear Unit Power Plant System was audited to determine the environmental qualification of safety-related electrical equipment.
Results of the audit are summarized in this report.
1 1
i i
t NRC FIN No. A6415--Equipment Qualification Case Reviews ii
SUMMARY
An audit of the environmental qualification of safety-relatec electrical equipment for the Standardized Nuclear Unit Power Plant System was conducted by a, team comprised of representatives of the Reliability and Statistics Branch of EG&G Idaho, Inc'., and the Nuclear Regulatory Commission (NRC) staff. Qualification deficiencies for individual equipment items are provided in Appendix A.
Summaries of the central file reviews are provided in Appendix B.
As a result of the audit it was concluded that when the Standardized Nuclear Unit Power Plant System resolves the concerns noted in this report, their qualification program will be complete and in accordance with 10 CFR 50.49.
4 iii m
FORE 40R0 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 Branen.
The U.S. Nuclear Regulatory Commission funded the work under the authori:ation, B&R 20-19-40-41-2.
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CONTENTS ABSTRACT.............................................................
11
SUMMARY
111 FOREWORD..............................................................
iv 1.
INTRODUCTION.....................................................
1 2.
BACKGROUNO.......................................................
2 3.
PURPOSE..........................................................
3 4.
SCOPE............................................................
3 5.
EVA LU AT I O N.......................................................
3 6.
CONCLUSIONS......................................................
4 7.
REFERENCES.......................................................
4 APPENDIX A--QUALIFICATION DEFICIENCIES FOR INDIVIOUAL EQUIPMENT ITEMS..................................................
5 APPENDIX B--SUMMARIES OF THE STANDARDIZED NUCLEAR UNIT POWER P LANT SYSTEM FOR INDIVIOUAL REVIEWS..............................
11 v
AUDIT OF THE ENVIRONMENTAL QUALIFICATICN OF SAFETY-RELATED ELECTRICAL EOUIpMENT FOR THE STANDARDIZED NUCLEAR UNIT 9CWER PLANT SYSTEM
~
1.
INTRODUCTION Equipment which is used to perform a necessary safety function must be demonstrated to be capable of main aining functional operability under all service conditions postulated to occur during its installed life for tne time it is required to operate.
This requirement, which is emcedied in General Design Criteria 1 and 4 of Appendix A and Sections III, XI, and XVII of Appendix B to 10 CFR 50, is applicable to equipment located insice as well as outside containment. More detailed requirements and guidance relating to the methods and procedures for demonstrating this capability has been set forth in 10 CFR 50.49, " Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants," and NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment." This NUREG supplements IEEE Standard 323, and various NRC Regulatory Guides and industry stancards.
On June 20-23, 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 for the Standardized Nuclear Unit Power Plant System.
The Callaway and Wolfereek Nuclear Power Plants are specifically accressed in this report.
The work effort consisted of:
(a) a pre-audit review of tne licensee's submittal (Reference 1), (b) an audit of the licensee's central files for selected equipment items, and (c) an onsite visual insoection of the equipment items, both at the Callaway and the Wolfereek sites, for which the central files were audited.
Qualification deficiencies for individual equipment items are provided in Appencix A.
Summaries of the central file reviews are provided in Appendix 8.
1
2.
BACKGROUND NUREG-0588 wa's issued in Decemcer 1979 to promote a more orcerly anc systematic implementation of equipment qualification programs oy industry and to provide guidance to the NRC staff for its use in ongoing licensing reviews.
The positions contained in this report provide guidance on (1) how to establish environmental service conditions, (2) how to select methods which are considered appropriate for qualifying equipment in different areas of the plant, and (3) other areas such as margin, aging, and documentation.
In February 1980 the NRC requested certain near term Operating License (OL) applicants to review and evaluate the environmental qualification documentation for each item of safety related electric equipment and.to identify the degree to which their qualification programs comply with the staff positions discussed in NUREG-0588.
IE Bulletin 79-019 " Environmental Qualification of Class 1E Equipment," issued January 14, 1980, and its supplements dated February 29, September 30, and October 24, 1980 established environmental qualification requirements for operating reactors.
This bulletin and it's supplements were provided to OL applicants for consideration in their review. A final rule on environmental qualification of electric equipment-important to safety for nuclear power plants became effective on February 22, 1983.
This rule, Section 50.49 of 10 CFR Part 50, specifies the requirements to be met for demonstrating the environmental qualification of electrical equipment important to safety for nuclear power plants became effective on February 22,.1983. The rule also specifies the requirements to be met for demonstrating the environmental qualification of electrical equipment important to safety located in a harsh environment.
In accordance with 10 CFR 50.49, the electrical equipment in the Standardized Nuclear Unit Power Plant System (Callaway and Wolfereek Plants) may be qualified in accordance with the acceptance criteria specified in Category I of NUREG-0588.
The qualification requirements for mechanical equipment are principally contained in Appendices A and B of 10 CFR 50. The 2
~ qualification methods defined in NUREG-0588 can also be applied to
' mechanical equipment 3.
PURPOSE
- The purpose of this report is to evaluate the adecuacy of the i
Stancardized Nuclear Unit Power Plant System's environmental qualification program for electric equipment important to safety as defined in 10 CFR 50.49, and for safety-related mechanical equipment. A discussion of open items, as well as any unresolved issues, is provided in this report.
4.
SCOPE The scope of this report includes an evaluation of the completeness of the list of equipment to be qualified, the criteria which they must meet, the environments in which they must function, and an assessment of the qualification documentation for the equipment.
The principal area of review was the qualification of safety-related equipment wnich must function in order to prevent or mitigate the consecuences of a loss-of-coolant accident (LOCA) or high energy line break (HELS) inside or outside of containment, while subjected to tne harsh environments associated with thesa accidents.
5.
EVALUATION General concerns and comments resulting from both the audit and the pre-audit review of the Standardized Nuclear Unit Power Plant System's (SNUPPS) submittal are as follows:
1.
An explanation is needed as to what will be done wnen the cualified life of a piece of eruipment expires at a time less than 40 years.
2.
An explanation of the Main Steam Line Break (MSLB) thermal lag analysis should be inclucedLin the environmental qualification B
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t (EQ) suomittal and further, incivicual files wnich use tnis analysis should be identified.
3.
Documentation should be added to justify changes to existing files.
4.
Justification of margins should be proviced in the qualification files.
6.
CONCLUSIONS As a result of the audit it was concluded that the Standardized Nuclear Unit Power Plant System demonstrated a high level of effort toward the EQ program. When the Callaway and Wolfereek Plants, through the Standardized Nuclear Unit Power Plant System, resolve the concerns noted aoove, their EQ program will be complete and in accordance with 10 CFR 50.49.
7.
REFERENCES 1.
Environmental Qualification Report, Revision 1, Stancardizec Nuclear Unit Power Plant System.
2.
Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, NUREG-0588.
3.
IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations, IEEE Std. 323-1974 4
Code of Federal Regulations, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants, 10 CFR 50.49.
4
APPENDIX A EQUIPMENT QUALIFICATION STATUS e
5
APPENDIX A EQUIPMENT QUALIFICATION STATUS The attached tables list the status of Class IE equipment for the Standardized Nuclear Unit Power. Plant System (SNUPPS).
The codes below are usec for status designation.
SNUPPS Status Q
Qualified per NUREG-0588 requirements L
Data to be provided later AP Action Plan to be completed LO Limited Qualification TIP Testing in Progress Reviewer Evaluation A
Aging deficiency 0
Applicant awaiting documentation from vendor L
Qualification data to be provided later Q
Qualified R
Radiation deficiency 5
Submergence deficiency T
Temperature deficiency AC Accuracy deficiency CD Qualification Contingency deficiency CS Chemical Spray'dsficiency OT Operating Time deficiency QL Status of equipment upon Qualified Life expiration is unclear RQ To be replaced with qualified equipment IIP Testing in progress 7
STANDARDIZED NUCLEAR tlNIT POWER PLANT SYSTEM (SNUPPS) ENVIRONMENTAL QUALIFICATION REPORT SNUPPS lieviewer Section EEW sunber Equipment Description Manutacturer Status Ey luation E01013 E01033-1 Stash Connection Kit Raychem Corporation 4
4
[01013-2 Heat Shrinkable Field Spilce Raychem Corporataan Q
Q E01013-3 nuclear Motor Connection Kits Raychem Corporation 4
Q E01013 4-1 Cable End Seal Kit Raychem Corporation Q
Q E01013-5-1 Cable Breakout Kit Raychem Corporation Q
E018 E0l8-1 Motor Control Center Starters Gould incorporated AP L
E018-2 Motor Control Center Circuit Breakers Gould Incorporated AP L
E018-3 Motor Control Center Relays Gould Incorporated AP L
E028 E028-l Interconnecting Wiring for Local Control Stations Coasty (Rockbestos)
Q E028-2 Can Actuated Lighted Instrument and Control Constp (Electroswitch)
L L
5=ltch in local Control Station E028-3 Indicating Lights for Local Control Station?
L E028-4 Terminal 8tocks for Local Control Stations Buchanan L
L 1028-5 Resistors for Local Control Stations jtater)
L L
E028-6 Terminal Lugs for local Control Stations ILaterb L
L E028-7 Marathon Terminal Blocks for Terminal Somes Marathon Special Products Q
Q E029 E029-1 5 kV IfTK/HINS Type Power Cable Kerfte Q
Q (n
E 029-2 5 kV 5plices and Motor Termination Kits Kerfte Q
LO E035 E015-1 Electrical Penetration Assemblies Amphenol(Bunker-Ramn)
AP Oi, D E 035-2 Electrical Penetration Assendalles Amphenol (Bunker-kamo)
AP A, D E0158
[0358-1 Electrical Penetration Adapter Modules Conas 4
1 E 0358-2 Electrical Penetration Adapter Modules Conan Q
I, 05 E0358-3 Terminal Blocks Kulka LQ u
I EuS7 E057-1
- 60) Volt Copper Control Cable Rockbestos Q
I E057-2 600 Volt Copper Control Cable Rockbestos Q
I E057-3 600 Volt Copper Control Cable Roc kbestos Q
l 1057-4 600 Volt Copper Control Cable Rockbestos Q
I E051A EQ57A 600 Volt Copper Control Cable Anacosala-Ericsson Inc.
Q CS E0578 EU578 600 Volt Copper Control Cable Brand-Ren Q
1 E058 E058 600 Volt Copper Control Cable Anaconda-Ericsson Inc.
Q Q
E060 E060-1 ER-IlfY lasulated Coastal and Irlaajal Cable Brand-Rea 4
I E060-2 Nuclear Instrima atation Systeo Cable Assendalles Brand-Res ilP lir E061 E061 Eftm Insulated thermocouple Estension Cable Samuel Moore Q
l 1062 E062 M10 Volt Instrumentation Cable Boston Insulated Wire Q
Q O
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1 SIAfWARDIZED fiUCLEAR UNIT POWER PLANT SYSTEM (SNUPPS) ENVIRONMENTAL QUAllflCATION REPORT (continued)
$NUPPS Reviewer Sec t ion ElW hunter Equipment Description Manufacturer Status ivaluattun 1091 E093-1 Aozillary Relay Rack / Relays Consip Customline/Struthers-Dunn AP D
E093-2 Aunillary Relay Rack / Terminal Blocks Consip Customline/Amerace Corp.
AP D
E093-3 Ausillary Relay Rack / Cables Rockbestos AP L
[093-4 Auxillary Relay Rack / Fuse Blocks GIE Sylvania AP L
[093-5 Auxillary Relay Rack /lerminal lugs Thomas & Betts AP L
E093-6 Nulliary Relay Rack /8usbar Standuif (later)
AP L
J 301 J3OI Pressure Transmitter Rosemount Inc.
Q Q
J159 J359 Hydrogen Analyzer Cassip-Delphi, Inc.
Q Q
J361A J361A-1 Higli Range Radiation Monitor Detector General Atomic Co.
Q Q
J361A-2 Coastal Cable Rockbestos Q
Q J48I J481-1 Probe-Type Level Instrumentation Transamerica Delaval Inc.
Q Q
J5588 J5588 Resistance Temperature Detectors lieed Instrument Co.
Q Cs, Ac J60lA J601A muclear Service Control Valves Masonellan International LQ Ry 2
J60la J6018 Atmospheric Relief Valves Masonellan International LQ 1, kQ 2
e J601A J601A-l Solenoid Valves IIP llP J603A-2 Electric Conductor Seal Assemelles Conam Q
J605A J605A Butterfly Control Valves. Actuators F isher-Bettis Q
Q M)88 See Section Number W(AE-2)
M223A M223A-1 Valve Operator Anchor Darling /Limitorque Q
I, t'D, AC M223A-2 Valve Operator Anchor Darling /Limitorque Q
CD, AC M223C M223C Valve Operator Velan Engineering /Limitorque Q
AC,(D M2248 M2248 Valve Operator Velan Engineering /Limitorque Q
Q W25 M225-l Valve Operator Anchor Darling /L laitorque Q
(D, I, AC M225-2 Valve Operator An(hor Darling /Limitorque Q
AL, (D M231C M?31C Valve operator BorgWarner/L imitorque Q
I, (D AC N36 M236 Valve Operator f isher Controls /L imitorque Q
(D, AC M237 W 37-1 Valve operator I isher Controls /L leitorque Q
(D, AC M237-2 Valve Operator Fisher Controls /Limitorque Q
1, (D, AL W 37-3 Butterfly Valve, Actuator fisher-Bettis Q
I, AL
STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM (SNUPPS) ENVIRONMENTAL QUALIFICATION REPORT (c SteuPPS Revlemer Section EEW Ituneer Issulpment Description Manufacturer Status E va lualioni MEl2 pe612 Roan Coolers Carrier Corp. (Westinghouse)
AP A, D m ig.3 M619.3 Mydrogen Mixing Fans Joy Manufacturing Q
Q M620 M620 Containment Cooler American Air Filter (Joy /Nellance)
Q Q
M627A M627A-1 Pneumatic Damper Actuator Raymond Control Systems AP D
M627A-1 Electric Damper Actuator Raymond watrol Systems AP D
M628 M628 Mydraulic Actuator Anchor Darling AP D
M630 M630 Mydraullc Actuator Anchor Darling AP D
W(AE-2)
W(AE-2)-l targe Pump Motors Westinghouse Q
Q W(AE-2)-2 Eontainment spray Pump Motors ingersoll-Rand Co.
Q Q
W(E5E-l)
U(ESE-1)-1 Pressure Transmitter (Group A)
Barton Q
gt W(ESE-1)-2 Pressure Iransmitter (Group A)
Barton Q
QL W(ESE-3)
W(ESE-3)
Dif ferential Pressure Transmitters (Group A)
Barton Q
Q W(ESE-4)
W(E5E-4)
Dif ferential Pressure Transmitters (Group B)
Barton Q
yL W(E5F-5)
W(E5E-5)
Resistance Temperature Detector RdF Corporation Q
QL W(ESE-6)
W(ESE-6)
Resistance Temperature Detector RdF Corporation Q
yt W(if-2/5) W(if-2/5)
Safety-Related Solenoid Valves ASCO Q
Q W(if-3/6)
W(if-3/6)-l Externally skusated Limit Sultches leAMEO Q
4L W(if-3/6)-2 Externally Musented Limit Sultches leAMEO Q
QL W(if-4)
W(if-4) t imitorque Valve Electric Motor Operator Limitorque Q
yt, R I.
Stated by the applicant to be quallfled except for use la certain instrumentation circuits.
2.
Stated by th applicant to be quellfled pending qualification of limit switches.
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APPENDIX B SUMMARIES OF THE STANDARDIZED NUCLEAR UNIT PCWER PLANT SYSTEM CENTRAL FILE REVIEWS e
11
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APPENDIX B SUMMARIES OF THE STANDARDIZED NUCLEAR UNIT PCWER PLANT SYSTEM CENTRAL FILE REVIEWS 600-Volt Instrumentation Cable Manufacturer: Boston Insulated Wire & Cable Co. (BIW)
Model: EPR Insulation CSPE Jacketed The BIW instrumentation cable is used throughout containment at locations above and below flood level.
The maximum environmental parameters to which the cable may be exposed 7
are:
temperature, 385'F; pressure, 49 psig; radiation, 7.9 x 10 rads TID; humidity,100% and borated water spray at a maximum pH of 11.0.
Some of the cable is located below flood level and therefore, required to operate while submerged.
The operability recuirement is for six montns post-0BE.
Testing of similar cable is reported in " Boston Insulated Wire & Cable Company Prototype Test Documentation" P.O. No. 10466-E-062 BIW orders 60488 through 64092. The maximum environmental parameters to which the cable was tested are:
temperature, 340*F; pressure,105 psig; radiation, 0
2.0 x 10 rads TIO; humidity, 100%, and barated water spray at a pH of 10.5.
The test duration was 367 days.
The applicant claims, through thermal lag analysis, that the highest surface temperature reacned on :ne cable will be 295'F during an MSLB and therefore the test temperature of 340*F envelops the MSLB temperature with adequate margin.
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j It is concluced tnat the BIW instrumentation cable is qualifiec for use at SNUpPS plants provided that more information. supporting the thermal lag analysis is incluceo in the applicants E.Q. submittal.
Terminal Blocks
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Manufacturer: Marathon Special Products Model Number:
Series 142 NUC, 1500 NUC, 1600 NUC The Marathon Terminal Blocks as described in the equipment qualification package, are used for cable terminations throughout the containment.
The bounding environmental parameters are:
temoerature, 384.9'F MSLS (308.6 LOCA); pressure, 63 psia; radiation,1.802 x 108 rads TIO; numidity,100%; chemical spray of 2050 ppm baron concentration to a pH of 11.0, with a post-08A operability of 6 months. None of the terminal blocks are to be located below submergence level.
Three sets of terminal blocks were tested and the qualified parameters described in WYLE Laboratories Test Report Numcer 45603-1 are:
8 temperature,- 385'F; pressure, 83 psig; radiation, 2 x 10 rads TID; humidity,100%; chemical soray of 2000 ppm boron at a pH of between 8.5 and 10.5 for 30 days, and a post-0BA operability of more than 6 months.
The terminal blocks were thermally aged at 120*C for 444 hours0.00514 days <br />0.123 hours <br />7.34127e-4 weeks <br />1.68942e-4 months <br /> which represents a 40 year qualified life at normal operating temperatures.
During the LOCA test the insulation resistance of all of the scecimens 6
in the 528 volt box dropped to 0.5 x 10 ohms (minimum 6
required--I x 10 ohms) and did not comply with requirements specifying maximum leakage current.
The specimens in the 132 volt and 264 volt boxes however did meet all acceptance criteria.
The applicant has stated tnat these terminal blocks will not be used in circuit applications of greater than 120 volts. The temperature margin as originally stated in the cualification package was insufficient.
The applicant nas stated that tne s
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margin is approximately 85*F and will' update the qualification package to reflect this temperature margin.
It is concluced that the Marathon terminal blocks, model series 142 NUC, 1500 NUC, and 1600 NUC, are qualified for use at the Callaway and Wolfc' reek Nuclear Power Stations in circuit applications not exceeding 120 volts and the appifcant has adequate documentation to support this conclusion.
Probe Type Level Instrumentation
-Manufacturer:
Transamerica Delaval Model: XM-54852, 3, and 4 (Transmitter)
LS-57761 and 3 (Switches)
These transmitters are located at various locations inside containment and,in the auxiliary building. They are used to sense fluid levels in various plant sumps.
The maximum environmental parameters to wnica these units may be e
exposed are:
temperature, 385'F; pressure, 48 psig; radiation, 0
1.14 x 10 rads TIO; humidity, 100%; and borated water spray with a pH range of 8.0 to 11.0.
The transmitters are also located below flood level and therefore required to operate while submerged.
The operability requirement is six montns post-0BE with an accuracy requirement of 13% of full scale.
4 Testing of similar transmitters is reported in Wyle Nuclear Environmental Qualification test report No. 45700-1.
The maximum environmental parameters to which the transmitters were tested are:
8 temperature, 415'F; pressure, 66 psig; radiation, 1.16 x 10 rads TIO; humidity 100% and borated water spray with a pH range of 8.5 to 11.0.
The DSE test duration was for 30 days extended to six months by analysis.
The accuracy was demonstrated to be within 3% of full scale.
The units were also tested for submergence and found to be cualified.
Thermal aging was for 90 days at 120*C, yiel, ding a qualified life of greater than 40 years.
15
r1 It is concluded that the Delaval level transmitters are qualifiec for use at SNUPPS proviced qualified cable and connecting splices are usec.
Evidence to support this conclusion is contained in the acplicant's files.
Manufacturer: ASCO Model Number: Np831655E The ASCO solenoid valves addressed in the Equipment Qualification Test Report (EQTR) and Equipment Qualification Data Package (EQCP) are used for system isolation in various locations both inside and outside containment.
The bounding environmental parameters are:
temperature, 384.9'F MSLB (308.6*F LOCA); pressure, 63 psia; radiation,1.2 x 108 rads TID; humidity,100%; chemical spray of 1950-2050 ppm boren concentration to a pH of 11.0, with a post-0BA operability of 6 months.
Ten of the solenoid valves are stated to be below the submergence level but suomerged operation of these valves is not requirec.
The qualified parameters as described in :ne Westinghouse Test Report EQTR-H02A/H05A and EQOP HE-2/5 are: temperature, 420*F; pressure, 57 psig; 8
radiation, 2 x 10 rads TID: humidity, 100%; with a chemical spray concentration of 2500 ppm boron and a pH of 10.5 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The
-demonstrated operability is greater than 6 months post-CBA. Westinghouse has stated that the solenoid valves must be installed with the opening to the solenoid enclosure from the conduit hub effectively sealed from exterior moisture. Westinghouse further has stated that Conax type connectors are to be installed on the solenoid valves.
The applicant has stated that the installation process of the Conax connectors is underway and will be completed in both the Callaway and Wolfereek stations prior to fuel load.
Further, the solenoid valves have a qualified life of 3 years and the applicant has stated that these solenoid valves will be replacea upon expiration of the qualified life.
It is concluded that the ASCO solenoid valves model NP831655E, with the conax type connectors installed are cualified for use at the Callaway 16
and Wolfereek Nuclear Power Stations and the aoplicant has aceouate documentation to suoport this cerclusion.
Differential pressure Transmitter Manufacturer:
Earton Model:
764 The Bartor pressure transmitters are located inside containment anc are used for steam generator and pressurizer level monitoring.
The maximum environmental parameters to which these units may be exposed are:
temperature, 385'F; pressure, 49 psig; radiation, 7
6.32 x 10 rads TID; humidity, 100%; and borated water spray with a pH of 11.0.
The transmitters are not located below flood level. Accuracy requirements are !1C% to :15% depending on transmitter use.
The operability requirement is 6 months post-08A.
Testing of similar transmitters is reported in Westinghouse reports ECTR E03A and E00P ESE-3.
The maximum environmental parameters to whien the transmitters were testec are:
temperature, 420'F; pressure, 57 psig; 7
radiation, 6.8 x 10 rads TID; humidity, 100% and borated water spray with a pH of 10.7.
The test duration was 15 days extended to 6 months by analysis.
During testing a problem developed due to poor contact between
- ne strain gauge and the circuit board.
The problem was solvec by soldering this connection.
The qualified life of the transmitters is six years provided the cover 0-rings are replaced each time the cover is removed or every two years, whichever comes first.
The applicant concludes that the Barton 764 is qualified for use at the $NUPPS plants.
The reviewer agrees with this conclusion provided the following two conditions are met and documented in the qualification files:
1.
The modification to solder the connection between the strain gauge and the circuit board has been mace on all SNUP S Earton 764 transmitters.
17
2.
A statement of similarity between the testec transmitters and those installed at the $NUPPS plants is proviced.
Hydrogen Mixing Fans Manufacturer: Joy / Reliance Model Number:
445T Frame Motor These fans, manufactured by Joy / Reliance, are used as nycrogen mixing fans inside containment.
The counding environmental parameters are:
temperature, 308.6*F; 0
pressure, 63 psia; radiation, 1.75 x 10 rads TIO; humidity,100*;;
chemical spray to a concentration of 2050 ppm boron with a cH of 11.0.
The recuired post-accident operability is 6 months.
Qualification testing was performed as described in the Joy Qualification Recort Numbers X-604 and M619.3-0007-04 The parameters to wnien tnese fans are qualified are:
temperature, 350*F; oressure, 80 osig; 8
ractation, 2 x 10 rads TIO; humicity,100*4; chemical spray at a concentration of 3000 ppm boron and a DH of 10.5 for 7 cays.
The comonstrated post-accident operability is for more snan 6 months.
Thermal aging was completed by subjecting the unit to 213.3'C for 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> which is equivalent to 22.78 years at normal coerating temoeratures (120'F).
Approximately 122 days into the post-LOCA test a bearing on the unit failed.
Extensive research and documentation was shown in the applicants files to support the conclusion that the bearing failed cue to an installation error by a field representative.
The vencer has stated, and the applicant concurs, that any bearing corrective maintenance will be cone by the vender at the manufacturing facility. A concern of similarity between the tested piece of equipment and the actual installed piece of ecutoment is to oe addressed by the applicant at a future cate.
18
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It is concluced that the hydrogen mixing fans, manufactured by Jcy/ Reliance, are qualified for use at the Callaway and Wolfereek Nuclear Power Stations provided that a statement of similarity between tne testec and installed equipment is submitted by the applicant prior to fuel load.
P Pressure Transmitter Manufacturer:
Rosemount Inc.
l-Model:
11538 All of the Rosemount transmitters which the applicant considers qualified are located outside containment.
Those which are inside containment are not considered qualified to date.
The maximum environmental parameters to which the transmitters may be 6
exposed are:
temperature,190*F; pressure, 2 psig; radiation, 2.15 x 10 rads TID; and humidity 100f., They are required to operate for six months cost-0BE with a required accuracy of
+8*.' uoper range limit.
Testing of these transmitters is reported in Rosemount Test Recort 108025, revision A.
The maximum environmental parameters to wnich they were tested are:
temperature, 318'F; pressure, 72 psig; radiation, 7
2.21 x 10 rads TID; and humidity, 100%.
The test duration was 23 cays extended to six months by analysis.
The tested transmitters demonstrated an accuracy of 3.19f. upper range limit.
The qualified life is 9.5 years.
It is concluded that the Rosemount Model 11538 transmitters are qualified for use outside containment provided recommended maintenance is i
performed.
This conclusion is supported by information contained in the amplicants files.
I i
e I
l 19
I Containment Cooler Manufacturer: American Air Filter (Joy / Reliance)
Model Numoer:
5005 Frame These units, located in containment, are manufactured by American Air Filter (Joy / Reliance) and are used as part of the containment air cooling system.
The bounding environmental parameters are:
temperature, 308.6'F (LOCA) and 384.9'F (MSL3); pressure, 63 psia; radiation,1.75 x 100 rads TID; humidity, 100%; cnemical spray at a concentration of 2050 ppm boron with a pH of 11.0.
The required post accident operability is 6 months.
Qualification testing was performed as described in the Joy Qualification Report Numbers X-604, M619.3-0007-04, and M620-049-03.
The parameters to which these units are qualified are:
temoerature, 350*F; 8
oressure, 80 psig; radiation, 2 x 10 rads; humidity, 1004: enemical soray at a concentration of 3000 pom boren and a pH of 10.5 for 7 days.
Thermal. aging was ccmoleted by suojecting the fan units to 213*C for 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> which simulated 40 years at 10S*C, The demonstrated post-accident operability is for more than 6 months.
The applicant has snown that although MSLB temperatures in containment spike to 384,9'F, the actual temperature the unit will be exoosed to is 247'F.
This is based on the motor / fan being on the effluent side of the cooling cotis.
Approximately 122 days into the post-LOCA test a bearing on the unit failed.
Extensive documentation was included in the applicants files to sucport the conclusion that the bearing failed due to an installation error by a field representative.
The vencor, witn the concurrence of the appitcant, has stated that the bearings are not to be repla,ced in the field but rather the entire unit is to be removed and sent to the manufacturing facility for corrective maintenance.
It is concluded that the containment coolers manufacture:: by American Air Filter (Joy / Reliance) are Qualified for use at the C4114way and Wolfereek Nuclear Power Stations and adequate documentation to succort this conclusion exists in the applicants files.
20
-- ~.
nc nom 335 v.s. NucLEAn cicutAro;;v commissicN ii.n BIBLIOGRAPHIC DATA SHEET EGG-EA-6339 A firLE ANo svarirLE
- 2. Ite=e m-i Audit of the Environmental Qualification of Safety-Related Electrical Equipment for the Standardized
- s. aEcipiENr s Ac:EssmN No.
Nuclear Unit Power Plant System 7 AufMOR'SI
- 5. D ATE REPC Ar COVPLE TED ucNTw jveam T. G. Humphrey, V. A. Stuart July 1983 9 PERPORVING ORGANi2A TICN N AME ANO \\ TAILING ACORESS t/ae/vor 2,0 Cocel CATE REPORT :$5 LED l
l YONfw lvtAm July 1001 EG&G Idaho, Inc, e _ ft,,,,, e,
Idaho Falls, ID 8.' ' 15 8 (Lt.e genes
- 12. $PCN$0 ming O AG ANIZAf CN NAVE AND V AILINO A00ME53 (tactuoe l<a Cooel 77 7
Division of Encineerino Office of Nuclear osame oemil e W is nN No.
U.S. Nuclear Regulatory Commission Washington, DC 20555 A6415 13 fvPE CF REPORT eE mico cove mE o t/acr s.ve mesi w
1
?S SUP8LEVENTARY N0fts 1 A (te=e eyes to A8$7m ACT 1100 wores or.essi The Standardized Nuclear Unit Power Plant System was audited to determine the i
environmental qualification of safety-related electrical equip. rent.
Results of the audit are summarized in this report.
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i te Av AiLAsitifv stativtNT is si cw i fy *. ass r...esen.
J ' N o - s # A :,8 3 a
i Unclassified Un1imi ted
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