ML20062A494
| ML20062A494 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/02/1982 |
| From: | Repka D NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Brenner L, Carpenter J, Morris P Atomic Safety and Licensing Board Panel |
| References | |
| ISSUANCES-OL, NUDOCS 8208040017 | |
| Download: ML20062A494 (19) | |
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'o UNITED STATES
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'g NUCLEAR REGULATORY COMMISSION
.-E WASHINGTON, D. C. 205 5 Q...../
August 2,1982 Lawrence Brenner, Esq.
Dr. James L. Carpenter Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Peter A. Morris Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Conmission Washington, D.C. 20555 In the Matter of Long Island Lighting Company (Shoreham Nuclear Power Station, Unit 1)
Docket No. 50-322 (0L)
Dear Administrative Judges:
On June 2 and 3, 1982, the NRC Staff conducted a re-audit of the Shoreham environmental qualification files for safety-related electrical equipment.
This pertains to SER open item #9, and is the subject of unscheduled contentions SC 8/ SOC 19(h) and SC 32/ SOC 19(f).
Attached for the information of the Board is the Staff's Request for Additional Information, dated July 22, 1982, generated by the re-audit.
Attached to the information request is the Staff's trip report, which specifies the equipment for which further documentation is required.
It should be noted that two of the items requiring additional information from.
the Applicant are the 100 and 200 Series, GE Electrical Penetrations.
Sincerely, k
e.cb David A. Repka 1
Counsel for NRC Staff
Enclosures:
As stated cc:
See page two h
8208040017 820802 PDR ADOCK 05000322 O
cc:
(w/ enclosures)
Matthew J. Kelly, Esq.
Ralph Shapiro, Esq.
Howard L. Blau Esq.
W. Taylor Reveley, III, Esq.
Stephen B. Latham, Esq.
John F. Shea, III, Esq.
Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Board Panel l
Herbert H. Brown, Esq.
Lawrence Coe Lanpher, Esq.
Karla J. Letsche, Esq.
Docketing and Service Section Edward M. Barrett, Esq.
Mr. Brian McCaffrey Marc W. Goldsmith David H. Gilmartin, Esq.
Mr. Jeff Smith MHB Technical Associates Hon. Peter Cohalan Mr. Jay Dunkleberger P
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DATE :08/02/82
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UNITED STATES
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JUL 2 2 1982 Docket No. 50-322 Mr. M. S. Pollock Vice President - Nuclear Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801
Dear Mr. Pollock:
Subject:
Request for Additional Information - Shoreham Nuclear Power Station As a result of our review of your application for an operating license for l.
the Shoreham Nuclear Power Station and the re-audit of your documentation for environmental qualification of Class lE electrical equipment per NUREG-0588, we find that we need additional information regarding the environmental qualification of electrical equipment. Please find attached the trip report filed by the NRC Staff discussing this topic. The specific requests for information are included in Attachment 3 to Enclosure 1.
Please inform the staff within seven days of receipt of this letter your schedule for forwarding this infonnation.
If you have any questions on this matter, please contact NRC Project Manager, Edward J. Weinkam at (301) 492-8430 Sincerely,
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WUS$V A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
As Stated cc: See next page l
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Vice President - Nuclear
'Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 c::
Howard L. Blau, Esquire MHB Technical Associates 1723 HamH ton Avenue, Su b K N
r dge Ro San J se, California 95125 Hicksville,',New York 11801 Stephen Latham, Esquire Mr. Jay Dunkleberger Twomey,:Latham & Shea 33 he co Str et ency u 1.ng Empire State Plaza Riverhead, New York 11901 Albany, New York 12223 Matthew. J. Kelly, Esq.
Energy Research Group, Inc'.'
Staff Courisel'
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New York State Public Service Commission 400-1 Totten Pond Road Three Rockefeller Plaza Waltham, Massachusetts 02154 Albany, New York 12223 E
ore iuclear Power Station A
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n al Environmental Protection Bureau d ng ver ew ork 11792 New York State Department of Law 2 World Trade tenter W. Taylor Reveley, III, Esquire Hunton & Williams New York, New York 10047 Post Office Box 1535 Richmond, Virginia 23212 Resident Inspector Shoreham NPS, U.S.N.R.C.
Post Office Box-B' l
Ralph Shapiro, Esqu' ire.
Rocky Point, New York,l'1778 Cammer.& Shapiro
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9 East 40th Street New Yo'rk, New York 10016 Herbert H. Brown, Esq.
Kirkpatrick, Lockhart, Hill, s
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Long Island Lighting Company Washington, D.C.
20036 175 E. 01d Co.untry Road Hicksville', New' York 1T801 -
Lawrence Coe Lanpher, Esq.
Kirkpatrick, Lockhart, Hill, Honorable Peter Cohalan Christopher.& Phillips Suffolk County Executive 1900 M Street, N.W.
County Executive / Legislative Building Washington, D.C.
20036 Veteran's Memorial Hignway Hauppauge, New York.11788 Karla J. Letsche, Esq.
Kirkpatrick, Lockhart, Hill, 3
David Gilmartin, Esquire Christopher & Phillips Suffolk County Attorney 1900 M Street, N.W.
County Executive / Legislative Building Washington, D.C.
20036 Veteran's Memorial Highway Hauppauge, New York 11788 o
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NUCLEAR REGULATORY COMMISSION n
h WASHtNGToN. D. C. 20665 N 30 g MEMORANDUM FOR:
Zoltan R. Rosztoczy, Chief Equipment Qualification Branch Division of Engineering FROM:
J. E. Kennedy Equipment Qualification Branch Division of Engineering THRU:
R. G. LaGrange, Section Leader Equipment Qualification Branch Division of Engineering
SUBJECT:
TRIP REPORT - RE-AUDIT OF LONG ISLAND LIGHTING COMPANY'S DOCUMENTATION FOR ENVIRONMENTAL QUALIFICATION OF CLASS 1E ELECTRICAL EQUIPMENT PER NUREG-0588-FOR SHOREHAM NUCLEAR POWER STATION Plant Name:
Shoreham Nuclear Power Station Unit 1 Docxet No.:
50-322 Licensing Stage:
OL Responsible Branch:
Licensing Branch #2 Project Manager:
R. Gilbert Review Status:
Continuing The NRC staff and consultants from EG&G Idaho, Inc., conducted a re-audit of the Shoreham Nuclear Power Station environmental qualification files for safety-related electrical equipment on June 2 and 3, 1982.
This was a follow-up audit to one conducted in the last week of April and described in a trip report dated June 8, 1982.
At that time, the files were not considered to be sufficiently complete.
After the initial audit, the applicant reviewed all of the equipment files and made appropriate revisions to address the generic comments and deficiencies identified by the audit team.
Based on the results of the first audit, a two day follow-up audit was deemed sufficient for reaching a conclusion on the adequacy of the central files.
The list of attendees is provided in Attachment 1 and a list of the audited equipment in Attachment 2. discusses in detail the evaluation of individual files.
The conclusions of the audit team are that, overall, the files were significantly improved from the previous audit and that except for one file, satisfactory evidence of qualification is now contained therein.
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James E. Kennedy Equipment Qualification Branch Attachments:
As stated
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s Zoltan R. Rosztoczy 2
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R. Vollmer W. Johnston A. Schwencer J. LaGrange (R. Gilkaat-M. Yost, EGM T. Humphrey, EG&G R. Borgen, EG&G J. Higgins, Region I EQ Section l
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List of Attendees June 2-3, 1982 Audit NRC SWEC J. E. Kennedy Y. Can J. C. Higgins, Region I D. S. Papp R. Snyder EG&G Idaho, Inc.
EDS Nuclear M. W. Yost R. A. Borgen N. K. Woodward T. G. Humphrey W. V. Be11ando S. Pauly LILCO Wyle Laboratories J. F. Etzweiler R. W. Grunseich R. Bennett M. H. Milligan J. L. Smith MHB Associates C. Roller 1
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Items Selected for Shoreham Envirorimental Qu'alification Audit June 2-3, 1982 s
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Equipment Identification Description Manufacturer Model No.
Number 1.
Pressure Switch Barksdale BIT-M12SS 1E11*PS134A 2.
Pressure Switch Barton 288A 1E41*PS023C 3.
Penetration GE 100 Series 1T23-Z-EA2 4.
Penetration GE 200 Series 1T23-7.-ECS 4
5.
Transformer Magnetics L-12514 1P35*T-B2' 6.
Level Switch Magnetrol 3.5-751-1XMPG 1E41*LSD[2A 7.
Position Switch Namco EA180 1E11*PNS031C 8.
Fan Motor Westinghouse 405TZ 1T46*FN0038-
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Lugs & Splices Amp 52900-53900 10.
Transmitter Rosemount 1151 1821*LT154A
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Drywell Hydrogen Delphi 7045-N5-4702-0000 IT48*H2I1153X \\
Analyzer Indicator i
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N Evaluation of Files 1.
Pressure Switch, Barksdale Model B1T-M12SS Plant Identification No. 1E11*PS134A This pressure switch is used in the.RHR purr.p discharge ard is located in the reactor building secondary.
The specified accident conditions are a peak temperature of 150*F, a peak pressure of 0.9 psig; 100% relative humidity.
and a radiation dose of 2x108 rads.
The switch is required to function' fee seven days.
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The environmental qualification data for this component are reccrded in Barks-
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dale Procedure 9993, Test Report No. 3018A, and EDS c. lculation nucers,
a 0630-001-013 and 0630-001-014.
The switch was testid'at 212*F, 0.25 psig,
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,e 100% relative humidity for six hours, and was demonstrated to be q0alified for a radiation dose of 3x10s rads.
AnalysisoEthe[testdatawasperformed to show operability for seven days.
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AIF components are qualified for forty years except the'aeopreng face gasket,
with a cualified lifelof six years.
This information will be. put intr the plant preventive maintenance program to ensure the. device does not exceed its~
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qualified life.
It is concluded that the Barksdale pressure switch is qualifiss for the
.g environment specified.
- 2. ' Pressure Switch, Barton Mcdel 288A Plant Identification No. 1E41*FS023C j.,
This p essure switch is used to trip the HPCI[td'roine[on low steam pressure and is located in the reactor building secondary.
The specified accident
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a parameters are a peak temperature of 130'F,,a pressure of 0.9 psig, 100% rela-tive humidity, a "adiation dose of 7xlG5 rads during a LOCA, and an operability time requirement o'f twelve hours.
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Environmental testing, was performed or, identical models of this pressure switch and results are reported in Barton Tsst; Report No. 9999.1217.2, Rev.
1 and Report No.--R3-288A-1.
Calculations for operability time and qualified life were included in the central file.
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The mc :imum envir9 mental parameters that the pressure switches were subjected to were a temperature of 212*F, a pressure of seven inches water column, 100%
relatire humidity,'3x108 ra'ds radiation dose, and a test duration of six hours.
Ar.alysis extends the operating time to fifty-six hours and aging cal-i:ulations provided a qualified life of fortkyears using Arrhenius methodology.
This file had been audited in April and was' noticonsidered to be satisfactory at that? time.
Concerns identified during the pr'evious audit have been cort'ectc}. by providing:
(r2) Additional information to the file verifying energized switches during the st'eam test and c4libration data taken immediately after the steam test.
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(b) Additional ' analysis 3urtifying the qisalification methods.
(c) Separation of the pressure switcne's into three groups depending on location and function, with qual,1f fcation being claimed for only one l
group.
The other groups require further testing or analysis before full qualification can he attained.
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It.is concluded that tbp doedientation presented in the applicant's file is ade-quatefordemonstratingiq'alificationofselectedswitches.
The particular item u
l of equipment chosen for audit is not qualified, but a corrective action plan acceptable to' the staff has been established.
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Shorcham Re-audit /Att. 3 3.
Electrical Penetration, GE Series 100 Medium Voltage Plant Identification No.1T23-I-WA3-1 There are three GE medium voltage electrical penetrations which contain con-ductors supplying power to the recirculation pump motors in the drywell.
Since the recirculation pumps are classified as non-1E, the only safety function the penetrations perform is maintaining containment isolation.
The limiting environmental conditions during an accident are temperature, 340*F; pressure, 48 psig; 100% relative humidity; demineralized spray; and radiation, 1.2x10s rads T.I.D.
The accident duration is 180 days.
Secondary side seals do not experience abnormal temperatures during a LOCA.
The test report con-tained in the central file was GE No. 74-502-2 " Medium Voltage Qualification Test Report." Sequential radiation and LOCA testing was performed on penetrations with a dose of 5x107 rads and a peak temperature of 340*F for four hours. Two radiation calculations, one in the test report and another (SWPS-1-VR-22-F) in the file, were performed to reduce the required dose to 3.9x107 rads.
Both of these should be provided to the staff for verification of the postulated dose.
Leak-tight integrity was maintained after testing and analysis was used to demonstrate that the safety function would be maintained for 180 days.
The margins on time and temperature in the short duration test were utilized in Arrhenius calculations to demonstrate a more severe condition than the 180-day accident duration.
The limiting material required for containment isolation was EPR.
The applicant, however, should identify to the staff other materials which are required for containment integrity.
The penetration also contains a seal located in a zone outside the drywell which experiences no change from normal conditions following a LOCA.
The most recent revision to the EQSR indicates that these penetrations per-form a safety function for line breaks outside of the drywell.
Qualification for the environmental conditions of these breaks was not addressed.
Previous submittals, however, had prescribed functionability for a LOCA only.
Clari-fication in this area is therefore required.
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Shoreham RI-audit /Att. 3 Thermal aging was not performed before LOCA testing and the thermal cycling described in GE Test Report 74-502-2 was inconclusive since no results were presented.
However, the applicant calculated an expected life for EPR under normal conditions in excess of 40 years.
The applicant committed to Type B testing as described in Appendix J of 10CFR Part 50 for periodically verifying the leaktight integrity of these penetrations.
The applicant should confirm that epoxy or rubber seals in the conductor modules will be subjected to leak testing in this program, and should describe the corrective action to be taken if unacceptable leak rates are obtained in service.
The staff reviewed IE Bulletin 77-07 concerning GE 100 Series penetrations for applicability at Shoreham.
The adverse operating experience described in this bulletin relates to electrical insulation failures and does not impact the qualification of penetrations which do not carry 1E power.
The staff finds these penetration's acceptable subject to receipt of the con-firmatory information requested above.
4.
Electrical Penetrations, GE Series 200 Low Voltage Plant Identification No. 1T23-Z-ECS These penetrations were reviewed during the first audit,but were not considered complete at that time.
For the second audit, additional information had been placed in the central file and the status changed to qualified.
These penetrations are located in the drywell (a portion of the penetration is in the secondary containment), and are exposed to a composite accident environ-ment consisting of a 340*F peak temperature, 48 psig peak pressure, 100% relative humidity, demineralized spray, and 1.2x10s rads radiation dose.
The required operability time is 180 days.
The principal test report in the central file was GE No. 994-76-018 Rev. 1 "200 Series Low Voltage Electric Penetration Qualification Test Report." A demonstration of leaktight integrity was presented for penetrations which had 4
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. Shoreham R;-audit /Att. 3 been sequentially exposed to thermal cycle aging, radiation, overcurrent, and LOCA tests.
Although the LOCA test duration was only 13 days, analysis was utilized to demonstrate that the safety function would be maintained for 180 days.
This included Arrhenius calculations and the consideration of the secondary side seal experiencing no abnormal temperatures during a LOCA.
The applicant did not address, however, high energy line break conditions out-side containment and their effect on secondary seal integrity.
It should be noted that the original submittal stated that these penetrations performed a safety function only for a LOCA.
In addition, the radiation dose on the secondary seal was only 1.3x10s rads, compared with a postulated value of 4x108 rads.
The file was also reviewed for a demonstration of electrical operability during testing.
Unlike the 100 Series penetrations, 'the 200 Series penetra-tions supply power to 1E equipment in the drywell.
The referenced test report and analysis performed by the applicant are insufficient for demonstrating that the penetrations can carry rated current and voltage under accident conditions.
In one sequence of tests, only current was applied during the LOCA portion of testing and for a duration of only 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The inability to apply rated voltage was attributed to problems in the test set-up.
The applicant attempted to demonstrate 180-day operability by Arrhenius analysis.
However, a 13-day test duration was used in this calculation, while electrical testing was only performed for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and, as noted previously, was incom-plete for demonstrating ability to carry rated voltage.
A second LOCA test was performed on backup modules of three different wire gages.
For two of the modules, only " operating" voltage was described as being applied during testing and for a duration of only 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
Analysis to demonstrate 180-day operability was not performed for these test data.
A#8 AWG module was LOCA tested but experienced failures in two of five cables.
An unspecified voltage was applied at a lower temperature (320 F) to the three remaining cables.
The test rcport did not state that rated current had been applied during this test.
The report indicated that the cable failures were due to contact with the inside of the autoclave.
In general analysis of failures due to test set-up problems or attributing failures to random causes is not adequate for 5
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Shorehm R2-audit /Att. 3 demonstrating qualification without additional conclusive evidence.
In this instance, testing difficulties had been previously experienced and a large per-centage failed in testing.
In addition, it is not clear that rated current and voltage had been applied at the peak temperature.
The values selected for voltage and current should be compared with the values required at Shoreham.
No basis for their selection is currently given in the file.
Aging analysis was performed on an EPR "C" ring, which has a qualified life of five years, and EMR 300 epoxy which provides for containment isolation and acts as an electrical insulator.
A greater than 40 year qualified life was estab-lished by comparison with data for N229 epoxy used in the 100 series penetra-tions.
The staff does not agree with this evaluation.
IE Bulletin 77-07 and related reports describe adverse operating experiences with N229 epoxy.
It is therefore appropriate that the applicant describe the surveillance program to be utilized for monitoring or detecting inservice degradation of these penetrations, if one is to be established.
Although a commitment to Appendix J leak testing was made for 100 Series penetrations, none has.been made for the 200 Series.
In addition, since these penetrations carry 1E power, consideration should be given to periodic checks for electrical integrity (insulation resistance, e.g.) and trend analysis of surveillance data.
Other approaches, such as analysis of EMR 300 test data, may be acceptable.
If a t'est program is to be utilized for moni-toring inservice degradation it should be submitted to the staff for review and evalcation.
The frequency of surveillance, type of testing, minimum acceptable values, and corrective action for unacceptable test results described.
The file for the 200 Series penetration is not considered adequate for demon-strating qualification at this time.
Additional information addressing the concerns noted above should be obtained and provided to the staff, or a commit-ment to additional testing provided.
5.
Transformer, Magnetics Model No. L-12514 Plant Identification No. 1R35*T-B2 This transformer supplies electrical power to several Class 1E loads, including
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gas analyzers and radiation monitoring panels, and is located in the reactor building secondary.
The only harsh environmental condition is a radiation dose of 3.06x105 rads.
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Sh:rsham Re-audit /Att. 3 Wyle Laboratories Report No. 17464-1302 demonstrated radiation qualification.
It was.shown that the most susceptible materials will exhibit little or no degradation at 3.06x105 rads with adequate margin.
The same report calculates a qualified life by material analysis using Arrhenius methodology and concludes that at loads less than 90% of rated load, a lifetime of greater than 40 years is shown.
A load study is supplied showing loading of 33%.
It is concluded that the Magnetics transformer Model No. L12514 is qualified for the environment specified and that satisfactory evidence of qualification is contained in the central file.
6.
Level Switch, Magnetrol Model No. 3.5-751-1X-MPG-M14HY Plant Identification No. 1E41*L5092A These level switches are located in the reactor building and are used to transfer suction from the condensate tank to the suppression pool on high. pool level.
The specified accident environmental parameters are as follows:
temperature, 150 F; pressure, 0.9 psig; 100% relative humidity; radiation, 6.5x105 rads; and an operability time of twelve hours.
Environmental testing of a similar level switch is recorded in Wyle Labora-tories Report No. 43235-1, Revision A.
The maximum environmental parameters that the level switch was subjected to are as follows:
+emperature, 300 F; pressure, atmospheric; 100% relative humidity; radiation, 4.4x104 rads for the device and 3.3x10s rads for the separate components in the device.
The test duration was for 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />.
The test margins are considered adequate..
except for pressure which is insignificant.
The qualified life is six years based on a " weak link" analysis.-
It is concluded that this Magnetrol level switch is qualified for the environment specified.
7.
Position Switch, Namco Model No. EA180-11302 Plant Identification No.1D11*PNS031C T.his device is used to indicate the RHR pump suction valve position and is 7
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_Sh:reham R;-audit /Att. 3 located in the reactor building secondary. The specified accident environ-mental parameters are as follows:
temperature, 178*F; pressure, 0.9 psig; 100% relative humidity; radiation, 5.75x108 rads; and operating time, 180 days.
The test reports supporting qualification are " Qualification of Namco Controls Limit Switch Model EA180 to IEEE Standards 344-1975, 323-1974, and 382-1972" Rev.1 dated September 5,1978, " Qualification of EA180 Series Limit Switches fo" Use in Nuclear Power Plants," No. QTR Rev. 3 dated August 30, 1981, and Wyle Laboratories Assessment Report No. 17464-6002 dated February 26, 1982.
The environmental parameters this switch was subjected to are as follows:
temperature, 340 F; pressure, 100 psig; 100% relative humidity; and radiation, 2.04x10s rads.
The LOCA test duration was 30 days.
Pre-aging was performed at 248*F for 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />.
Using Arrhenius methodology and periodic maintenance and parts replacement, a qualified life of 40 years was developed.
It is concluded that the Namco limit switch Model No. EA180 1s qualified for the environment specified.
8.
Fan Motor, Westinghouse Model No. 405TCZ Plant Identification No.1T46*FN0038 This fan motor is located in the reactor building secondary and is used to power the reactor building standby ventilation exhaust fan.
The specified accident parameters are as follows:
temperature, 150*F; pressure, 0.9 psig; 100% relative humidity; radiation,1.3x10s; and operating time,180 days.
Environmental testing for this type of unit was performed by the Buffalo Forge Company and documented in their Qualification Document No. D0-146 Rev. T (includes Westinghouse Report MM9112).
The maximum environmental parameters that the motor was subjected to are as follows:
temperature, 227*F; pressure, 3.3 psig; 100% relative humidity; radiation, 2x10s rads; and test duration, 30 days.
The motor was pre-aged for 1369 hours0.0158 days <br />0.38 hours <br />0.00226 weeks <br />5.209045e-4 months <br /> at 210*C.
A qualified life of greater than 40 years was calculated using Arrhenius methodology.
The applicant has requested a maintenance schedule for the motor bearings from the manufacturer.
It is concluded that the Westinghouse fan motor is qualified for the environment specified.
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Lugs and Splices, Amp, Inc., Models 52979, 53409-1, 53425-1, 53426-1, and 53946-1 These terminals and splices are used in electrical connections throughout the plant.
The specified accident environmental parameters are:
temperature, 340*F; pressure, 48 psig; 100% relative humidity; demineralized water spray; radiation, 1.76x10s rads; and an operability time of 180 days.
The environmental testing of these components is recorded in Amp Qualification Test Report No. 110.11004 dated February 2, 1982.
The maximum environmental parameters that the terminals and splices were subject to are as follows:
temperature, 470*F; pressure, 74.5 psig; 100% relative humidity; chemical spray with a pH of 12.5; and radiation, 2.59x10s rads'.
The test duration was 30 days.
The PVC splices were aged at 329*F for 21 days yielding a qualified life of greater than 40 years with Arrhenius methodology.
It is concluded that the Amp terminals and splices are qualified for the environment specified.
10.
Level Transmitter, Rosemount 1151
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Plant Identification No. 1821*T154B The file for this transmitter was reviewed during the first audit and found to be unsatisfactory for demonstrating qualification.
Although the manufacturer had stated in one of the test reports that the 1151 model was qualified by similarity to the 1152, except for radiation, a detailed comparison of the two models was not available.
In addition, the circuit boards installed in -
units in the plant are different from those in the tested unit, and a dose rate effect on accuracy observed in the 1152 models had not been addressed for the 1151.
This transmitter is located in the secondary containment and is used to detect low water level in the reactor vessel and to initiate the RPS.
During a HELB, it is exposed to a harsh environment consisting of a peak temperature of 176 F (ramping down to 104*F after 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />), a peak pressure of 0.9 psig, and 100%
relative humidity.
During a LOCA, the only harsh environmental condition is radiation with a total dose over seven days of 9.76x105 rads.
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. _ _7, 7 Sh:rsham R:-tudit/Att. 3 Prior to the audit, the applicant changed the status of this model to unqualified.
Units required to operate for more than two days are not fully qualified for radiation, and an analysis of 8% output drift during radiation
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exposure must to be completed.
The applicant has committed to additional testing.
The file was reviewed to determine if the only deficiencies remaining to be resolved were those identified above.
A detailed similarity analysis was provided to demonstrate that thermal aging and HELB data from the 1152 were applicable to the 1151.
Based on this analysis a qualified life of 1.4 years was calculated.
The corrective action described in the applicant's response to IE Bulletin 80-16 was completed on the unit examined in the plant.
The staff found this file, its conclusions, and the corrective action plan to be satisfactory.
11.
Drywell Hydrogen Analyzer Electronics and Indicator, Model No.
7045-NS-4702-0000 (Part of Comsip Inc. Model K-IV Hydrogen Analyzer)
Plant Identification No.1T48*H22115B This equipment is located in the reactor building secondary and is used to indicate the post accident hydrogen concentration in the drywell.
It is required for a LOCA only and therefore the only harsh environmental parameter is a radiation dose of 2.47x105 rads.
The sample gas reaches a temperature'of 340 F at 48 psig, but is cooled to less than 104*F before reaching the gas analyzer.
The required operating time is 180 days.
Environmental testing was performed on a prototype analyzer by Engineering Analysis and Test Company, Inc. and reported in Project 1035-1 Rev. 1 Report supplemented by Reliance Electric Report NUC-9.
The maximum environmental conditions that the prototype was subjected to are as follows:
temperature, 150*F; pressure, 0 psig; 90% relative humidity; and a radiation dose of 1x10s rads.
The test duration was 100 days extended to 180 days by analysis.
Although the sample pump in the prototype failed. the analyzer electronics and indicator performed satisfactorily.
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Shor; ham R:,-cudit/Att. 3 1
It is concluded that the hydrogen analyzer electronics and indicator are qualified for the environment specified.
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