ML20009B113

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Technical Evaluation of Revision 1 to Licensee Response to IE Bulletin 79-01B, Environ Qualification of Safety- Related Electrical Equipment
ML20009B113
Person / Time
Site: Beaver Valley
Issue date: 01/31/1981
From: Finkel A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20009B107 List:
References
IEB-79-01B, IEB-79-1B, NUDOCS 8107140807
Download: ML20009B113 (38)
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{{#Wiki_filter:* ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT IEB 79-018 1 TECHNICAL EVALUATION REPORT BEAVER VALLEY 1 DOCKET NO. 50-334 l DATED: JANUARY, 1981 ) REVISION I \\ Licensee: Duqaesne Light Company Type Reactor : PWR, Westinghouse Size: 852 Ne f Prepared by: Alan E. Finkel Engineering Support Section Reactor Construction and Engineering Support Branch, RI 8107140807 810629 PDR ADOCK 05000334 P PDR .,,,,,., ri ,,7 i.,s. .,,. g. ,_ j s.

e Contents Page 1. Introduction.................................................... 1 1.1 General.................................................... 1 1 2. Background and Discussion....................................... 2.1 General.................................................... 1

2. 2 On-Site Verification Inspections...........................

2

2. 3 Evaluation of Licensee's Report............................

2 3. Ge n e ra l I n fo rma t i o n............................................. 2 3.1 Identi fication of Class IE Electrical Equipment............ 2 3.2 Service Conditions......................................... 3 3.3 Qualification Documentation................................ 3 4. Technical Evaluation............................................ 3 4.1 Identification of Safety-Related Equipment................. 4

4. 2 Master List................................................

5 4.3 Service Conditions......................................... 5

4..1 Inside Containment LOCA..........................

5 4 4.3.1.1 Radiation.............................. 6 1 4.3.1.2 Submergence............................ 7 4.3.1.3 Chemical Spray......................... 7 4.4 High Energy Line Breaks (HELB)............................. 8 4.4.1 Inside and Outside Containment................... 8 4.4.2 Recirculated Fluids.............................. 9

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Page 4.5 System Shut Down....................................... 9 4.6 Replacement Schedule................................... 10 4.7 Margins................................................ 10 4.8 Aging.................................................. 11 4.9 Documentation.......................................... 11 4.10 Site Verification Inspection........................... 11 l 4.11 Equipment Data Review.................................. 11 4.12 Conclusions............................................ 12 5. Licensee Event Reports (LERs)............................... 12 6. References.................................................. 13 Appendix A, Test Reports and Analysis Lists Appendix B, Equipment Status Lists Appendix C, Licensee's Index Items and Justification for Continued Operation h ? } p p .'} f B S J" 4 I l l . -,.. _~ - _. _.

1. INTRODUCTION 1.1 General The NRC Office of Inspection and Enforcement (I/E) issued Bulletin 79-018, " Environmental Qualification of Class 1E Equipment" in January 1980. - This bulletin required the licensee to perform a detailed evaluation of the environmental qualification on Class 1E electrical equipment required to function under postulated accident conditions and to submit a report on this action. This document is a report on revision 1 of the licensee's response to this bulletin dated December 3, 1980. l 2. BACKGROUND AND DISCUSSION 2.1 General The evaluation of the licensee's response was accon.plished by performing an on-site inspection of selected class 1E equipment and by examining the licensee's report for completeness and technical accuracy. The licensee's reports used in this evaluation for in-containment components is dated September 30, 1980, outside containment components dated October 30, 1980, 45 day report of April 3, 1980 and therefore, does not include the response to the bulletin supplement which was issued on September 30, 1980 in the form of Generic Questions and Answers. On December 2, 1980, a meeting was held in Bethesda, Maryland to discuss the Duquesne Light Company Beaver Valley Unit I responses to IE Bulletin 79-01B dated September 30, 1980 and October 30, 1980. As a re'sult of that meeting, Duquesne Light Company was to submit an updated and expanded response to the Bulletin by January 6, 1981.> On December 12, 1980 an interim response was submitted which (1) identified procedures which were prepared or changed to provide additional guidance or instruction to the operator on how to cope with electrical equipment having some Environmental Qualification Deficiency and, (2) provide expanded justification for interim operation of those items that were highlighted in the December 2,1980 meeting as being of special concern. The operating procedures that were identified during the December 2, 1980 meeting as being of special concern were updated and reviewed by the NRC Beaver Valley Resident Inspector on December 3, 1980. b o A ~,, w. f. m n .._4

l l The licensee in the December 31, 1980 Bulletin Response has requested the following: "It is respectfully requested that the information is proprietary to Westinghouse be witheid from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's reSulations." In response to the licensee's request Section 6, Appendix A, 8, and C of this TER has been considered to contain proprietary information and has to be so classified. Reference paragraph (b) (4) of 10 CFR, Part 2.790. 2.2 On-Site Verification Insoections The on-site inspection, performed on selected 1E equipment, verified proper installation of equipment, overall interfree integrity, location with respect to flood level for equipment inside the containment, and manufacturers nameplate data. The manufacturer and model number from the nameplate data was compared to information given in the Component Evaluation Work Sheets (CES) of the licensee's report. If any discrepancies were noted between the installed equipment and the correspondent equipment addressed in the licensee's. report, they are discussed in Section 4.11 of this report. The site inspection is documented by Report Number 50-334/80-12. 2.3 Evaluation of Licensee's Report Each component as addressed on the Component Evaluat' ion Work Sheets (CES) of the licensee's report was examined for completeness and accuracy to the criteria given in the bulletin. This examination assumed qualification documents (analysis, test reports, etc.) referenced by the license: in their submittal are acceptable. The resulta of this examination are documented in Appendix B. 3. GENERAL INFORMATION 3.1 Identification of Class IE Electrical Equipment The licensee's list of systems was compared to the systems list issued by the Environmental Qualifications Branch (EQB) and discussed in Section 4.1 of this report. .,,t 'w ,, s, c, -r s 4

m It is recognized that there are differences in nomenclature of systems because of plant vintage and engineering design, therefore, many of these systems may not exist or have different titles. These differences will be addressed in the Safety Evaluation Report (SER) that will be prepared for this Licensee. i t 3.2 Service Conditions The service condition accident environment, HEL8/LOCA inside containment and HELB outside containment are indicated or discussed in the licensee's i l report and are based on the FSAR accident analysis and Section 4.3 of this report. 4 t 3.3 Qualification Documentation 1 Ao'pendix A is a list of documents (test reports, analysi, letters, etc.) used by the licensee in determining the environmental qualification of plant equipment for Beaver Valley Power Station, Unit No. 1. These i references have been tabulated by the licensee and are indicated on the applicable CES of their report. 4. TECHNICAL EVALUATION The basis for the technical evaluation is the information provided bg,gge licensee. Duquesne Light Company for the Beaver Valley Power Station Unit No. 1 Site and the verification inspection of the following as-installed equipment which is located inside of the containment. The inspection results have been documented in IE Report 50-334/80-12. 1. Flow Transmitters - Steam Generator Flow, I. Valve Stem Mounted Limit Switches (SMLs), 3. Electric Motor Operated Valves, 4. Solenoid Operated Valves; and, 5. Junction Boxes and 0/P and Pressure Transmitters. Utilizing the information identified in the inspection of Beaver Valley 1(jg'fggpectionReport 50-334/80-12) and the licensee's submittal, th9 reviewer assessed its adgquacy in relation to the D0R guides,6 NUREG 0588, and the supplement to IEB 79-018 which provides the Commission's requirements and staff position. The quality control measures utilized by the licensee included using experienced concultants to perform the tasks required by IEB 79-018. Independent t6'enical overview of each part of the effort was performed by the licenses's engineering staff. In addition, an extensive review of the final response and sign-off approvals by various levels of the licensee's engineering managerent was required. 'i e a;., ;,. 1." ,.m ~ ~ ~ ~.

4.1 Identification of Safety-Related Equipment The licensee reviewed his documen64 tion to establish the systems required to achieve a safe shutdown or provide isolation for the events identified in IE8 79-018. These systems were then evaluated against the 00R guidelines. The systems identified and included in the evaluation are: Early Report 1. Electrical (Various) 2. Primary Component Cooling (PCC) 3. Charging and Volume Control (CHS) 4. Containment Vacuum System (CVS) 5. DrainsAeratedSystem(DAS) 6. Orains Hydro System (DG) 2. EeedwaterSystem(EWS) 8. Main Steam System (MSS) HIG}ation-Containment (ISC) Vent, Air Cond - Reactor (HVR) 9. Iso 10. 11. ReactorCoolentSystes(RCS) 12. Residual Heat Removal (RHR) 13. Service Water and Emergency Service Water (SWE) 14. ContainmentRecirculatingSpray(RSI) 15. SafetyInjection-LowPressure(SIL) 16. Safety Injection - (SI) 17. Leakage Monitoring System (LMS)

18. Acoustic Monitor (RCS) 19.

Incore Instrumentation Ihe list of systems includino those that were excluded was provided to the Environmental Qualification Branch (EQB). Ihe EQB compared the list to a "Q" list developed by the staff and to the lists provided by similar facilities to determine the completeness of the licensee's response. Basedontgeinformationprovidedbythelicenseeandthereviewer comparison, it has been determined that the systems identified are within the guidance provided in Section 3.0 and Appendix A of the DDR Guidelines and are acceptable with this exception: 1. "Q" List Ihe acceptability of the licensee's list in paragraph 4.1 will be evaluated by the Environmental Qualification Branch (EQB) and addressed in the Safety Evaluation Report (SER) for this licensee. 1 e I 4 / 4 e sg), y j', e '\\ v #

4.2 Master List Ihe licensee developed a master list based on their system evaluation as required by IES 79-018. Attachment 1 of the licensee's 90 day response includes a list of references which W ded the basis for including or excluding specific component /equ pment from having a detailed data work sheet as required by IES 7 -01B. We have reviewed the supporting basis for the inclusion or exclusion of equipment provided in the references and have concluded that References dated September 30, 1980, October 30, 1980, and December 31, 1980 are acceptable except as noted in this report. 4.3 Service Conditions e 4.3.1 I_nside Containment LOCA Ihe maximum environmental conditions inside containment were determined by using the following documents: 1-Beaver Valley Power Station, Unit 1 ESAR, Chapters 5 and 14; 2-Analysis and Systems Modification for Recirculation Spray and Low Head Safety Injection Pumps Net Positive Suction Head (dated November 17,1977); 3

  • Auxiliary Eeedwater/ Containment Pressure Analysis (C.

N. Dunn to A. Schwencer, NRC dated November 30,1979); and 4-Stone and Webster Corporation calculation 11700-PE(B)- 220-0. \\ Ihe Beaver Valley automatic containment depressurization systemconsistsoftwoseparategroupsofsubsystems}-(1) the quench spray (QS) subsystems and (2) the recircu ation spray (RS) subsystems. f Based on the above documents and system design, the peak containment pressure determined by the licensee was 41.1 psig(AuxiliaryEeedwater/ContainmentPresgureAnalysis)and the peak containment temperature was 269.3 E (ESAR Iable 5.2-5 "ESAR Hot Leg DER Summer"). Ihe environmental envelope set forth in the system component evaluation worksheets for inside containment components established a containment pressurespecificationof45PSIG(ESARSectiog7.1.2.3)and a containment temperature specification of 280 E; therefore amagginof3.9psigforcontainmentpressureand 10.7 E for i containment temperature is provided: i,.- ? n - .c ll

4.3.1.1 Radiation Ihe design basis dose rates given in Section 11.3 of the ESAR are integrated over the forty year plant life and added to the maximum LOCA doses as given in Iable 4 to provide the radiation environment for equipment qualification. The following tables are identified as follows: c Table 1 - Basis of Source Data Iable 2 - Systems versus Sources Iable 3 - LOCA Sources Contributing toSixMajorAreas e e f 1 i)-

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TABLE 1 BASIS SOURCE NO. SOURCE BASIS FRACTIONALAMOUNTS(1) No. 1 Pressurized Reactor 100% Activity 100%/50%/1% Coolant Release No.~ 2 Containment Sump Degassed and 0%/50%/1% Liquid diluted reactor coolant No. 3 Containment Atmosphere Gaseous Source 100%/50%/0% tF 5 min 100%/25%/0% tJ 5 min (1) Noble gas / halogen / remaining core inventory. t 5 i ..., r,, n- )

4 TABLE 2 SYSTEMS VERSUS SOURCES Pressurized Reactor Coolant (Source No. 1) ReactorCoolantSystem(RCS) Resident Heat Removal Systems (RHR) Post LOCA Sampling System Sump Activity (Source No. 1) Safety Injection System (SI) Charging and Volume Control System (CVCS) Recirculating Spray System (RS) Gaseous Source (Source No. 3) Containment Atmosphere Hydrogen Analyzer and Hydrogen Recombiner System (HY) e 6 % **1 o B pr ,e ,e \\\\< a p , ~.

l TABLE 3 LOCA SOURCES CONTRIBUTING TO SIX MAJOR AREAS Pressurized Containment Containment Area Reactor Coolant Sump Liquid Gaseous Sourc Containment Yes Yes Yes l Auxiliary Building Yes Yes No Saisguard Area' No Yes Yes 2 Cable Vault No Yes Yes 2 Main Steam Valve Area No Yes Yes 3 Service Building No Yes Yes lletdown secured - only source is Post-LOCA sampling system 2 Containment Penetrations 30irect and scatter dose from containment building i O h.6'. g,% p 9 ,,g. i 2 1 s

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TABLE 4 RADIATION ENVIRONMENT Design Basis Doses (Rads) Area 40 Years 6 Months Post LOCA 40 Years & LOCA Containment 6 3.5x10) 6.6 x 10 1.0 x 10 Outside Crane Wall 8 9 1.0 x 10 (2. 0 x 10 Inside Crane Wall 2.0 x 10 8 0 Internal RCS (I) 0.7 x 108 .5 x 10 2.2 x 10 Auxiliary Building 0 6 6 Inside Cubicle 3.0 x 10 3.5 x 10 6.6 x 10 3 Outside Cubicle 7.0 x 10 1.0 x 10 1.0 x 10 3 6 6 Safeguards Area 7.0 x 10 6.7 x 10 6.7 x 10 Cable Vault 2 5 5 (East & West) 8.8 x 10 1.5 x 10 1.6 x 10 Main Steam Valve Area 3 6 6 ? el 7224- 0" 7.0 x 10 5.4 x 10 5.4 x 10 3 5 5 el 735'- 6" 1.8 x 10 1.9 x 10 1.9 x 10

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~ 6 6 3 3.8 x 10 3.8 x 10 el 751 1.8 x 10 2 2 2 Service Building 2.6 x 10 1.1 x 10 3.7 x 10 III Design Basis is 10 year life (2) Design Basis is 4 months post LOCA

IhelicenseestatedghefollowingintheSeptember 30, 1980 submittal:3 " Submergence: Of all the items in containment covered by the scope of IE Bulletin 79-0).B, five motor-operated valves are below flood level. Ihey are MOV-CH 310, RH 720A SI 865A, B, and C. Ihis isanacceptableconditIonbecause(1)thevalves are not required to function after they are submerged, and (2) the valves control circuits are open-circuited except when the valves must be operated. Ear MOV-SI 865A, B, C, the open circuiting is done with jumpers in the control room. Ear MOV-RH 720A, the circuit breaker is normally racked out. MOV-CH 310 has no special provision for opening circuting beyond its normal control contacts. However, a review of its contrcl circuit shows thatoncethevalvehasoperatedonsafetyinjection, no flood-related short circuit will cause it to change position. By consideration of the foregoing it is clear that submergence does not invalidate the qualification of the above named components." Justification for interim operation pages 14 and* 15 of Index Item 25 appears to be adequate. Operating Manual, Chapter 53, Section 4, Emergency Procedures Chapter 53, Section 2, " Precautions and Limitations" have been revised tc reflect that in ~ the cases of containment flooding, MOV-CH-310 ma'y become submerged and that the associated limit switc is may give an erroneous valve position indication when submerged. The dates for modification has not been identified other than, "no later than June 30, 1982." This item is considered unresolved and is a category IV item. 4.3.1.3 Chemical Spray Thelicensee'sSystemgomponentEvaluationWork 3 Sheets (SCES) require a1.5%BorigAcidSpray with NaOH to result in a 10.5 Ph 25 C. s,

~ o 4.4 High Energy Line Breaks (HELB) 4.4.1 Inside and Outside Containment Postulated accidents were defined'by IE Bulletin 79-018. They were defined as those environmental conditions resulting from both LOCA and/or HELB inside containment and HELB outside the primary containment. In this submittal LOCA equipment was that equipment readed for initial core cooling and core cover injection. Post LOCA was defined as long term core cooling recirculation and containment spray with high radiation effects on equipment outside of containment. l The outside containment HELB study was a comprehensive multi-nodal environmental analysis following the HELB. The i HELB's postulated were those requiret to be considered by application of Branch Technical Positics ASCSB 3-1 (Appendix C). Under the criteria set forth in this document, five (5) ~ HELB's were considered for the primary auxiliary (PA) building and contiguous areas at Beaver Valley #1. These breaks were: 1) a double-ended rupture in the main steam feed to the auxiliary feedwater pumps, 2) a double-ended rupture in the steam generator blowdown line, 3) a double-ended ruptur-of the letdown line, 4) a double-ended rupture of the decay heat release line and, 5) s lits in the auxiliary steam supply line. For this anal sis, all breaks were terminated at 10 minutes after initiat on. The final submittal addresses only three (3) HELB because examination of the letdown line break showed that it was enveloped by the other breaks. Also, the control board operator would recognize the problem and isolate the letdown system. The double ended rupture of the Decay Heat Release line was not considered because it was totally enveloped by the main steam break up stream of the main steam isolation valves and is wholly contained in the main steam valve room and will effect no Class 1E equipment. All equipment was examined according to the Bulletin as to whether it was required to mitigate the accidents as defined and also whether it was affected by the accident it was mitigating. Finally a review was made subsequent to each failure mode analysis to insure that all necessary procedure modifications were m. that the review showed that no misleading indications that would confuse the reactor plant operator were apparent. l l l l,, l

I l In Section 5 of this submittal the licensee states that an integrated 3c procurement and tracking program will be established and supplied to 1 l the NRC by February 28, 1981. It is expected that detailed schedule information will be part of thi.s new system and up-dated on a routine basis. This area is considered to be unresolved and is classified as a Category IV ites. 4.4.2 Recirculated Fluids The licensee indicated that the hostile environments in the areas containing post LOCA recirculating flows have been reviewed and included as part of the System Ccmponent Evaluation Work Sheets (SCEWS). The foll) wing documentation is referenced in Section 4.11 of this report: ~ Environment Documentation Temperature ( F) S&W Calculation No. 11700-PE(B)- 216-0 Pressure (PSIG) S&W Calculativo . 11700-PE(B)- 216-0 Relative S&W Calculation No. 11700-PE(B)- Humidity (%)

  • 216-0 Radiation S&W Calculation No. li700-PR-153-0 The acceptability of the parameters identified and the basis for specific equipment qualifications are incl"ded in Section 4.11 of this report.

4.5 System Shut Down components associated with " cold shut down:3fEB 79-01B requirem The following is the licensee's response t "3. Status of RHR System Components: Beaver Valley - Unit 1 was designed and licensed as a " Hot Shutdown Plant." Because Beaver is a hot shutdown plant, the RHR System is neither " safety Valley' nor environmentally qualified. The plant can be brought grade to a cold shutdown condition without use of the RHR System by using either or both of the following methods. ,I I i g

O by dumping steam to the condensor while maintaining the condensor a. under vacuum b. by letting down through the pressurizer PORV's and providing makeup with the safety injection pumps. (This procedure will be ~ formalized as part of the Owners Group Procedures on Loss of Heat Sink.)" The qualification information for equipment required to achieve and maintain a Cold Shutdown Condition (Ref Q.1 and Q.5 of Supplement No.

2) shall be submitted not later than February 1, 1981.

4.6 Replacement Schedule The licensee has identified some replacement schedules for Index Items in Section 1 of the December 31, 1980 sunittal, but a more specific schedule will be required in order for the NRC to provide the inspection required to verify installation, equipment, types of do'cumentation and overall system appraisal. 4.7 Margins The 00R Guidelines indicate that special consideration was given to the time required to. remain functional when establishing the criteria in Section 5.2 of the guidelines. NUREG-0588, Section 3(4), requires that a type test be for a minimum of 1 hour in duration when the functional requirement is within the first seconds or minutes of an event and the 00R guidelines, Section 5.2, requires that the test duration be at least as long as the period from initiation until the service conditions return to the level that existed prior to the event. Therefore, any type test that exceeds the functional operability time by 1 hour or longer meets the requirements as defined in NUREG-0588 and the D0R guidelines for margin in relation to test duration for this facility. In section 4.3 of this report the licensee has established certain margins on temperature, but the requirement is less than that referenced in IEEE 323-1974 section 5.3.1.5. The other consideration identified in the 00R guidelines in relation to the methods of qualification, other than identified specifically in this report will be addressed in the Safety Evaluation Report (SER) which will incorporate an audit of selected analysis and test reports identified in Appendix A. ,,i

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O 4.8 Ag The licensee indicated'that a study of the components subjected to harshenvironmentsisstillanoutstandingitem.3@etailsofthe licensee's effort is included in their submittal. As discussed in section 4.6 of this report, replacement of parts to maintain the life of a qualified item should be part of the February 28, 1981 submittal from the licensee to the NRC. 4.9 Documentation The licensee has established a file containing referenced material cited in the Equipment Qualification Worksheets (EQW). The data files are located in the Duquesne Light Building, 435 Sixth Avenue, Pittsburgh, PA 15219. 4.10 Site Verification Inspection An inspection of the installed components as listed in Section 4 of this report was conducted on May 8-9, 1980, at the Beaver Valley Unit 1 facility. The details of this inspection are documented in IE Inspection Reoort 50-334/80-12. ThelimitswitchonValvesTV-CC-107-01,-ElandTV-CC-11d-E3werenot ~ replaced prior to start-up as the licensee had committed to in report IE 50-334/80-12. The detailed identification of the components and the observations records will be addressed in the Safety Evaluation Report (SER) which will incorporate an audit of selected analysis and test reports identified in Appendix A. 4.11 Equipment Da:.a Review TheequipmentlistedinAppendixBisthestatusofthelagstdata sutmitted by the licensee in their response to IEB 79-018 Appendix B identifies the licensee data 3cin a format that allows the reviewer a quick look status of each listed component. The first four columns are self explanatory while the next three columns are defined as folicws: Environment - The listing in this column identifies the environment that appears to have same question as to whether or not it is in compliance with the requirements of the licensee. As listed below, a category I through V has bean Catecoq to the environment for a specific component or group of assigns components as listed. ,,,P 6 y'

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Remarks - The remarks column was used to identify the environmental conditions associated with the category number, or identify the system location when the licensee indicated that data was being looked for or an analysis was in progress. An example of this lack of data environment information in the licensee submittal is the requirement for aging. The equipment has been listed and identified in one of the following categories: I Qualified for Plant Life II Qualified with Restrictions III Exempted from Qualification IV Qualification of Equipment Unresolved, and V Equipment Not Qualified The. number in the ( ) in the serial no. block on the table indicates the number of identical components listed, but may have a different title within the report. Where this licensee did not address a requirement identified in IEB 79-01B the regional reviewer listed the item as a Category V. 4.12 Conclusion This evaluation is based on the on-site insp3gtion, the information supplied by the licensee in their IEB 79-018 submittal, their FSAR, and the assumption that the Qualification Documentation (Test Reports, . Analysis, Letters, etc.) are acceptable. 9 8 The Region I reviewer using the guidance and instructions for the evaluation of licensee data submittals and the site verification inspections that were performed to verify IE Bulletin 79-018 January 1980datasubmittalingggmation,findsthelicenseetobeinaccordance with the NRC directi:2 except as listed in Appendix B and C of this report. The results of this evaluation do not necessary imply that the equipment is unreliable, unsafe or represents a significant safety issue; it does imply that additional information is required and that the items in Appendices B and C will be evaluated by the Equipment Qualification Branch (EQB) and addressed in the Safety Evaluation Report (SER) to be written for this licensee by February,1981. 1 5. Licensee Event Reports (LERs) No licensee event reports were submitted by the licensee, associated with their evaluation of IEB 79-018, as of December 31, 1980. l t j .c

6. References 1. IEB 79-018, Memo to V. Thomas (NRC) from A. Finkel (NRC) dated May 2, 1980. 2. EQ Branch Comparison of systems and Parameters. (Systems list Westinghouse PWR). 3. Duquesne Light, Revised and Updated Response to IE Bulletin 79-018, a - In Containment Components, September 30, 1980 b - Outside Containment Components, October 30, 1980 c - Volume 1&2, December 31, 1980 4. Supplemental Information to IEB 79-018, dated February 29, 1980, September 30, 1980, and October 24, 1980. 5. Order requiring licensees implement requirements of Commission Memorandum and Order of May 23, 1980 (CLI-80-21). 6. Division of Operating Reactors (00R), "Guidelinas for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors", Enclosure 4 to IEB 79-018. 7. NUREG-0588, " Interim Staff Pesition on Environmental Qualification of Safety-Related Electrical Equipment", dated December 1979. 8. Inspection Requirements for Verifying Reactor Licensee Responses to IE Bulletin No. 79-01B, dated April 25, 1980. 9. IE Support and Review of Environmental Qualification of Electrical Equipment as Operating Reactors, dated October 10, 1980. 10. Duquesne Light Responses to IEB 79-018, dated April 15, 1980, March 31, 1980, May 8, 1980, September 30, 1980, October 30, 1980, and December 31, 1980. r i

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l Appendix A Test Reports and Analysis Lists 4 O O g k n

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~ 1. Qualification of Test of Kerit SKV Non-Shielded Power Cable Under Simulated Post-Accident Conditions, The Kerite Co., Decemger 23, 1976. -2. Kerite Letter of July 7,1980, E. N. Slight to H. W. Mooncai. 3. Kerite-Duquesne Light Telecon of July 11, 1980. 4. Franklin Institute Test R2 port fF-C2857 dated September 1970. 5. Okonite Test Report dated May 7, 1971. 6. Okonite-Stone & Webster telecon of September 15, 1980. 7. Franklin Institute Test Report F-C2935 Dated October 1970. 8. Physical' Properties of CC-2115 Silicone Rubber After Conditioning Simulating a LOCA dated January 1979, Revised March 1980, Anaconda Wire & Cable. 9. A.E.T. L. Test Report #5450-4643 dated October 30, 1973. 10. Viking Industries Test #VIR405 dated June 7, 1973. 11. OLC Test Report dated March 25, 1986, Envir. Qual. Test Data and Results of Penn Union (Series 1000) & Marathon (Series 1500) Terminal Blocks.

12. -Qualification of Firewall III Class 1E Electric Cables IChemically Cross-Linked Insulation) the Rockbestos Co., dated July 7,1977, Revised November 26, 1979.
13. Topical Report on G.E. Vert. Induction Motors Inside Cont. Recirc Spray PP Motors, Docket No. 50-280 and 50-281 by M. W. Sheets, G. E. Co. June 12, 1973 and Revised July 23, 1979.

14. G.E. Letter of August 25, 1980 signed by R. E. Radabaugh. '15. ASCO Test Report AQS215678.

16. Acme-Cleveland Development Co. Test Report dated February 20, 1970.

17. Letter from NAMCO Controls dated April 26, 1979. 18. Simulated LOCA Test of Solenoid Valves and Limit Switches by Masoneilan International, April 19, 1973. 19. NAMCO-Stone & Webster telecon of September 15, 1980. 20. Franklin Institute Test Report F-C3834 dated March, 1974. i ? 5.' 9 4

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o 21. Isomedex, Inc. Test Report dated November, 1975.

22. Nuclear Power Station Qualification Type Test Report Limitorque Valve Actuators for PWR Service Project #600456. Tested per IEEE Standard 382-1972. Test performed June 7, 1974-November 22, 1974.

Prepared by Limitorque Corp. Test Laboratory. 23. Limitorque Valve Actuator Qualification for Nuclear Power Station Service Report 80058. Test conducted per IEEE 382-1973, 323-1974, 344-1975. 24. Limitorque letter of August 15, 1980 by J. B. Orab.

25. NS - TMA - 2184, Anderson to Stolz.
26. WCAP-9157, RTD's (Wide & Narrow Range) Sostman.
27. Ononite Engineering Report No. 307 Test 0177-4.
28. Okonite Telex to C. D. Nardella of S&W dated October 14, 1980.

29. Franklin Institute Test Report #F-C378', " Testing of Class 1E AC MCC under Exposure to High Temp / Humidity Envir and Press Pulse", dated May, 1974.

30. Qualification Type Test Report Limitorque Valve Actuators for Class IE S'ervice Outside Primary Containment in Nuclear Power Station Service Per IEEE 382-72 and IEEE 323-71.

Test performed November 13, 1974-January 23, 1975. Project No. 600461, Report No. B0003. Prepared by Limitorque Corporation Test Laboratory.

31. NS - CE - 755.
32. WCAP 8754, Revision 1, Section 5-2.

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Appendix 8 Equipment Status List 9 0 4 9 .'s r. 4',

8 '/ Port / Centala Environ-numerks glel mee t aant I*I'98ty EF****I 8**I* ihe QUT II-I terite-51 I Temperature tv Ties a Pressere 8 Il-2 Cerro - I Tesverature IV taustic Spr4y with Ph betacen 9 and 11 e 1000V Tlee & Tested I hr. at hiih temperature and pressure High Tesp. Preasure etsre i I II-3 OKONITE I Teeperature IV

  • y,stes t hr at bl'A tasperature and pressere SEV Fomer [able flee a Pressure 11-4 01@fff f E I

terperature IV Tested I hr at hiah tese:rature and pressere 600 Vult Cuatrol gl e a Cable Pressere 1 e i 11-5

Continen, lastries:nt table tal Wire 1

lerycrature IV Tested 1 br at high tevicerature armi pressure Ilrw 4 Pressure .{ i \\ ~ g I

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!!-15 Sarton F,, I V To be replaced Flow Iransaltters 18 16 rtan M4-Let 2 I Aglag II Anlag data entstandlag on the Itarton tot 2 ltems. Offlerential.. 19) The 386 mfil be replaced with a 8arten tot 2 764 flee. Pressure Transaltter M6(1) li-17 Sees IM-59342 I IV Testlag is currectly in progress. !bcumentation of tbc esalifica. Level Tran mitter (2) tion test is schedsled for review by Decenter 1981. 4 1*-18 h sen- .32522(1) I y To be replaced. 81e18ecry is scheduled for October 1981.- no dated tevel Transaltter mellan for lastellation. ~ 11 19 Fischer-50EP1031 I V is be reeleced. Delivery is scheduled for Oct(her 1981. No date i Pressure transmitter Porter (1) for fastallation. I t 1 l l .y.- l ) 1

I 'IInsusf. W Centale - Envirse. Smarts Mlal meet meet fatagry w $N Op[ Il-20 Barton 763-E Aging IV Informstlon is scheested prior to March 30, 1981. Pre nere Transmitter-. Lot 2 (5) 18-21 Barton 386(3) 1 V to be reolaced. Requires detailed scheeste. Level Tree witters 11-22 STJs Wide and harrow 50STPWI 118348-1 X V To be replaced. Requires detailed scMte. Range sad i 119018-2 i (6ea.) 11-23 Trinity Temperature Resist-r I V To be replaced. Rega.' es detalled schedule. aat Bulb 18-24 and 25 Both items ladess 24 and 25 discuss the llettort>e POWS. Class Motor Operators Limitorque Y B lasulation actors will be replaced with higher lasulated j sisterials. Requires detailed sche 4 ele. 4 4 i' ~ 1 G j .e g.. 1

,l e d e te lpm o c I i b M da e nt I a e e o dat e 0 sgn 3 u n es oi ci i e ht e cl ge m n e ne h. l i dis t et n y sdese b eaN ec ih ti l l de ss .l etsaa te aet nc l enor t l r p a h eif s o a hsmt C eait t h m d r r s shldo a e e iT uAp m b b. l g e A e l e .r o oe A .r s se t t s n srt er s se eeeti r i c l reiu i f um q e lt se s gl o n t ctiR p im naoh a to ef nt sr du e ef insrt mmofM aeo r t u t s nr e d I n. s oo t s e ip iato ai0 t e rp ar neht3 c eut a f ie dq ch o f r nraic li i otf r e l u t aia m aq sid r M i m a he hirl y i R T t TLocb y roge I l I e VV V I V t II e r n u o t e r it ar ve ru es ns E a ps ae cr iP 'e t l u t o nt Ce e 0 I I I 0 I 8 A 0 / 2 0 t 1 r1 L 2 a: t M Pt 1 A 0 3 3) g 0 = 6) 14 5 K2 22 1 S( 2( n o [ f 0 h i u E t i e V N a s E E r) O p E D K a1 N M( O E r t o s i t K k i c n o e k c t. r l l i B r e e c p l i i a S e t s h n y 6 7 u 8 9i 0e s m 2p 2o 2 s 2 m 31V ~ m 60 - m - c - V - r 1 a0 I u 8 c lO 1 e E (T 1C6 IP 1A IM - k 1 ,i l 1 1 1 i i!. iI il:Il!

' gg,,,,g* W Male EmiN-h6s r-bh. g g.lat meet . anot y e. 184 out Ilw splice sisterials will be replaced. Rearttro scheeste frass 11-31 Kerite a V IIcensee. Electrical Splici Ett 5tv Requires schedule and results of lavestigation by licensee. II-32 vullene I 'g y SIS Wire EE 57275 s II-33 GE Vulkene I I SIS Ware Supreme P 5 11-34 Westing-012 I V The licensee is dis:canecting this switch frun the system. Control Switch house i ~ f I1-35 Ilotor Control Allis-Centers 480V Chalmers (5) II Administrative change, pequires review of the procedures. t i ~' -

i t I g e 1 s 6 y 'e e9 b l1 ese u d ne d, e e0 i es ca h3 f i i e c Se t l c n n 1 u e f1 .J d o i 1 m So 8n r 9a e e ef 1h l t u l e d l u t e ir e d il e u re h h gd ph c c ne At s s ih o d nc eud e s d rs l de e t e e i l r l ce l a i nr st a u t ti d a ei m nt e ep en d e t h A e d ne ne o c oR od. pi e N s s i m l e e t r ar otu r t ce cod i ie ne d t4 t h e u p nsc r q <e 14 H 1 c ei s e e m d R Mt t ead r o coe o d n all d e f lli s c o5 paa l. e e1 t ae c l nf r1 e ee a a p oo ad ss l dt n p r t5 ese de e i e t ar ec r u ti e lt cli b oe e u cl e se prq e b T leh soe pe o i s EfR ah o [t T 1. W V V V V k I e n or

igv, n,

E, I-e t I u x I l x a t o ng a, N C, S) / 6 ) P5 t 2 4 %( rg A 5 2 0( a. 0 6 1 0 45 Pg 2 1 3 3 0 46 20 t 8 0 70 88 g. r) 8) 4) A0 0A e8 14 23 E2 1B t 0( ( ( r f O O er m C C he m O O M M ct a sr H C C A U io I S S I A A I FP s r e t e e t v v h h l l l a a c c a tn V V t t s e i i n n d d w w a i l S r e T p o o s 6n 7n 8t 9t 0 a 3 e 3 e 3l 3i 4 w C - l l - e - m o 1 o 1 o 1l 1i 1l 1S 1S 1L 1L 1f

x L

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I

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1 ,s m to nr s ea e I e .l m. bl noc or li pt et o vaen ecv li os fbi nia e or O e1 e it 'c t 1 s a ' n e e e c 1 c s i eo i n f et s l e l sai c l nlh m i ee t o l ucl r qil r f m l ao o r ff e r od l f enn s u aeoo t d e ofeii r e l l tt t u t .ca a ic d a ec me s e mssi h re f t e c oumi e r s fl et v i eat s o u e l viu b q r j a e i gns R u noee 3 q iide 4 e st ns R saI n 1 d i c e 1 e / misc c fii s a d dihl a l e act p c he e s e a pnh m r l ssit e p t l e enst b b e eamw o b hh et r o stt p l o i, Y as a e t sl e m ael r a Dl aa S g V Y V V t I I I a t nor itvn ne E s 8-C I l I e r m a w la t 6, I Jl mt a l nem L 4 ) / t 14 1 4( rt 7 0 aa Pl 0 1 ) 1 FA ) 2 g Pt CI 1 2 Ea 0C 1 ( 0C 5D ( 5B [ e e u u e q q u r r r r q I er er o o r he he t t o t ct ct i) i l sr sr m5 m io io i3 i e FP FP L( L i n L e e i t t t t l i a m s s s r n n o a a t r r a S 1 T T r w M 4 e e e e I r r f e I u e in s 2s 3 r 4 5 s 4 ss 4e 4 4 9 1m t e er t V e s 1 1O 1h 1M i r 8 re 1 P 3Pt t' FW ~ _7 't-( [ b. ljl l

sia y g* NI J e, I Q*3 E ,3-3II I 22 E- !i 5 PE

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J-e..- 1. sH --j,{ en Tow 3** et , t 'A m C 2 E I$4 4. 2 a 5 21lg 5_W j 6 S w" -.t.. a 2k E ~ = = .t G M M M V -{m-l 1 = s:- 20 8 N 5 E a _C _R = d 5 k I 3 3 3.$ 3.$ i e g-i a3 R R .t. 2 e a 1 I i s A t se $;gf $55 f i i k 4 .h ' 4d =t t ,,t, T s a ay, j y --w ,-n, -e-w y--,,,, --4-,wa ,w,, ey, e ,,---m- ,,-,,y-,-,

s 1 Appendix C f Licensee's Index Items and Justification for Continued Operations 1 ) e..,

  • h.

Qualification Worksheet Bulletin Index Item Equipment Sheet Number O General Issues 1 Power Cable - Kerite 1 2 Power Cable - Cerro 2 i 3 Power Cable - Okonite 2A 4 Control Cable - Okonite 3 5 Instrument Cable - Continental 4 6 Elec. Penetrations - Viking 6 7 Terminal Blocks - Buchanan 7 8 Terminal. Blocks - Penn Union 8 9 SIS Wire - Rockbestos" 9 10 Elec. Motor - G.E. 325, 326 11 Asco Solenoid Valves 25,27,29,31,33,35,37,39, 41,45,46,119,120,121,149,' 154,158,161,248,277,278,279,280, 281,282,334,364,365 12 Namco Limit Switch Model EA740 71,73,75,79,81,83,85,87, 91,143,156,162,165,253 13 Namco Limit Switch Model EA180 77,92,124,125,126,295, 296,297,348,349,350,351 14A Level Transmitter - Mason-Neilan 287 Model 12522 148 Pressure Transmitter - Fiscner-289 Porter Mode 50EP1031 15 Gems Level Transmitter 328,327 16 Temperature Resistance Bulb - 329,330 Trinity i f l l t . tr 6 .a. s,

Qualification Worksheet Bulletin Index Item Equipment Sheet Number 17 Acoustic Monitor Sensors 368-391 18 Motor Operator - Limitorque 243,7'.5 19 Motor Operators - Limitorque 131,134,284,285,286,300, (Westinghouse Scope) 301,302,303,304,305,338, 352,353,354 20 Flow Transmitter - Fischer & 199,200,201,202,203,204 Porter 1082496 21 Flow Transmitter - Barton (386)a,c 342,343,344,346,175,179, 183 22 Level,Tpansmitter-BartonLot2 270,271,272,172,173,174, (364) 176,177,178,180,181,182 23 PressureTrgngmitter-Barton 255,256,273,274,275 Lot 2 (763) 24 RTD - Sostman 264,265,266,267,268,269 257,258,259,260,261,262 25 General hotes (Outside Containment) 26 Terminal Blocks - Marathon 1500 8A 27 Splicing Material - Okonite 10A '28 Splicing Material - Kerite 10B 29 SIS Wire - GE Vulkene 11A 30 SIS Wire - GE Vulkene Supreme llB 31 Control Switch - Westinghouse 16,17,18,19,20 32 Limit Switch - NAMCO Model No. 250,251,252 02400X 33 Motor Control Center - Allis 15A-E Chalmers 34 Solenoid Valve - ASCO Model No. 22',224,246,247,247A HPX 40L,401,402 i I v. a, ,b r -ir--

Qualification Worksheet Bulletin Index Item Eguipment Sheet Number '5 Motor Operated Valve - 196,197,198,216A,306,307 Limitorque 308,309,310,311,313A-H, 314,315,395,395,396,397, 398,399,426,427,428,429 36 Elect. Motro - Louis Allis 331,332,392,393 37 Flow Transmitter - Fischer & 403,404,405,312,313 Model Nc. 10824 38 Pressure Transmitter - Fischer 332C,3320 & Porter Model No. 50EP107 39 Solenoids Valve - ASCO 122,'55-337 40 Motor Operated Valve - 436-446 Limitorque 41 Motor Operated Valve - 127-130,132,133,135-139 Limitorque 339-341,355-358,432-435 42 SI Pump Motor - Low Head 447,448 43 Charging Pump Motor - $16-118 Westinghouse 44 Pressure Transmitter - Fischer 205-213 & Porter Model 50EP1041 45 Limit Switch NAMCO EA740 453,454 O 4 a +,, ,,.g I L ie a) [g

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