ML20004D223

Equipment Environ Qualification,Browns Ferry Unit 3, Technical Evaluation Rept

ML20004D223
Person / Time
Site:	Browns Ferry
Issue date:	01/31/1981
From:	Crane C FRANKLIN INSTITUTE
To:
Shared Package
ML18025B526	List: ML18025B525 ML18025B527 ML20004D218 ML20004D222 ML20004D223
References
IEB-79-01B, IEB-79-1B, TER-C5417-006, TER-C5417-6, NUDOCS 8106090015
Download: ML20004D223 (130)

Text

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. h TECHNICAL EVALU ATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QUALIFICATION TEEESSEE VAI! CY AIFrCRITY SFSNS.-AY htQlAR P'hER STATICN LNIT 3 NRC CCCKET NO.

50-296 NRC TAC NO.

A.'433

PC F AC EO7 0917 EG&G ICAr 0. iNC. SUSCCNT?ACT NC. GSt5

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Prepared by l

Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 FRC Group Leader: C. J. Crane l

Prepared for EG &G Idaho. Inc.

l Idaho Falls, Idaho 33401 January 31,1981 This recert was ers ared as an ec00unt of werx performed under a succentrset fr:m EG&G l

Icahc. Inc.. a come :cntractor tc the United States Oscartment Of Energy. Neitner EGiG l

ncr the United States Government ncr any agency herect er any of neir em 'cvees.

makes any warranty. expressec or impliec. or assumes any 'egal siacility Or res:cns.t:ility for any third party's use. Or the results Of sucn use. or any informaticn a:paratus. Or0cu::

Or process discicsed in this report. cr represents that its use ::y sucn tnird party ucula not intnnge pr:vately cwned nghts.

NOTE - THIS iS A CR AFT Because of senecule iimitaticns. this report draft nas nct gone thrcugn tre ccmclete review cyc!e of FRC. While the overall conclusicn is expected to temain the same tne rescer is :aut:enec that scme details of tne recert may cnarge as the rev ew 's :cr :::etec.

.A THIS DOCUMENT CONTAINS aI_ Franklin Research Center P00R QUAllTY PAGES A cmsien ci rne Franen insuute n.s,e r eon., x.

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4 TECHNICAL EVALUATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION TEEESSEE VAlI Y AUTrCRITI l

BFONS FERRY NLO. EAR PChER STATICN LNIT 3 NFC CCCKET NO.

50-296 NFC TAC NO.

12483 FRC PPO.ECT C5M 7 EG&G :DAMO,lNC. SU8 CONTRACT NO. K 7615 FRCTAS<

6 Prepared by Franklin Research Center The Parkway at Twentieth Street Philadelphia, P A 19103 FRC Group Leader: C. J. Crane Prepared for EG&G Idaho, Inc.

Idaho Falls. Idaho 83401 January 31.1981 This re::crt was cre:;ared as an secount of acrk ::ertermec encer a succentract f rom EG&G Icanc. Inc.. a ::nme :entractor to the United States Ce::artment of Energy Neatner EG1G ner the United States Government ncr any agency inerect er any si ine'r erncicyees makes any narranty. expressed er imclied. er assumes any legal.iaciiity Or rescens;c4iity fer any inird :: arty's use. cr the results of sucn use. cr any information. accaratus. creduct er:: recess disc!csec in this report, er represents that its use ::y sucn third party aculd not infnnge pnvately owned rights.

NOTE - THIS ;S A CPAFi Secause of senecule ! imitations. this recert draft nas t.ct ;cre !!:rcugn me :cmciete review cycle Of :AC. While the everall conclusion is expected tc remain :ne same, me reacer is cautioned that some details of tne re::crt may cr.ange as the review is Ocmeteted i

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o TER-C5417-6 CCNTENTS Section Title Page 1

INTRCDUCTION.

1-1 1.1 Purpose of the Review.

1-1 1.2 Generic Issue Background 1-1 1.3 Specific Issue Background.

1-6 1.4 Scope of the Review 1-7 2

NRC CRITERIA FOR ENVIRCNMENTAL QUALIFICATICN.

2-1 2.1 Criteria Provided by the NRC 2-1 2.2 Staff Positions and Supplemental Criteria.

2-1 2.2.1 Service Conditions Inside Containment for a Loss-of-Coolant Accident.

2-1 2.2.2 Submergence.

2-2 2.2.3 Equipment Located in Areas Normally Maintained at. Roca conditions.

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2.'7. 4 Simulated Service Conditions and Test Curation.

2-3 2.2.5 Deferment of Qualification Review 2-3 2-4 2.2.6 Test Sequence 2.2.7 Padiation 2-4 3

METHODCLOGY USED BY FRC.

3-1 4

T3iCHNICAL EVALUATION.

4-1 4.1 Methodology Used by the Licensee 4-1 4.1.1 Completeness of Equipment List.

4-1 j

4.1.2 Definition of F.tipment Operating Time 3

Requirements 4-2 4.1.3 Qualified Life.

4-4 4.1.4 Licensee Event Reports (LER) 4-5 4.1.5 Licensee's Generic Positions With Respect to the DCR Guidelines.

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1 CONTENTS Section Title Page 4.1.6 Required Signatures.

4-9 4.1.7 Chemical Spray 4-9 i

4.1.8 Description of Qualification / Replacement Plan 4-10 l

4.2 Equipment Qualified for Plant Life.

4-12

'i 4.2.1 NRC Category I.a Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines.

4-12 4.2.2 NRC Category I.b Equipment for Which Deviations From the DOR Guide-lines Are Judged Acceptable.

4-12 4.3 Equipment Qualified With Restrictions.

4-13 I

4.3.1 NRC Category II.a Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines and 3as a Service Life I 4s Than T

.nt Life.

. 4-13 4.3.2 NRC Category II.b Equipment That Fully Satisfies All Applicable Requirements of the DCR Guidelines Provided That 3

Specific Modificatiens Are Made.

4-14 4.3.3 NRC Category II.c Equipment for Which Deviations From the DCR Guidelines Are Judged Acceptable 4-14 4.4 NRC Categcry III Equipment That Is Exempt From Qualification 4-15 4.5 Equipment for which Documentation contains Deviations From the Guidelines That Are Judged Unresolved.

4-16 4.5.1 NRC Category IV.a Equipment Which Has Qualification Testing Scheduled but Not Completed.

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a TER-C5417-6 CONTENTS Section Title Page 4.5.2 NRC Categt.t? IV.b Equipment for Which a Qualification Doct. mentation in Accordance With the Guidelines Has Not Been Established.

4-16 4.6 NRC Category V Equipment Which Is Unqualified.

4-33 4.7 NRC Category VI Equipment for Which Qualification is Deferred.

4-43 5

CONCLUSIONS.

5-1 6

REFERENCES.

6-1 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS APPENDIX B - EQUIPMENT ITEM TABLE APPENDIX C - SAFETY SYSTD4S EUR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED APPENDIX D - CABLE RNUFACTURERS LIST APPENDIX E - EQUIPMENT I m CROSS-REFERENCE LIST 1

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INTRODUCTION 1.1 PURPOSE OF THE REVIEW The NRC Office of Inspection and Enforcement (IE) issued Bulletin 79-013, t

" Environmental Qualification of Class lE Equipment" in January 1980. This Bulletin required the Licensee to perform a detailed evaluation of the environmental qualification of Class 13 alectrical equipment required to function under postulated accident conditions and to submit a report on this action.

The objectives of the NRC Equipment Environmental Qualification Review program are to evaluate nuclear power plant safety-related elot-ical equipment in accordance with criteria established by the NRC and to identify J

(1) equipment whose. qualification documentation is adequate, i.e.,

substantiates that equipment is capable of performing its specified design basis safety function when it is exposed to a harsh environment and (2) equipment whose qualification documentation is deficient, i.e., does not give ensonable assurance that the equipment is capable of performing it specified safety function.

To meet the overall program goals, the objective of this Technical Evaluation Report is to review the Licensee's submittals to determine if the Licensee reviewed its safety-related electrical equipment for environmental qualification in accordance with the DOR Guidelines and NUREG-0588 as required by IE Bulletin 79-017 The NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. If discrepancies ars found, the audit will be extended.

1.2 GENERIC ISSUE BACKGROUND Safety-related electrical equipment must be capable of performing design safety functions under all normal, abnormal, and accident conditions. Of j

particular concern is the assurance that equipment will remain operable during 6

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o TER-C5417-6 and following exposure to the harsh environmental conditions (i.e.,

temperature, pressure, humidity (steam), chemical sprays, radiation, and submergence) imposed as a result of a design basis accident. These harsh environments are generally defined by the limiting conditions resulting from the complete spectrum of postulated break sizes, break locations, and single failures consequent to a loss-of-coolant accident (LOCA), sain steam line break (MSLB) inside the reactor containment, or a high energy line break (BELB) outside reactor containment (such as a main steam or feedwater line break). The purpose of equipment qualification is to provide tangible evidence that equipment will operate on demand and to verify design

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performance, thereby establishing assurance that the potential for common-mode failure is minimized.

Qualification criteria applied during the licensing of the older nuclear plants have been modified over the years, and industry standards concerning qualification have been revised as the design of reactor systems has changed and as regulatory and operating experience has accumulated. Examples of such standards are IEEE Standards 279-71, 323-74, 383-74, 317-76, 334-74, 382-72, 4

and 381-77. NRC NUREG documents 0413 and 0588 have been developed to address 4

this topic. In particular, NUREG-0588 (published for comment in December 1979) formally presented the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment in the resolution of Gcneral Technical Activity A-24, " Qualification of Class lE Safety Related Equipment." The positions documented therein are applicable to plants that are or will be in the construction permit or operating license review process.

Although qualification standards and regulatory requirements have undergone considerable development, all of the currently operating nuclear power plants are required to comply with 10C7R50, Appendix A, General Design Criteria for Nuclear Power Fiants,Section I, Criteria 4.

This criterion states in part that " structures, systems and components important to safety shall be designed to accommodate the effects of and to be compatible with the I

environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents."

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TER-C5417-6 In addition, qualification requirements are also embodied in 1COFR50 Appendix A, General Design Csiteria 1, 2, and 23 and Appendix B, Quality Assurance Criteria for Nuclear Power Plants and P'el Reprocessing Plants, Criteria III and XI.

These requirements are applicable to safety-related equipment located inside as well as outside of containment.

The NaC staff has evaluated the Licensee's equipment qualification program by reviewing the qualification documentation of selected safety-related equipment as part of the operating license review for each plant. The NRC staff has also used a variety of methods to assure that thess general requirements are met for electrical safety-related equipment. In the oldest plants, qualification was based on the fact that electrical components were of high industrial quality. Af ter 1971, qualification was judged on the basis of IEEE 323-71: however, no regulatory guide was issued adopting tP IEEE 323-71 standard. For plants whose Safety Evaluation Reports were issued after July 1, 1974, the Commission issued Regulatory Guide 1.89 which in most respects adopted the most recent standard, IEEE 323-74.

In 1977, the NRC staff instituted the Systematic Evaluation Program (SEP) to determine the degree to which the older operating nuclear plants deviated from current licensing criteria. The subject of electrical equipment environ-mental qualification (SEP Topic III-12) was selected for accelerated evalua-tion as part of this program. Seismic qualification of equipment was to be addressed as a separate SEP topic. In December 1977, the NRC issued a generic letter to all SEP plant Licensees requesting that they initiate reviews to determine the adequacy of existing equipment qualification documentation.

Preliminary NRC review of Licensee responses led to the preparation of NUREG-0458, an interim NRC assessment of the environmental qualification of electrical equipment. This document concluded that "no significant safety deficiencies requiring Lamediate remedial actions were identified." However, it was recommended that additional effort should be devoted to examining the installation and environmental qualification documentation cf :pecific electrical equipment in all operating reactors.

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TER-C5417-6 On May 31, 1978, the NRC Office of Inspection and Enforcement issued IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants," which required all Licensees of operating plants (except those included in the SEP program) to examine their installed safety-related electrical equipeent and ensure appropriate qualification documentation for equipment function under postulated accident conditions.

Subsequently, on February 8,1979, the NRC Office of Inspection and Enforce-ment issued IE Bulletin 79-01, whith was intended to raise the status of IE Circular 78-08 to the level of Bulletin, i.e.,

action requiring a Licensee response. This Bulletin required a complete re-review of the environmental qualification of safety-related electrical equipment as described in IE Circular 78-08.

The review of the Licensee responses indicated certain deficiencies within ene scope of equipment addressed, definition of harsh environat.nts, and a

adequacy of support documentation. It became apparent that generic criteria were needed to evaluate the electrical equipment environmental qualification for both SEP and non-SEP operating plants. Therefore, during P'e second half of 1979, the Division of Operating Reactors (DCR) of the NRC issued internally

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a document entitled " Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors."

(The document is hereaf ter referred to as the " DOR Guidelines.") The document was prepared as a screening standard for reviewing all operating plants, including SEP plants. Originally it was intended that the Licensees would evaluate their qualification documentation in accordance with the DOR Guidelines. However, initial NRC review of this documentation, which was compiled to support Licensee submittals, revealed the need for obtaining independent evaluations and for acceleratir.g the qualification review program.

In Octooer 1979, the NRC awarded Franklin Research Center (FRC) a contract to provide assistance in the " Review and Evaluation of Licensing Actions for Operating Reactors," which included an assignment for review of equipment environmental qualification under SEP Topic III-12.

FRC was given the assignment to review equipment environmental qualification documentation d':::

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TER-c5417-6 and to present the results in the form of a Technical Evaluation Report for each plant included in this program.

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On January 14, 1980, the NE Office of Inspection and Enforcement issued the DCR Guidelines and IE Bulletin 79-018, which expanded the scope of IE Bulletin 79-01 and requested additional information on environmental qualification of safety-related electrical equipment at operating facilities, excluding the 11 facilities undergoing the SEP review. This Bulletin stated that the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification are the DOR Guidelines. The scope of the l

review was expanded to include high energy line breaks (inside and outside containment) in addition to equipment aging and submergence. The NE advised the Licensees that the criteria contained in the DCR Guidelines would be used l

in its review of Licensee submittals; problems arising from this review would 1

be resolved using MUREG-0538 as a guide.

In early February 1980, the NE decided that Indian Point Units 2 and 3 l

and Iion Units 1 and 2 should be included within SEP Topic III-12 for the purpose of equipment envirensental qualification review.

On February 21, 1980, the NRC and representatives of the SEP Plant Owners Group held an open meeting at NE headquarters to discuss an accelerated review program in accordance with the DOR screening guidelines. Represen-tatives of the Indian Point Units and Iion Station also attended this meeting. The NE formally issued to all Licensees represented at the :seeting the DCR Guidelines document (64]* which included a second document,

" Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Is To Be Addressed,' [64]

together with the request that the Licensees review their plant systems and provide additional equipment environmental qualification information to the N E on an accelerated schedule.

For non-SEP plants, the NE Office of Inspection and Enforcement formed a task force including a principal reviewer in each region and a task leader from headquarters. The regional members are responsible for the technical

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TER-C5417-6 review of the Licensees' responses to IE Bulletin 79-013, and the task leader is responsible for the overall coordination of the review effort with NRC to assure overall consistency. The regional reviewers held meetings with the Licensees in their respective regions which resulted in staff positions being issued in a supplement to IE Bulletin 79-013 dated February 29, 1980.

In April 1980, the NRC organizational structure was modified and the Equipment Qualification Branch was formed within the new Division of Engi-neering. Responsibility for reviewing the status of equipment qualification for all plants was assigned to this branch.

On May 27, 1980, the NRC issued Memorandum and Order CLI-80-21, [671 specifying that Licensees and applicants must meet the requirements set forth in the DCR Guidelines and NUREG-0588 regarding environmental qualification of safety-related electrical equipment in order to satisfy 10CFR50, Appendix A, General Design Criteria,Section I, Criterion 4.

This order also established that the Safety Evaluation Reports on this subject, to be prepared by the NRC staff, must be issued on February 1,1981 and that all subsequent actions to be taken by Licensees to achieve full compliance with the DOR Guidelines or NUREG-0$88 must be completed no later than June 30, 1982.

In October 1980, EG&G awarded Franklin Research Center (FRC) a contract to provide assistance in the equipment environmental qualification review for 13 of the plants whose Licensees responded to IE Bullatin 79-013.

FRC was given the assignment to evaluate the Licensee's equipment environmental qualification submittal and to present the results in the form of a Technical Evaluation Report for each plant.

1.3 SPECIFIC ISSUE BACKGROUND The staff held regional meetings with the Licensees and interested parties during the week of July 13, 1980 in various locations. The staff issued a second supplement to IE Sulletin 79-01B, a response to significant questions raised during the public meetings, and two orders. The order dated May 30, 1980 required the Licensees to comply with the previously issued Ccamission Memorandum and Order of May 27,1980 (CLI-80-21). The above orders s

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TER-C5417-6 required the Licensees to complete the tasks identified in IE Bulletin 79-018 no later than November 1,1980 to allow the staff to comply with the February 1, 1981 date imposed by the Commission Order. The responses to the questions were issued on February 29, 1980; and the second and third supplements to IE Bulletin 79-013, highlighting the staff positions affecting the Licensees' responses, were issued September 29 and October 24, 1980, respectively.

1.4 SCOPE OF THE REVIEW Environmental qualification of safety-related electrical equipment was selected by the NRC for accelerated review. Therefore, the scope of this report is limited to equipment that must function to mitigate the consequences of a loss-of-coolant accident (LOCA) or high energy line break (HELB) and whose environment is adversely affected by that event.

I.) addition, IE Bulletin 79-013 requires enviremental qualification for all safety-related electrical equipment exposed to a harsh environment in accordance with the DCR Guidelines or NUREG-0588. Harsh environments include the limiting conditions resulting from (i) the entire spectrum of postulated line breaks resulting I

from a loss-of-coolant accident (LOCA) or a high energy line break (HELB) inside and outside of containment and (ii) radiation from fluids which are l

recirculated from inside containment to accomplish long-term cooling subsequent to an accident. Qualification aspects not included within the i

scope of this evaluation ares l

e seismic qualification equipment protection against natural phenomena e

equipment operational service conditions (e.g., vibration, voltage, e

l and frequency deviations) equipment located where it is subject to outdoor environments e

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e equipment protection against missiles.

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NBC CRITERIA FOR ENVIRONMENTAL QUALIFICATION 2.1 CRITERIA PROVIDED BY THE NBC l

The DCR screening guidelines used by FRC to evaluate the electrical equipment environmental qualification program were:

e " Guidelines for Evaluating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors" (64]

i e " Guidelines for Identification of That Safety B:ruipment of SEP j

Cperating Reactors for Which Envircnmentrl Qualification Is Ib Be Addressed" (64]

l e NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment." (69]

These guidelines were issued by the NBC in February 1980 for implementation by all Licensees.

2.2 STAFF POSITIONS AND SUPPLEMENTAL CRITERIA The NBC identified the following staff positions and supplemental criteria to be used in conjunction with the referenced DCR screening guidelines.

2.2.1 SERVICE CCNDITICNS INSIDE CCNTAINMENT EUR A LOSS-OF-COOLANT ACCIDENT l

(DCR GUIDELINES SECTION 4.1)

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For Pressurized Water Reactors (PWRs), the DCR Guidelines state that the containment temperature and pressure conditions as a function of time should be based on the most recent NRC-approved aorvice conditions specified in the Final Safety Analysis Report (FSAR) or other Licensee documentation. In the specific case of pressure-suppression type containments, the following mini:num high temperature conditions may be used:

(1) Boiling Water Reactor (BWR)

Dryvells - 340"F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and (2) PWR Ice Condenser Lower Compartments --

340*F for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. As stated in Supplement to IE Bulletin 79-013, (65]

"these values are a screening device, per the Guidelines, and can be used in l

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TER-C5417-6 lieu of a plant-specific profile, provided that expected pressure and humidity conditions as a function of time are accounted for."

Service conditions should bound those expected for coolant and steam line breaks inside containment with due consideration given to analytical uncertainties. h steam line break condition should include superheated conditions, with peak temperature and subsequent temperature / pressure profile as a function of time.

If containment spray is to be used, the irpact of the spray on required equipment should be accounted for.

Se adequacy of a plant-specific profile is dependent on the assumptions and design considerations at the time the profiles were developed. The DOR Guidelines and NUREG-0.i88 provide guidance and considerations required to determine if the calculated plant-specific temperature / pressure profiles encespass the LOCA and HELB accidents inside containment.

2.2.2 SUBMERGENCE (DOR GUIDELINES SECTION 4.1, SUBITEM 3; and SECTION 4.3.2, SUBITEM 3)

Equipment submergence (inside or outside containment) should be addressed where the possibility exists that submergence of equipment may result from HELBs or other postulated occurrences. Supplement 2 to IE Bulletin 79-018 (65] provides the following additional criterion:

If the equipment satisfies the guidance and other requirements of the DOR Guidelines or NUREG-0588 for the ICCA and HELB accidents, and Ihe Licensee demonstrates that its failure will not adversely affect any safety-related function or mislead the operatoe after submergence, the equipment can be considered exempt from the submergence portion of the qualification esquirements.

2.2.3 EQUIPME.Vf LOCATED IN AREAS NCRMALLY MAINTAINED AT ROOM CONDITIONS (DOR GUIDELINES SECTION 4.3.3)

Supplement 2 of IE Bulletin 79-01B (65] permits deferment of the revw of environmental qualification for all safety-related equipment items located in plant areas where the equipment is not exposed to the direct effects of a HELB or to nuclear radiation emanating from circulation of fluids containing radioactive substances. At the Licensee's option, the review may be deferred until af ter February 1,1981.

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g TER-C5417-6 By June ad,1982, all safety-related electrical equipment potentially expoaed to a harsh environment in nuclear generating stations licensed to operat-or before June 30, 1982 shall be qualified to either the DOR Guidelines or NUREG-0588 (as applicable). Safety-related electrical equipment is that required to bring the plant to a cold shutdown condition ind to mitigate the consequences of the accident. It is the responsibility of the Licensee to evaluate the qualification of safety-related electrical equipment to function in environmental extremos not associated with accident conditions and to dccument it in a form that will be available for the NRC to audit.

Qualification to assure functioning in mild environments must be completed by June 30, 1982.

2.2.4 SDfULATED SERVICE CONDITIONS AND TEST DURATION (DOR GUIDELINES SECTION 5.2.1)

The Guidelines require that the test chamber environment envelop the required service conditions for a time equivalent to the period from the initiation of the accident until the service conditions return to normal.

Supplement 2 to IE Bulletin 79-01B (65] provides the following additional criterion:

" Equipment designed to perform its safety-related function within a short time into an event must be qualified for a period of at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in excess of the time assumed in the accident analysis. The staff has indicated that tims is the most significant factor in terms of the margins required to provide an acceptable confidence level that a safety-related function will be completed. Ihe 1-hour qualification requirement is based on the acceptance of a type test for a single unit and the spectrum of accidents (small and large breaks) bounded by the single test."

2.2.5 DEFERME.Y:' OF QUALIFICATION REVIEW Supplement 3 to IE Bulletin 79-01B [66] permits the submittal of qualification documentation regarding the TMI Action Plan equipment and the equipment required to achieve and maintain a cold shutdown condition to be delayed as follows:

e Qualification information for installed IMI Action Plan equipment must be submitted by February 1, 1981.

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TER-C5417-6 Qualification information for future TMI Action Plan equipment e

(reference NUREG-0737, when issued), which requires NRC pre-implementation review, must be submitted with the pre-implementation review data.

Qualification information for TMI Action Plan equipment currently e

under NBC teview should be submitted as soon as possible.

Qualification information for TMI Action Plan equipment not yet e

installed that does not require pre-implementation review should be submitted to NBC for review by the implementation date.

e Qualification information for equipment required to achieve and maintain a cold shutdown condition should not be submitted later than February 1,1981.

2.2.6 TEST SEQUENCE (DCR GUiEINES SECTION 5.2.3)

Supplement 2 to II Bulletin 79-013 [65] provides the following additional criteria:

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' Sequential testing requirements are specified in NUREG-0588 and the DCR r.uideline s. Licensees must follow the test requirementr. of the applicable document.

1.

If the test has been completed without aging in equence, justification for such a deviation must be submitted.

2.

If testing of a given component has been scheduled but not initiated, the test sequence / program should be modified to include aging.

3.

Test programs in progress should be evaluated regarding the ability to comply by incorporating aging in the proper sequence. These programs would then fall in the first or second category."

2.2.7 RADIATICN (DCR GUIDELINES SECTIONS 4.1.2, 4. 2.2, and 4. 3. 2, SUBITEM 2)

Jupplement 2 to IE Bulletin 79-013 (65] provides the following addit onal criteria:

"Both the DCR Guidelines and NUREG-0588 are similar in that they provide the methods for determining the radiation source term when considering LOCA events inside containment (100% noble gases /50% iodine /lt partic-ulates). Olese methods consider the radiation source term resulting from an event which completely depressurizes the primary system and releases the source term inventory to the containment.

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e TER-C5417-6 NUREG-0578 provides the radiation source term to be used for determining the qualification doses for equipment in close proximity to recirculating fluid systems insid, and outside containment as a result of LOCA. This l

method considers a I4CA event in which the primary system may not depressurize and the source term inventory remains in the coolant.

NUREG-0588 also provides the radiation source term to be used for j

qualifying equipment following non-I4CA events both inside and outside containment (lot noble gases /10% iodine /04 particulates).

When developing radiation source terms for equipment qualification, the Licensee must ensure consideration is given to these events which provide the most bounding conditions. Se following table summarizes these considerations (RCS = reactor coolant system) :

LOCA Non-LOCA HELB Cutside Containment NUREG-0578 NUREG-0588 (100/50/1 (10/10/0 in RCS) in RCS)

Inside Containment targer of NUREG-0588 NUREG-0588 (100/50/1 (10/10/0 in Containment) in RCS) or NUREG-0578 (100/50/1 in.C )

Gamma equivalents may be used when consideration of the contributions of beta exposure has been included in accordance with the guidance given in the DCR Guidelines and NUREG-0588. Cobalt-60 is one acceptable ganna l

radiation source for environmental qualification of safety-related eculpment. Cesium-137 may also be used."

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METHCDOLOGY USED BY FRC IE Bulletin 79-013 required the Licensee to:

e provide a master list which identifies the systems and electrical i

equipment required to function during and subsequent to an accident and to maintain the plant in a safe condition e provide the environmental service conditions e identify the submergence levels provide written eviderae of the qualification of the equipment e

identified evaluate the qualification documentation using the DOR Guidelines and o

NUREG-0588 e submit a Licensee Event Report (LER) for electrical equipment determined not to be environmentally qualified.

The requirements of IE Balletin 79-013 were requested under provisions of 10CFR50.54 (f), " Conditions of Licenses," which requires the Licensee to submit written statements, signed under oath or affirmation, to enable the Cosmission to determine whether or not a Ticense should be modified, suspended, or revoked.

To provide assurance that the Licensee implemented the requirements of IE Bulletin 79-013 and to provide i basis for the NRC Safety Evaluation Report (SER), FBC developed this Technical Evaluation Report (TER) by:

assessing the Licensee's responses in relatien to the general e

requirements of the DOR Guidelines as augmented by the supplements to the 79-013 Bulletin e using NUREG-05a8 to resolve cpen issues.

l The results and conclusions contained in this report are valid assuming that the Licensee's analyses of test reports referenced in the Licensee I

submittal are correct. Review of test reports was not within the scope of FRC's assignment. However, the NRC staff will audit selected analyses and i

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TER-C5417-6 test reports, incorporating the results of the reviews with the conclusions of the TERs, when developing the plant-specific SERs.

tie Licensee, Tennessee Valley Authority, identified an extensive list of safety-related electrical equipment items in various locations of the Browns Ferry Nuclear Power Station Unit 3 in its submittals to the NRC.

FRC analyzed the Licensee's listing and grouped together all identical equipment items located within plant areas that are exposed to the same environental service conditions. This analysis resulted in a reduced listing containing 135 different equipment ?.tems that formed the basis for the review. Appendix A contains the environmental service conditions for each location, Appendix B contains a tabulation of the equipment items and locations (the tabulation does not include equipment covered by the evaluation deferment described in Section 2.2.3 of this report), and Appendix C lists the plant systems identified by the Licensee and the NRC as being essential to safety.

Using the listing of safety-related electrical equipment items,* each equipment item was reviewed by FRC in relation tot NRC DOR Guidelines, as modified by NBC staff interpretations e

e Licensee definition of harsh service environments (Appendix A) e analysis and/or justification of qualification e Licensee-proposed remedies for qualification deficiencies.

2: pics not within the sccpe of FRC evaluation ares l

e completeness of the Licensee's listing of safety-related equip ant e acceptability of Licensee-provided environmental service conditions e acceptability of Licensee-stated position concerning safety system or component function review and acceptability of qualification test reports and other e

qualification documentation.

• In this report, the term "saf ety-related electrical equipment" refers to the equipment defined by the two NRC Guidelines referenced in Section 2.1.

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TER-C5417-6 Upon completion of the final review for each equipment item, FRC developed an overall evaluation of the component and a specific conclusion with respect to its qualification. Based on the FRC conclusion, each equipment item was assigned to one of the generic qualification categories provided by the NRC.

NRC categories are described belcw.

All equipment item numbers discussed in Section 4 of this report are associated with Reference 68.

The NRC Office of Inspection and Enforcement conducted an on-site verification inspection of selected lE equipment to verify proper installation of equipment, overall interface integrity, location with respect to flood level for equipment inside the containaent, and manufacturer's nameplate data. The manufacturer and :nodel numoer from the nameplate data were ccapared to infor: nation given in the System Component Evaluation Work Sheets (SCEWS) of the Licensee's report. The details of this site inpection are documented in the IE Inspection Report thaber 50-296/80-36 and will be addressed by the NRC.

NBC QUALIFICATION CATEGORIES AND DEFINITIONS e NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES This category includes equipment items which are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment has been found to be qualified for the life of the plant.

e NRC Category I.b EQUIPMENT FCR WHICH DEVIATIONS FRCM THE DOR GUIDELINES ARE JUDGED ACCEP:ABLE This category includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelines; however, sufficient informatien has been presented to determine that the specific deviations are acceptable.

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TER C5417-6 e NBC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE This category includes equipment items that are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life.

o NBC Category II.b WUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES PROVIDED THAT SPECIFIC MODIFICATIONS ARE MADE This category includes equipment items which will be fully acceptable and will satisfy all applicable criteria defined in the DOR Guidelines provided that specific modifications are made on or before the designated date. When the modifications are complete, the equipment can be considered qualified.

e NBC Category II.c MUIPMENT FCR WHICH DEVIATIONS FRCM THE DOR GUIDELINES ARE JUDGED ACCEP!ABLE This category includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOP ':uidelines; however, either sufficient bases have been presented to al*:S a determination that the specific deviations are judged to be acceptable for less than plant life or the specific deviations are judged by FRC to be acceptable for less than plant life based on review of the applicable qualification documentation associated with the general equipment environmental qualification program.

e NRC Category III EQUIPMENT THAT IS EXMPT FRCM QUALIFICATION This category includes equipment items which are exempt from qualification on the basis that (i) the equip==nt does not provide a safety function (i.e., should not have been included in the equipment list submitted by the Licensee), (ii) the specific safety-related function of the compenent I

can be acccmplished by some other designated component which is fully qualified, or (iii) the equipment is not subject to a potentially adverse environment as a result of accidents for which proper operation of the equipment is required. In addition, any failure of the exempt ecmponent must I

not degrade the ability of a qualified component to perform its required j

safety-related function.

l e NRC Category IV.a j

EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLETED me qualification of equipment items in this category has been judged deficient or inadequate based upat review of the documentation provided by the Licensee. Ecwever, the Licensee has stated that the equipment item is 6

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TER-C5417-6 scheduled to be tested by a designated date. The results of the testing will dictate the specific qualification category of the equipment item. Specific justification for interim plant operation prior to testing should be provided for each ites.

e NRC Category IV.b EQUIPMENT FOR WHICH QUALIFICATICN DOCUMEWATICN IN ACCOR0ANCE WITH THE GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of equipment items in this category is deficient or inconclusive based upon review of the documentation provided by the Licensee.

This equipment is judged to have a high likelihood of operability for the specified environmental service conditions; however, complete and auditable records reflecting comprehensive qualification documentation have not been made available for review. Specific justification for interim plant operation should be provided for each ites.

B e NRC Category V I

EQUIPMER WHICH IS UNQUALIFIED The DCR Guidelines require that complete and auditable records reflecting l

a comprehensive qualification methodology and program be referenced and made available for review of all Class lE equipment.

Se qualification of equipment items in this category has been judged to be deficient or inadequate, based upon review of the documentatien provided by the Licensee. The extent to which the equipment items fail to satisfy the criteria of the DOR Guidelines can be categorized as follows:

(1) documen-tation reflecting qualification as specified in the DOR Guidelines has not been made available for review, (ii) qualification documentation made available for review is inadequate, or (iii) the documentation indicates that the equipment ites has not passed the required tests.

e SRC Category VI EQUIPME W FOR WHICH QUALIFICATICN IS DEFERRED This category includes eqcir ent items which have been addressed by the Licensee in the equipment environt-ental qualificatica submittals; however, the l

qualification review of this equipment has been deferred by the NRC in l

accordance with criteria presented in Sections 2.2.3 and 2.2.5 of this report.

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TECHNICAL EVALUATION 4.1 METHCDOLOGY USED BY THE LICENSE 2 The Licensee has submitted for Browns Ferry Units 1, 2, and 3 a rather voluminous equipment environmental qualification report (20 large volumes in total) dated October 31, 1980, in response to the January 14, 1980 NBC IE Bulletin 79-013 and Memorandum and Order CLI-80-21 dated May 23, 1980. All

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previous responses to IE Bulletin 79-013 (April 30 and July 18, 1980) are said to be superseded by this latest submittal. The final submittal [68] contained a general introductory section which described the Licensee's basic approach to qualification and evaluation methodology. A review by FRC has generated the following observations and comments.

4.1.1 COMPL2TENESS OF EQUIPMENT LIST The Licensee discussed the approach used in selecting the equipment for which qualification must be demonstrated. For example, the Licensee stated:

e As directed, TVA has evaluated the environmental qualification of the safety-related electrical components which experience the harsh environment due to Loss of Coolant Accidents (ICCA's) and High Energy l

Line Break (BELB) accidents. Only that equipment either required to function for accident mitigation (Category a, as defined in NUREG-0588, Appendix E) or required not to fail (Category b, as defined in NUREG-05a8, Appendix E) during accident mitigation, including those required for cold shutdown, are contained in this report.

e The 2 valuation Work Sheets (bis) in Appendix C [681 and their supporting appendices provide documentation of qualification as defined by the DOR Guidelines.

e Browns Ferry Nuclear Emergency Operating Instructions were also used to identify safety functions, safety systems, and components, f

e If a saf ety-related component's location in the plant was found to be outside the harsh areas, the item was deleted from the equipment list (although it still is required to be qualified for its nonaccident service environments). Before an item could be deleted, all associated items, especially cabling, were identified and their a

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locations reviewed against the harsh areas. This assured that input and output associated with the original item was fully reviewed for qualification.

FRC notes that IE Bulletin 79-OlB Supplement 2 requires that qualification documentation for all operating reactors (as of May 23, 1980) be evaluated using the DOR Guidelines. When sufficient detail is not provided by the DOR Guidelines, NUREG-05d8 Category II can be used. In addition, criteria to be used for evaluation of replacement compenents for these plants will be derived using NUREG-0588 Category I.

NUREG-0588 Category I criteria will be applied for documentation associated with reactor facilities whose construction permit safety evaluation reports were issued af ter July 1,1974.

For facilities whose construccion permits were issued prior to July 1,1974, NUREG-0588 Category II will be applied.

(NUREG-0588 Categories I and II refer to applicable criteria referenced to IEEE Standards 323-1974 and 1971, respectively.

FRC noter that the DOR Guidelines require the Licensee to review its emergency operating procedures to determine the electrical components needed or relied upon to perform safety functions or provide safety-related display information to the operator. FRC concludes that the Licensee methodology for identification of safety-related equipment is consistent with NRC requirements.

4.1.2 DEFINITION OF FQUIPMENT OPERATING TIME REQUIREMENTS The Licensee has defined the equipment operating time as follows:

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operating timt e..s defined as the time period during which a component must be available to perform its function. It was not considered to be the time actually required to perform an action (i.e., actual time required for a valve to close).

An operating time category was defined as specified time period starting at the accident initiation during which a component must be available to perform its function. This specified time period was I

given sufficient scope to incorporate all reasonable operating times required for the components in the category.

The following operating time categories were used:

1 W - One hour following accident initiation X - One day following accident initiation 6

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Y - Thirty days following accident initiation 2 - one year following accident initiation i

W-Z Items marked as "W-Z" are components that fit into operating category A for the first hour following accident initiation and then fit into operating category B for the duration of the event and recovery (taken to be one year for this report). Isolation valves fall into this situation. They are required to close as' then to remain closed.

X-Z Items marked as "X-Z" are components that fit into operating category A for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and then fit into operating category B for the year following the accident.

Y-3 Items marked as "Y-Z" are components that fit into operating category A for the first 30 days and then fit into operating category S for the remainder of the year following the accident.

Operating time categories were assigned based upon the review of components' functions. For components that perform multiple functions, each function was considered and the worst-case time requirement used for the components. Ge'neral functions were defined as having the following operating times categories:

W & W-Z - Primary and secondary containment isolation (including SCTS initiation) following a LOCA or HELB inside primary containment; isolation for a HELB outside primary containment (i.e., the specific line that breaks); scram initiation (RPS),

and open scram following a LOCA or HELB inside primary containment or a HELB in the main steam line valve vault.

X & X-Z - Primary and secondary containment isolation for HELBs outside primary containment (except for the line broken); scram initiation (RPS) and scram for HELBs outside primary containment (except for a main steam line break in the valve vault).

Y & Y-Z - High pressure ECCS Z - All other functions.

FRC EVALUATION:

FBC coraludes that the Licensee's approacn to operating time is acceptable.

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I TER-C5417-6 4.1.3 QUALIFIED LIFE The Licensee has not adequately addressed the topic of qualified life for any of the safety-related equipment identified by the Licensee as essential for safe shutdown of the plant. The DOR Guidelines required that equipment with components susceptible to degradation caused by thermal or radiation environmental conditions are to have an established qualified life.

The Licensee should maintain detalled maintenance records to demonstrate that those components which can be degraded are replaced on a scheduled basis l

in order to restore the equipment and minimize the likelihood of equipment failure to perform a safety-related function.

Qualified life is the :naximum period of normal service under specified conditions for wnich it can be demonstrated that the functional capability of the equipment at the end of the period is still adequate for it to perform its j

specified safety function for an applicable accident and to remain functional as long as requirM a fter the accident. The qualified life may depend on carrying out a specified maintenance program. The qualified life of some l

elements of an equipment assembly may be less than the qualified life of the assembly provided a program for replacement of such elements at intervals not exceeding their qualified lifetimes is specified and fulfilled. The qualified life of a particular equipment item may be changed during its installed life l

where justified by new information that permits a reanalysis of the l

qualification program.

i It is necessary to establish a qualified lifs for every type of safety-related equipment that requires environmental qualification. A l

conservative choice of qualified lire must be made to account for the assumptions and approximations made in tha qualification program.

The Licensee stated:

l At the time of procurement of the equipment, documented evidence of l

aging effects was not a requirement; however, TVA intends to meet the l

DOR Guidelines in Section 7.0.

If the equipment contains eterial subject to aging degradation (the guidelines require that this j

determination be made), an analysis was dor.e to determine the maintenance or change out interval. Whe; there was insufficient documentation to determine the thermal or radiation aging effects on a piece of equipment, a ptogram of eicher further analysis of materials

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TER-C5417-6 (when a detailed list of materials is obtained), or type testing was instituted. If neither of these options were available, a replacement or relocation plan was established. In general, the procurement specification required equipment whose intended service, determined either by repairs or replacements, was for the design life of the plant for 40 years; therefore, in our engineering judgment the device will be able to perform its safety function in the interim time period required for completely documenting qualificatien.

FRC notes that the salient points of the Licensee's methodology are e If equipment contains materials subject to aging degradation, an analysis was conducted to determine the maintenance or change out interval.

e When insufficient documentation existed to allow determination of aging effects, an analysis program or type tasting was instituted.

e An equipment replacement or relocation program was established in lieu of analysis or type where appropriate.

e Procurement specifications required 40 years design life; therefore the equipment will be able to perform safety functions in this interim period while complete documentation is being completed.

FRC concludes (1). that the procurement specifications requiring a 40-year design life provide absolutely no assurance that the degradation effects due to aging-related stresses on equipment have been reduced, accounted for, or eliminated and (ii) that the Licensee's basis approach to aging As acceptable however, FRC has found no substantive evidence of the use of the stated methodology and the subsequent Licensee conclusions and action relative to the actual evalaution of the individual equipment items in the EWS data.

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4.1.4 LICENSEE EVENT REPORTS (LER)

The Licens e has stated:

Item 6 of the bulletin required " Licenses Event Reports" (LER) be issued when a component is found not capable of performing its intended safety function. Section 5.2 of the report provides a i

Summary of F4uipment Qualification Status which included the LER I

number issued when the above determination has been made.

FRC notes, however, that the Licensee has left the LER column blank in Section 5.2 of the report. It is not clear whether there are no LERs or the Licensee has not completed its listing.

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4.1.5 LICENSEE'S GENERIC POSITIONS WITH RESPECT TO THE DOR GUIDELINES A. MARGIN The Licensee states:

In Section 6.0 of the DOR guidelines it is stated that margin only applies to type testing and that the guidelines in Section 4.0 for establishing service conditions include conservatisms which assure margins between the service conditions specificed and the actual conditions which could realistically be expected in a design basi; event. Based upon the above statements and the fact that all calculations for establishing service conditions meet or exceed the DOR Guidelines given in Section 4.0, no additional margin was considered for qualification by analysis. As stated in DOR Guidelines, Section 6.0, additional margin for the service

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conditions for type testing needs to be considered only if Section 4.0 and Gection 5.2 of the DOR Guidelines are not met; since the guidelines of Section 4.0 are met, margin was considered only if Section 5.2 was not met.

FRC concludes that this position is acceptable.

B. ACCURACY The Licensee states:

As stated in Enclosure 3 to IE Bulletin 79-013, specificed and demonstrated accuracies of all instruments for their trip functions and/or post-accident requirement must be provided. When the documentation did not clearly demonstrate the specified accuracy during the environmental extr.unes resulting from a DBE, a program of either further search for documentation that address accuracy or type testing was instituted.

In our engineering judgement, the following two statements provide justification for continued operation during the interim time period required to obtain completely documented qualifications:

(1) in general, the procurement specifications required and the vendoc's demonstrated accuracies are much more stringent than system requirements, (2) surveillance tests are conducted periodly as required by the technical specifications to confirm the validity of the manufacturer's stated accuracy.

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FRC concludes that the Licensee's position is acceptable for interim operation until full qualification can be obtained.

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1 TER-CS417-6 C. CPERATING DATA The Licensee states:

Substantial percentages of the systems components installed in plant locations other than inside pcimary containment, have well l

establist.ed industrial rating at or above the limits required for

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operation during and/or af ter the required DBE's.

In cases where J

operating data is used as a justification for interim qualification. This qualification will be supplemented at a later date by either type tasting and/or further analysis. If neither of j

l these options are available, a replacement plant was instituted.

l FRC notes that NRC required a definitive resolution by November 1980 from the Licensee on all qualification issues.

The Licensee's position is in variance with this requirement.

1 D. RELATIVE HUMIDITY I

I The Licensee states:

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The humidity ranges from 30 to 80 percent for areas outside primary containment. The values given in Section 3.0, Table 1, note E of this report are peak values and probability of occurence is extremely low. There are redundant fans servicing areas where there is essential equipment. Most industrial grade electrical equipment can function properly in the reactor zone building ambient humidity.

FRC concludes that this generic position is (i) not clear and (ii) does not alleviate the need for humidity to be addressed by the Licensee as an environmental service condition.

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E. TYPE TESTING The Licensee states:

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pressure, and steam service condition. However, analysis is l

acceptable if supported by test data, for the other service conditions.

A*. the time of equipment procurement, type testing was not a required esthod of proving qualification. To the extent that an analysis is not conclusive to verify qualification per the DCR 4-7 4W Franklin Resea.rc.h Center

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FBC notes that the DOR Guidelines stater Type Testing is the preferred method of qualification for electrical equipment located inside containment required te mitigate the consequences of dnsign basis events, i.e., Clus IE equipment (see Section 3.0 above). As a minimum, the qualifi-cation for severe temperature, pressme, and steam service conditions for Class IE equipment should be based on type testing. Qualification for other service conditions such as radiation and chemical sprays may be by analysis (evaluation) supported by test data.

FRC concludes that type testing is required, and that the Licensee's generic position regarding analysis and further search for qualification documentation is not in accordance with NRC requirements.

F. RADIATION The Licensee states:

e Be*a Radiation - According to Section 4.1 of the DOR Guidelines, beta radiation has low penetrating power in comparison to gamma rays of equivalent energy. Of the general classes of electrical equipment in the plant conteinment (e.g., cables, instrument transmitters, valve operators, containment penetrations),

electrical cable is considcred the most vulnerable to damage fecm beta radiation. Por othe:: equipment whose enclosure provides adequate shielding, beta radiation need not be considered. For any equipment that is determined unshielded (e.g., cable) or is shielded by sheet metal of 'l0 gauge or less, an analysis of the qualification of the equipment related to beta radiation was included as attachments to the ENS's.

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e Gamma Radiation - From Table C-1 in Appendix C in the DOR Guidelines and references 1 and 2 below, there is substantial test data available to demonstrace that most conventional material used in electrical equipment has a gamma radiation threshold exceeding 4

10 rads; the er.ception is solid-state devices containing N-MOS 3

integrated circuits which have a threshold of 10 rads (see Table C-1). Teflon has a threshold for damage of approximately 3.5 x 104 rads (for 20 percent decreases in elongation). Electrical properties (e.g., resistivity) of these materials are sufficiently l

conserative initially, such that substantial ch:nges can be tolerated without causing equipment failures or malfunction.

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TER-CS 417-6 Threshold is defined from the above referenced table as the radiation exposure required to change at least one physical property of the material. The threshold is not a point of failure or end of useful life; therefore, there is a band of tolerance from the threshold point to the failure point which may vary by an order of magnitude or more.

i On the above basis and the existing test data, it is not considered necessarytoperformaqualificationstestoranalgsison electrical equipment for radiation of less than 10 rads which would degrade the safety function of the equipment.

FRC agrees with the Licensee's position.

4.1.6 REQUIRED SIGNATGES The Licennte has stated:

e To ensure complaceness and accuracy of the EWS, signatures of a' preparer, reviewer, and quality assurance engineer are required on each of the EWS.

Any appendixes fer which the preparer or reviewer of g

EWS was not directly responsible will also contain preparer and

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reviewer signatures.

The most significant changes to the EWS were as follows: 1) use of e

appendixes, 2) use of permanent notes, 3) required signatures, and 4)

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use of unique numbering system for the EWS and their appendixes.

FRC notes that none of the sheets appears to be signed by a quality assurance engineer.

4.1.7 CHEMICAL SPRAY The Licensee states:

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Chemical spray is not applicable for this report since no chemical injection is used.

(This is a permanent note N/A on all EWS sheets.'

FRC notes that the DOR Guidelines require demineralized water sprays to be addressed. In addition, the effects of in-leakage must be considered. The I

Licensee has not complied with this requirement.

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TER-C5417-6 4.

1.8 DESCRIPTION

OF QUALIFICATION / REPLACEMENT PLAN The Licensee states:

It is TVA's intention to comply fully with the requirements of Bulletin 79-013.

This section addresses the requirements stated in item 4 of the bulletin for " outstanding items."

It is not possible to submit a detailed qualification / replacement plan at this time.

The following items have a great tapact on our inability to supply a detailed schedule at this time:

a.

Limitations en industry's capability for testing large numbers of components.

b.

Availability of qualified replacement equipment.

c.

Unit outage schedules.

TVA has a contract with Wyle Laboratories to do any testing that is required to prove qualification of any questionable equipment. Wyle will also provide TVA a detailed schedule of all tests they plan to conduct for TVA.

-d When we receive schedules of testing from Wyle Lah, we will inform the NRC as stated in your letter dated October 1, 1980, from D. G. Eisenhut t

to licenaees of operating plants. TVA will make a best faith effort to test equipment as aoon as possible. However, if problems are encountered with either the testing or qualificability of the equipment, the justification for continued operation will be reviewed as well as a safety review. It is our plan to schedule first the items that have the greatest impact on safety.

The qualification status of all equipment is listed in Table 5.2.

The status of all items falls into one of four categories as liated below.

Category I - Components qualified to DOR guidelines.

Category II - Components for which analysis indicating qualification but that lack documentation to prove qualification to DOR quidelines.

Category III - Items that will be qualified by either analysis or type testing or a combination of these methods.

Category IV - Equipment to be replaced.

For Category IV equipment checks were made to determine the availability of qualified equipment on the market. In general, even if qualified equipment is available the delivery has a long and indefinite lead time.

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TER-C5417-6 TVA will submit a detailed schedule for qualifying or replacing all open items by February 1, 1981. This schedule will be developed in conjunction with Wyle Labs.

FRC concludes that the Licensee has not complied with the NRC requirement that the Licensee must submit all qualification information to NDC by November 1, 1980. With this information, an exact schedule for equipment replacement l

and specific justification for interi:n operation must be provided for any item l

whi:::h does not conform to Guidelines requirements.

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TER-CS417-6 4.2 EQUIPMENT QUALIFIED FOR PLANT LIFE This section includes equipment items which are fully acceptable on the basis that (i) all criteria defined in Section 2 of the report are satisfied or (ii) sufficient data exist to determine acceptability by judgment.

4.2.1 NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES This section normally includes equipment items which are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and the equipment has been found to be qualified for the life of the plant. For Browns Ferry Unit 3, no equipment items fall into this category.

4.2.2 NBC Category I.a EQUIPMENT FOR iGIICH DEVIATIONS FROM THE DOR GUIDELINES ARE JUDGED ACCEPTABLs This section nor:nally includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelines; however, sufficient information has been presented to determine that the specific deviations are acceptable. For Stowns Ferry Unit 3, no equipment items fall into this category.

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TER-C5417-6 4.3 EQUIPfGNT QUALIFIED WITH RESTRICTIONS This section includes equipment items fully acceptable on the basis that (i) all criteria defined in Section 2 of this report are satisfied (ii) the equipment is qualified for a time interval less than plant life; or (iii) the equipment requires specific modifiation which, when completed, will estab1':.a full qualification.

4.3.1 NRC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE The following equipment items are fully acceptable on the bash that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life.

4.3.1.1 Equipment Ites No. 24 Solenoid valve Target Rock Model 73FF-005 (Licensee Reference 34)

The Licensee has shown that this equipment is qualified to function in a post-accident environment, and that the equipment is qualified for a specific time interval less than plant life.

4.3.1.2 Equipment Item No. 132 Electrical Penetration Assembly GE Model NSO4 (Licensee Reference 23)

The Licensee has provided documentation that shows this equipment to be qualified :o function in a post-accident environment, but for a time interval less than plant life.

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TER-C5417-6 4.3.2 NRC Category II.b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES PROVIDED THAT SPECIFIO MODIFICATIONS ARE MADF The equipment items in this category will be fully acceptable and will satisfy all applicable criteria defined in the DOR Guidelines provided that specific modifications are made on or before the designated ste. When the modifications are completed, the equipment can be considered qualified. For Browns Ferry Unit 3, no equipment items fall into this category.

4.3.3 NRC Category II.c EQUIPMENT FOR WHICH DEVIATIONS FRCM THE DOR GUIDELINES ARE JUDGED ACCEPTABLE This section includes equipment items which do not satisfy one or :nore of the applicable criteria defined in the DOR Guidelines; however, either suffic.4nt bases have been presented to allow a determination that the specific deviations are judged to be acceptable for less than plant life, or the specific deviations are judged by FRC to be acceptable for less than plant life based on review of other applicable qualification documentation associated with the general equipment environmental qualification program. For Browns Ferry Unit 3, no equipment items fall into this category.

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I TER-C5417-6 4.4 NRC Category III EQUIPMENT THAT IS EXEMPT FROM QUALIFICATION Equipment items in this category are exempt from qualification on the basis that (i) the equipment does not provide a saftsty function (i.e., should not have been included in the equipment list submitted by the Licensee), (ii) the specific safety-related function of the component can be accomplished by some other designated component which is fully qualified, or (iii) the equipment is not subject to a potentially adverse environment as a result of accidents for which proper operation of the equipment is required.

In addition, any failure of the exempt component must not degrade the ability of a qualified component to perform its required safety-related function. For Browns Ferry Unit 3, no equipment items fall into this category.

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TER-C5417-6 4.5 EQUIPMENT ECR WHICH DOCUMENTATION CONTAINS C3VIATIONS FROM THE GUIDELINES THAT ARE JUDGED UNRESOLVED This section includes equipment items which are deficient on the basis that all criteria defined in the DOR Guidelines are not satisfiedt however, the equipment item is either scheduled to be tested or is judged to have a high likelihood of operability.

4.5.1 NRC Category IV.a EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLETED The qualification of equipment items in this category has been judged deficient or inadequate based upon FRC's review of the documentation provided by the Licensees however, the Licensee has stated that the equipment item is scheduled to be tested by a designated date.

The results of the testing will dictate the specific qualification category of the equipment item. Specific justification for interim plant operation prior to testing should be provided for each item.

For Browns Ferry Lhit 3, no equipment items fall into this category.

4.5.2 NRC Category IV.b IQUIPMENT FOR WHICH-QUALIFICATION DOCUMENTATION IN ACCORDANCE WI"'M THE GUIDELINES 1AS NOT BREN ESTABLISHED The qualification of the following equipment items is deficient or inconclusive based upon FRC's review of the documentation provided by the Licensee. This equipment is judged to have a high likelihood of operability for the specified environmental service conditionst however, complete and auditable records reflecting comprehensive qualification documentation have not been made available for review. Specific justification for interim plant operation sho'id be provided for each item.

4.5.2.1 Equipment Item No.1 Solenoid Valves AAA Mode 1 SO2 (Licensee reference not ei'. ed)

The Licensee has not provided qualification information for this equipment item and requests permission for contir ued use of the solenoid valve based on 6

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TER-C5417-6 the contention that similar solenoid-operated valves have successfully operated in the environment specified for this equipment item. The Licensee will type test this item or replace it with qualified equipment during the next refueling outage.

4.5.2.2 Equipment Item No. 2 Plow Indicating Switch Fischer & Porter Model 10A2235A-55AR1011 (ficensee reference not cited)

This equipment item has not been qualified, but the manufacturer's specifications indicate that this type switch has been tested and found to operate successfully at temperatures of 250*F and atmospheric pressure. TVA states that it will type test or replace this equipment (no date specified).

4.5.2.3 Equipment 7. tem No. 3 Differential Pressure Switch Dwyer Model 3302 (Licensee reference not cited)

This equipment item has not been qualified to operate in a post-accident environment. The Licensee will replace this item with qualified equipment during the next refueling outage that follows delivery of qualified equipment.

4.5.2.4 Equipment Item No. 4 Solenoid Valve ASCO Model EB830281RU (Licensee reference not cited)

The Licensee failed to submit qualification documentation for this equipment item, but bases justification for continued cperation on tests of similar valves from the same manufacturer. The Licensee will type test this item or replace it with qualitied equipment during the next refueling outage.

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4.5.2.5 Equipment Item No. 5 Pressure Differential Modifier Honeywell Model: Relay Assembly R7165-1078 Terminal Assembly 127100 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification information for this equipment item, but will type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.6 Equipment Item No. 6 j

Pressure Differential Indicating Controller Fischer & Porter Model 53EL3311BalB ESL-01 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification information for this equipment, but will type test the device or replace it with qualified equipment during the next refueling outage.

4.5.2.7 Equipment Item No. 7 Pressure Differential Transmitter Fischer & Porter Model 10B2494TBAB (Licensee Reference 62)

The Licensee has provided documentation that shows this item to be qualified for radiation dose after an accident. Other environmental conditions h3ve not been evaluated, however, and the Licensee will either type test this equipment or replace it with a qualified device during the next I

refueling outage.

4.5.2.8 Equipment Item No9, 8, 11, and 13 Solenoid valve ASCO Models HB830081RU, EV200-924-lF, and HT8262A203A (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation for this item, but will either type test this item or replace it with qualified equipment during the next refueling outage.

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TER C5417-6 4.5.2.9 Equipment Item Nos. 9 and 10 Temperature Element Weed Model SP60llAA3C275SN42 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation for these equipment items, but will type test the items or replace them with qualified equipment during the next refueling outage.

4.5.2.10 Equipment Item No. 12 Plow Transmitter GE/MAC Model 50-554212BKZZ3 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation, but will either type test this item or replace it with qualified equipment during the next refueling outage.

4.5.2.11 Equipment Item No. 14 Pressure Transmitter Bailey Model 551 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation for this equipment and will either type test this item or replace it during the next refueling outage.

4.5.2.12 Equipment Item No.15 Flow Transmitter GE/MAC Model 555 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to snow that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

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TER-C5417-6 4.5.2.13 Equip'ent Item No. 16 Temperature Switch Fenwal Model 18002-27 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.14 Equipment Item No. 17 Solenoid valve ASCO Model HTX8300B61U (Licensee reference nc* c.ited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

n 4.5.2.15 Equipment Item No. 18 Solenoid Valve ASCO Model 8300C610 (Licensee reference not cited)

The Licensee has failed to submit sufficient qualification documentation for this equipmant and does not state the intention to replace or type test it.

4.5.2.16 Equipment Item No. 25 Solenoid Valve ASCO Model aT8211C94 (Licensee reference not cited The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

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TER-C5417-6 4.5.2.17 Equipment Item No. 26 Indicator Pressure Converter Fisher Controls Model 546 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment l

during the nexc refueling outage.

V 4.5.2.18 Equipment Itea No. 27 Pressure Switch Custom Components Model 630GH (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling o'Itage.

4.5.2.19 Equipment Item Nos. 29 and 31 Thermostat Honeywell Models T675A1508 and T675A1540 l

(Licendee reference not cited)

The Licensee has failed to provide qualification documentation to show l

that this item will successfully function in a post-accident environment. The l

Licensee will either type test the item or replace it with qualified equipment during the next refueling outage, by June 1982.

4.5.2.20 Equipment Item No. 30 l

Damper Motor l

Honeywell Model M445A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident envf ronment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage, by June 1982.

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m TER-C5417-6 4.5.2.21 Equipment Item Nos. 36 and 37 Motor GE Models SK4254XL2 and SK6226XJ201A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.22 Equipment Item No. 48 Level Indicator Switch Yarway Model 4418C (Licensee Reference 46)

The Licensee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee will retest this equipment.

4.5.2.23 Equipment Item No. 53 Temperature Element Calmatic Model 158B7061P016 l

(Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.24 Equipment Item Nos. 58 and 59 Flow Transmitter GE/MAC Model 50-555111BOAA3AAA (Licensee reference not cited)

The Licensee has failed to provide qualification doc 2 mentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment

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during the next refueling outage.

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4.5.2.25 Equipment Item No. 64 Limit Switch Micro Switch Models OPD-AR and OPD-AR30 1

(Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.26 Equipment Item No. 66 Temperature Switch Fenwal Model 40-104014-103 (Licensee reference not cited)

I The Licensee has failed to provide qualification documentation to show that **.s item will successfully function in a post-accident environment. The L*.ensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.27 Equipment Item No. 67 Temperature Element Fanwal Model 28-232106-304 (Licensee reference not cited) 1 The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

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4.5.2.28 Equipment Item No. 73 Limit Switches NAMCO Model D1200G (Licensee reference not cited) i The Licensee has failed to obtain qualification documentation to show that this item will successfully function in a post-accident environment. The 1

l Licensee vill either type test the item or replace it with qualified equipment during the next refueling outage.

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TER-C5417-6 4.5.2.29 Equipment Item No. 76 Pressure Transmitter GE/MAC Model Series 30 and 55 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.30 Equipment Item No. 77 Power Supply CE Models 570012FAACl and 583001AAGK1 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully functier. in a post-accident environment.

4.5.2.31 Equipment Item No. 79 Temperature Element American Standard Model 158B7079P051 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.32 Equipment Item Nos. 85 and 86 Temperature Element Scam Model S51-1 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident envitonment. The Licensee will either type test the item or replace.t with qualified equipment.

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TER-C5417-6 4.5.2.33 Equipment Item Nos. 90 and 96 l

Turbine Control Valve Terry Turbines Types GS and CCS (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

4.5.2.34 Equipment Item No. 92 l

Pressure Switch Mercoid Models DA-7043-804 and DA-23-804 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

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l 4.5.2.35 Equipment Item No. 94 l

Square Root Converter l

GE Model 565100AAAC1 l

(Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident _ environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.36 Equipment Item No. 99 Level Switch Robertshaw Model SL-202-A2X (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.37 Equipment Item No. 105 Pump Motor GE Model SK634axC23A (Licensee reference not cited) l l

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will perform further tests to verify qualification of this equipment.

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4.5.2.38 Equipment Item No. 107 Pump Motor GE Model SK6336XC198A (Licensee reference not cited)

The Licensee has failed to provide sufficient gaalification documentation to show that this item will successfully function in a post-accident environment, and states that further evaluation is necessary to determine qualification of this equipment item.

4.5.2.39 Equipment Item No. 109 Hydrogen Element GE Model 47E226428G2 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification docuemtnation to shcw that this item will successfully function in a pect-accident environment, and states that further evaluation is necessary to determine qualification of this equipment item.

4.5.2.40 Equipment Ites No. 110 Level Switch GEMS Model XM-36425 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will succassfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

i 4.5.2.41 Equipment Item No. 111 Solenoid Valve Versa Model V0G-3521 1

(Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensea will either type test the item or replace it with qualified equipment.

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TER-C5417-6 4.5.2.42 Equipment Item No. 112 Limit Switch Micro Switch Model BZE6-2RN (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.43 Equipment Item No. 113 Level Switch Autocon Model M-4 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.44 Equipment Item No. 114 Temperature Element Thermo-Elect Model 37532-1 (Licensee reference not cited)

J The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.45 Equipment Item No. 115 Level Switch Meletron.W el 9241-6SS10A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

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TER-C5417-6 4.5.2.46 Equipment Item No. 117 Solenoid Valve ASCO Model HVA86-030 (Licensee reference not citied)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.47 Equipment Item No. 118 Position Switch Micro Switch Model BZE6-2RN (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.48 Equipment Ie:2 No. 119 CRD Scram Inlet Valve ASCO Model HVA-90-405-2A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.49 Equipment I?,m No. 120 Level Switch Robertshaw Model SL-305-E3-X (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. 7e

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Licensee will either type test the item or replace it with qualified equipment.

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l 4.5.2.50 Equipment Item No. 121 Ion Chamber GE Model 237X731G001 l

(Licensee reference not cited) l The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The l

Licensee will either type test the item or replace it with qualified equipment.

4.5.2.51 Equipment Item No. 122 Sensor and Converter GE Model 194X927G014,12 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show i

l that this item will successfully function in a post-accident environment. The

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Licensee will either type test the item or replace it with qualified equipment.

4.5.2.52 Equipment Item No. 123 Fission Product Monitor GE, Model Not Stated l

(License reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-eccident environment. The Licensee will either type test the item or replace it with qualified equipment.

l 4.5.2.53 Equipment Item No. 124 TIP System Valve Assembly GE Model 136B1302G2 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

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l 4.5.2.54 Equipment Item No. 125 Transformer GE Model llCH2L4 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that the item will successfully function in a post-accident environment.

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TER-C5417-6 4.5.2.55 Equipment Item No. 126 Motor Control Center International Switchboard Corp., Model Not Stated (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee states that it is pursuing the acquisition of the appropriate qualification information.

P 4.5.2.56 Equipment Item No. 127 Motor Control Center GE Model 7700 Series (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee states that it is pursuing the acquisition of the appropriate qualification documentation.

4.5.2.57 Equipment Item No. 129 Solenoid Valve Target Rock Model 1/2 SMS-A-01-1 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that. this item will successfully function in a post-accident environment. The j

l Lictnsee will either type test the item or replace it with qualified equipment.

i 4.5.2.58 Equipment Item No. 32 Motor-operated Valve Limitorque Model SMB-000 (Licenses Reference 40)

The Licensee has provided documentation that shows this item to be

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qualified in all areas except operating time. However, the Licensee states that substantial aging tests have been conducted and that, in its judgment, this more than satisfies the requirements of the DOR Guidelines.

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I TER-C5417-6 FRC finds this evidence to be inconclusive and necessitates further testing.

I 4.5.2.59 Equipment Item No. 68 Pump Motor GE Model 5K326PK-234A (Licensee reference not cited)

The Licensee states that redundant equipment is available to mitigate the accident; consequently, it suggests that this equipment item need not be

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qualified. No qualification information is presently available to the Licensee or FRC.

The Licensee should pursue qualification of this equipment.

4.5.2.60 Equipment Item Nos. 42 and 43 l

Pressure Solenoid Operator Automatic valve Corp. C5497 (Licensee Reference 42)

The Licensee has provided insufficient documentation to enable, evaluation of qualification for this equipment item.

4.5.2.61 Equipment Item No. 41 Differential Pressure Indicator Switch Barton Model 278 (Licensee reference not cited)

The Licensee has fail".. to provide qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee requests approval for interim operation based on the post-accident information provided by redundant low pressure instrumentation for MSIVs.

l 4.5.2.62 Equipment Item Nos. 22 and 23 Solenoid Valve Valcor Model 5260 (Licensee Reference 33)

The Licensee has provided documentation that shows this device to be qualified to function in a post-accident environment. However, in view of IE l

l Sulletin 30-23, validity of the testing should be verified.

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TER-C5417-6 4.5.2.63 Equipment Item No. 133 Penetration Assembly GE Series 100 (Licensee Reference 22)

The Licensee has provided d qualified to function in a post ocumentation that shows thisBulletin 77-06, the qualifi

-accident environment.

equipment to be cation status should be verifi dHowever, in view of IE e.

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TER-C5417-6 4.6 NCR Category V EQUIPMENT WHICH IS UNQUALIFIED The DCR Guidelines require that complete and auditable records reflecting a comprehensive qualification methodology and program be referenced and made available for review of all Class lE equipment.

The qualification of the following equipment items has been judged to be deficient or inadequate, based upon FRC's review of the documentation provided by the Licensee. The extent to which the equipment items fail to satisfy the criteria of the DCR Guidelines can be categorized as follows:

(i) documenta-tion reflecting qualification as specified in DOR Guidelines has not been made available for review, (ii) documentation reflecting qualification has been made available for review and is totally inadequate, or (iii) the documenta-tion indicates tnat the equipment item has not successfully passed required tests. S e following equipment items are therefore considered unqualified.

4.6.1 Equipment Item Nos.19, 20, and 21 Solenoid valve ASCO Model HB830081F i

(Licensee Reference 32)

The Licensee has provided documentation that shows this equipment to be unqualified. me Licensee will retest the item or replace it with qualified i

equipment.

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l 4.6.2 Equipment Item No. 28 l

Component Assembly Nuclear Measurement Corp., Model Not Stated (Licensee References 35, 36, and 37)

The Licensee has provided documentation that shows this equipment does not j

fulfill Guidelines requirements for temperature, humidity, and radiation dose. The Licensee will retest these monitors to determine if they will i

functicn in the post-accident environment specified in this area of the plant.

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i TER-C5417-6 4.6.3 Equipment Item Nos. 23, 34, and 35 Motor-Operated Valve Limitorque i4odel SMB-000 (Licensee Reference 40)

The Licensee has provided qualification documentation that shows this item to be unqualified according to DOR Guidelines. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.6.4 Equipment Item No. 39 Pressure Solenoid Operator Target Rock Model 1/2 SMS-A-01 (Licensee Reference 41)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for radiation dose, aging, and operating time. The Licensee will either retest this equipment or ter'.~.ce it with qualified equipment.

4.6.5 Equipment Item Nos. 44 and 45 Temperature Switch Fenwal Model 17002-40 (Licensee Reference 43)

The Licensee has provided documentation that shows this equipment to be qualified in all areas except. radiation and aging. The Licensee will retest i

this equipment or replace it with qualified items.

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4.6.6 Equipment Item Nos. 46 and 47 Pressure Swi*Jh Barksdale Model B2T-A12SS (Licensee References 44 and 45)

The Licensee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment.

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TER-C5417-6 4.6.7 Equipment Item Nos. 49 and 50 Pressure Switch Barton Model 288 (Licensee References 47 and 48)

The Licensee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment.

4.6.8 Equipment Item Nos. 51 and 52 Level Indicator Switch Barton Model 288A (Licensce References 47 and 48) j The documentation provided by the Licensee shews this equipment to be unqualified to successfully function in a post-accident environment.

4.6.9 Equipment Item Wos. 55, 56, 61, 62, 81, 82, 83, 84, and 35 Motorized Valve Actuators i

Limitorque Models SMB-2, SMB-00, SMS-3, SMB-0, and SMB-1

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(Licensee Reference 49) l 1

The documentation provided by the Licensee fails to show this equipment item is qualified to meet post-accident environmental specifications. The Licensee will subject this equipment to a retest to establish possible_

l qualification.

4.6.10 Equipment Item Nos. 54, 57, and 60 Motorized Valve Actuator Limitorque Models SMB-2 and SMB-00 (Licenseo Reference 49)

The Licensee has failed to provide adequate aging documentation for this equipment item, but argues for its permanent exemption from the DOR Guidelines based on Limitorque Test Reports B0003, B-0027, and 600198 which show that this equipment performed successfully at temperatures nigher than post-accident temperatures, although for a shorter time.

L-In resoonse to the Licensee's position, FRC finds this equipment l

unqualified.

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TER-C5417-6 4.6.11 Equipment Item No. 65 Solenoid Valve ASCO Model X8300-B61F (Licensee Reference 42)

The Licensee has provided documentation from ASCO Test Report AQS-21678/TR that shows this equipment to be unqualified in the areas of aging and test duration.

4.6.12 Equipment Item No. 70 Solenoid Valve ASCO Model WPHTX8300B45F,R (Licensee Reference 42)

The Licensee has provided test report documentation that shows this item to be unqualified in the area of test duration. Aging effects for this valve have not been evaluated.

4.6.13 Equipment Item No. 75 Plow Switch Barton Model 289 (Licensee References 53-55)

The Licensee has provided documentation that shows this equipment does nut fulfill Guidelines requirements exposure for radiation, test duration, and aging. The Licensee will subject this equipment to further qualification testing or replace it with qualified equipment.

4.6.14 Equipisent Item No. 78 Level Transmitter Rosemount Model 1151 Series (Licensee References 56 and 57) 1 The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for operating time and radiation exposure.

Aging qualification has not been documanted.

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i TER-C5417-6 4.6.15 Equipment Item Nos. 88 and 89 Temperature Switch Fenwal Model 17023-6 (Licensee References 3 and 43)

The Licensee has provided documentation that shows this item does not fulfill Guidelines requirements for radiation and aging. The Licensee considers the effects of aging due to the nor:nal environmental conditions negligible.

c FRC finds this equipment to be unqualified.

4.6.16 Equipment Item No. 91 Pressure Switch Barksdale Model PIH-M85SSV (Licensee References 44 and 45) l l

The Licensee has provided documentation that shows this equipment does i

not fulfill Guidelines requirements for temperature, radiation exposure, and operating time. The Licensee will retest this equipment or replace it with i.

qualified devices.

l 4.6.17 Equipment Item No. 93 Pressure Switch Static-O-Ring Models 6N-AA21 and 6N-AA21-V

(

(Licensee Reference 58) l The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, radiation exposure, and operating time. The Licensee will retest this equipment and replace it if it proves to be unqualified to suitably function ir a post-accident environment.

4.6.18 Equipment Item No. 97 Pressure Switch Barksdale Model D2H-M150SS (Licensee References 44 and 45)

The Lic6r.see has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, operating time, and aging i

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Tol-C5417-6 effects. The Licensee wtil retest this equipment to verify qualification or replace it with qualified equipment.

4.6.19 Equipment Item No. 98 Motor Operator Limitorque Model SMB-4T (Licensee Reference 49)

The Licensee has provided test data that shows this equipment does not fulfill Guidelines requirements for temperature and operation duration.

4.6.20 Equipment Item No. 100 Pressure Switch Static-O-Ring Mcdel,5N-rA3 (Licensee Reference 58)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements foe radiation exposure, temperature, operating time, and aging effects-The Licensee will either retest the equipmant or replace it with qualified equipment.

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4.6.21 Equipment Item Nos. 101 and 103 Motor Operator Limitorque Models SMB-5T and SMB-4 (Licensee Reference 49)

The Licensee has provided documentation from Limitorque Tist Reports 600197, B-0027, and B-0003 that shows this equipment does not fulfill Guidelines requirements for temperature, operating time, and radiation effects. The Licensee will continue testing to verify conclusions of the previously referenced test reports.

4.6.22 Equipment Item No. 102 Motor Operater Limitorque Model SMB-4 (Licensee Rr.ference 49)

The Licensee has provided documentation that shows this equipment to be unqualified in the area of operating time. Aging criteria have not been addressed.

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TER-C5417-6 4.6.23 Equipment Item No. 104 Differential Pressure Indication Switch Barton Model 289A (Licensee References 48 and 53)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, radiation exposure, and operation time.

4.6.24 Equipment Item No. 10G Flow Switch Barton Model 289 (Licensee References 53 and 54)

The Licensee has previded documentation that shows this equipment does not fulfill Guidelines requirements for radiation exposure, operating time, and aging effects. The Licensee will either provide further qualification documentation or replace tne item with qualified equipment, 4.6.25 Equipment Ites No. 108 t

Solenoid Valve ASCO Models X8315 and C28 (Licensee Reference 42)

The Licenses has referenced ASCO qualification test report AQS-21678/Ta covering the 8300 series ASCO valves and finds them qualified in all areas except operation time and aging effects. In TVA's judgment, this equipment is of sufficient quality to function successfully in a design based post-accident environment.

FRC judges this equipment item to be unqualified until further documentation can be provided to verify qualification.

4.6.26 Equipment Item No. 116 Level Switch Barksdale Model D2H-M18SS I

(Licensee References 44 and 45)

The Licensee has provided documentation that shows this equipment to be unqualified in the areas of operating time and aging requirements.

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TER-C5417-6 4.6.27 Equipment Item No.128 Motor Generator Louis Allis Model 3-127033 (Licensee References 4 and 59)

The Licensee has provided documentation that shows this equipment to be unqualified in the areas of operating time and aging effects.

4.6.2S Equipment Item No. 131 Terminal Block GE Models EB-5 and CR15182 (Licensee References 24, 25, and 26)

The Licensee has provided documentation that shows this equipment to be unqualified in the area of radiation effects.

4.1.29 Equipment Item No.134 Switches GE and Cutler Hammer Models GE-CR2940 and CH-10250T (License Reference 61)

The Licensee has provided qualification documentation that shows this item is unqualified in the areas of operating time and radiation. The

~

Licensee will et tinue equipment testing to determine the ultimate qualification of t'ais equipment item.

4.6.30 Equipment Item No. 38 Motorized Valve Actuators Rotork Model 14A (Licensee Reference 63)

The Licensee has provided documentation that shows this item to be qualified in all areas except operating time and temperature.

4.6.31 Equipment Item Nos. 40 and 63 Pressure Solenoid Operator ASCO WPH XS300B68F (Licensee Reference 42)

The Licensee has provided documentation that shows this equipment to be unqualified in the areas of radiation, aging, and operating time. Further s

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TER-C5417-6 testing is necessary to,@.ow that this equipment is qualified to adequately operate in a post-accident environment.

4.6.32 Equipment Item No. 74 Pressure Switch Barton Model 289 (Licensee Refer.nces 53-55)

The Licensee has provided documentation that shows this device to be unqualified in the areas of t'.st duration and aging.

4.6.33 Equipment Item No. 69 Explosive valve Lonax Model 1832-117 (Licensee References 50 and 51)

The Licensee has provided data from test report Refererences 50 and 51 that shows this equipment to be unqualified in the areas of radiation and aging effects. The Licensee suggests that specification for radiation level is unnecessarily conservative and that this valve is qualified to operate I

successfully for up to 30 days in a post-accident enviror. ment. However, this information has not resolved qualification of this equipment item.

4.6.34 Equipment Ites No. 80 Pressure Switch Static-O-Ring Mcdel 12N/AA4 (Licensee Reference 58)

The Licensee has provided documentation that shows this equipment is l

unqualified in the areas cf operating time, radiation, and aging effects.

4.6.35 Equipment Item Nos. 71 and 72 Limit switch NAMCO Model EA740-50100 (Licensee Reference 52)

The Licensee has provided documentation from Reference 52 (Acme-cleveland Development Co. Test Report 2/20/78) that shows this equipment to be qualified in all areas for up to 7 years. However, the report notes that the Licensee a

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TER-C5417-6 must use a qualified method for sealing the switch. The seal has not been addressed.

4.6.36 Equipment Item No. 87 Temperature Element Scan Model SSl-1 (Licensee reference not c!- d)

The Licensee has provided documentation which shows this equipment to be unqualified in the areas of aging and temperature requirements.

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4.7 NRC Category VI EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED This section includes equipment items which have been addressed by t.*Te Licensee in the equipment environmental qualification submittal but for thich the qualification review has been deferred by the NRC in accordance with criteria presortted in Sections 2.2.3 and 2.2.5 of this report.

4.7.1 Equipment Item No.130 Junction Boxes various Model Numbers (Licensee References 19 and 20)

FRC judges junction boxes to be non-electrical equipment and, hence, chooses not to evaluat.e their longevity or reaction to post-accident environmental conditions in this TER.

4.7.2 Equipment Item No. 135 l

Cable - See Manufacturers List The Licensee has failed to provide documentation that correlates cable type with its respective manufacturer and location to enable a proper evaluation of its environmental qualification.

FRC, therefore, defers qualification until substantive documentation has been provided by TVA.

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CCNCLUSIONS Fac's review of the qualification documentation and other information submitted by the Tennessee Valley Authority for these equipment items and their applications in the Browns Ferry 3 plant has resulted in the following categories:

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NE Compliance With The DOR Quantity Of Category Guideline Requirements Equipment Items I.a Equipment Fully Satisfies All Applicable Requirements for 0

Life of the Plant I.b Equipment Does Not Meet All Applicable Requirements for Life of the Plant However, O

Deviations are Judged Acceptacia II.a Equipment Fully Satisfies All Applicacle Recuirements for Less Then Plant Life 2

II.b Equipment Fully Satisfies All Applicable Requirements Provided That Specific Modifications are Made 0

II.c Equipment for Which the Licensee Has Not Provided Evidence of Full Compli-ance with the Guidelines, but Which is Judged by FE To Be Satisfactory for Less Than Plant Life Based on Total EEQ Program Review 0

III Equipment is Exestpt from Qualification 0

IV.a Equipwnt has Qualification Testing Scheduled 0

IV.b Equipment has High Likelihood of Operability; However, Proper Qualification Documentation is Not Available 73 V

Equipment is Unqualified 58 VI Equipment for which Qualification is Deferred 2

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TER-C5417-6 In general, the major deficiencies that have been identified are shown in the summary review sheets at the end of the section.

The conclusions stated herein represent a summary of the results of the equipment environmental qualification evaluation conducted by FRC in accordance with the methodology presented in Section 3.

.l.,cion results are largely based on the available qualification documentation provided by the Licensee. The results of the review do not necessarily imply that the equipment is unreliable, unsafe, or represents a significant plant safety issues they do imply, however, that qualification documentation is inadequate and that additional infcrmation is required.

The Equipment Environmental Qualification Sammary Form presented on the following pages shows the overall results of the FRC review. The entries on this form delineate the overall status of each specific equipment item with respect to compliance with the Guideline criteria defined in Section 2.0 and the resultant qualification categories defined in Section 3.0.

The following designations are used:

X = A deficiency with respect to compliance with a Guideline requirement. Deficiencies result in equipment items categorized as unquelified or qualification not established.

L = A limiting condition with respect to qualification in that the qualified life has not been established by the Licensee.

O z ;ikC Qualification Category.

l R = Replacement of the equipment by the Licensee is planned.

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TER-C5 417-4 6.

REFERENCES 1.

IPECA S-61-402 Paragraph 3.9 and Appendix D.

2.

TVA Engineering Report No.1943.

3.

Wyle Laboratory Report No. 43854-3.

4.

NUREG-0588 Material List.

5.

TVA Engineering Report No.1946.

6.

TVA Engineering Report No.1944.

7.

Parkinson and sisman, October 1970.

8.

Blodgett and Fisher, June 1968.

9.

Asaka and Yamamoto, 1973.

10.

Anaconda-Continental Test Report No. 79117.

11.

Franklin Institute Test Reports F-C4113 and PC-5120.

12.

Rockbestos Test Report, dated July 1977, amended 1979, 13.

TVA Engineering Report 1942.

14.

TVA Engineering Report 1328.

15.

TVA Engineering Report 1923.

16.

TVA Engineering Report 1945.

17.

TVA Engineering Report 1947.

18.

Franklin Institute Test Report F-C2935.

19.

TVA Engineering Report 1950A.

20.

TVA Engineering Report 1950s.

21.

TVA Engineering Report 1925.

22.

TVA Engineering Report 1926.

23.

TVA Engineering Report 1921.

24.

GE Letter Cated February 3, 1978 to H. J. Green.

25.

Westinghouse letter dated March 9, 1978 to F. W. Chandler.

26.

BWR Owners Group Report 081-A-01 dated September 23, 1980.

2 7. - MIL-C-49142.

28.

GE Report EPAQ-57.

29.

0.E Report EPAQ-60.

4

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TER-C5417-4 30.

GE Report EPAQ-10.

31.

GE Prototype Test Data - Epoxy Life Tests.

32.

ASCO Report No. AQS-21678/TR.

33.

Valcor Doc. No. QR-526 dated February 15, 1979.

34.

Target Rock Report No.1827A dated November 4,1976.

35.

TVA Specification 3350.

36.

NMC Test Report NMC-PT-7630 Rev. O.

37.

NMC Drawing 0082445 Rev. D, February 9, 1978.

38.

Appendix I to Sheet ME3-63-01.

39.

Appendix II to Sheet MEB-64-02.

40.

Appendix II to Sheet MEB-67-01, 41.

Target Rock Test Report 2199A.

42.

ASCO Report AQS-21678/TR.

43.

Fenwal Engineering Report 6350.

44.

Wyle Laboratories Report Q5R018A012.

45.

Barksdale Qualification Procedure 9993.

46.

Lockheed Test Report 3232-3155 dated March 22, 1973.

47.

Barton Engineering Report R3288A-1.

48.

Wyle Summary Report QSR-027-A-02.

49.

Limitorque Test Reports B003, B0027, and No. 600198.

50.

Conax Test Report TR-39 51.

Wyle Summary Report QSR-146-A-01 g;

52.

Acme Cleveland Devel Co. Test Report, dated 2/20/78 53.

Barton Engineering Report R3-288A-1 54.

Wyle Summary Report QSR-029-A-01 55.

Wyle Summary Reports 312-3 and E12-N010 56.

Rosemount Test Reports 37327B and 127227 57.

Wyle Report QSR-048-A-01 58.

Viking Lab Report 30203-2 59.

Louis Allis Document S40EJ4-099-630 of 10/10/79 60.

TVA Engineering Report 1927 61.

Wyle Lab Report QSR-002-A-02 62.

Franklin Institute F-C2815 Final Report l

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TER-C5417-4 63.

Rotock Report, "A" Range Nuclear Qualification 64.

Letter from G. Lainas, NRC, to A. Schwencer, NRC.

Subjects Electrical Equipment Environmental Qualification, dated February 19, 1980.

65.

Letter 2 rom Norman C. Moseley, NRC, to B. H. Grier, J. P.

O'Reilly, J. G. Keppler, K. V. Sezfrit, R. H. Engelken, NRC.

Subject:

IE Supplement No. 2 to Bulletin 79-013, Environmental Qualification of Class 12 Equipment, dated September 29, 1980.

66.

Letter from Norman C. Moseley, NRC, to S. H. Grier, J. P.

O' Reilly, J. G. Keppler, K.V. Sezfrit, R. H. Engelken, NRC.

Subject:

IE Supplement No. 3 to Bulletin 79-013, Environmental Qualification of Class lE Equipment, dared October 24, 1980.

67.

U.S. NRC Memorandum and Order (CLI-80-21) pursuant to the Petition for Emergency and Remedial Relief filed with the NRC on November 4, 1977.

68.

TVA response to NRC IE Bulletin 79-013 Environmental Qualification of Class LE Equipment for Browns Ferry 1, 2, and 3, dated October 31, 1980.

69.

NUREG 0588.

4 6-3

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TER-CS417-6 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS This appendix contains temperature / pressure profiles or tables referenced by the Licensee in the " Environment Specifications" column on the EWS.

Three tables in this appendix are used to locate the appropriate figure or table which defines the temperature / pressure values for each room. The temperatures / pressures given in either figures or tables are assumed to linearly return to ambient in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The three tables are as follows:

e Table 3.0 (1,2,3), Room Number, Name, and Plant Location This tacle relates the room number to a room name and to a specific plant location (See plant arrangement drawings, sheets 1-6 for plant locatieas).

See pages A-2 through A-9.

e Table 3.00 (1,2,3) - Environmental Temperature / Pressure i

curves - Room Number Designation t

l This table relates various room numbers to figures or Table B.1 j

(1,2,3) which are in this appendix for temperature and pressure.

See pages A-10, A-11, and A-19 through A-53.

e Table B.1 (1,2,3) - Temperature / Pressure (Selected Areas)

This table gives selected temperature / pressure values for selected areas that are not contained in a profile.

l See pages A-12 through A-lS.

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TER-C5417-6 TABLE t.0 (1.2,35 acom WP. Name. and Plant '.ocation 81 ant Location' acom %.

Room W___

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I l l I TER-C5417-6 j l l With respect to environmental service conditions, the Licensee has stated: A. Service Conditions The environmental conditions present in plant areas that can affect safety-related equipment have been established. The following categories were used to bound anticipated plant conditions.

1. Normal - The temperature, pressure, humidity, and radiation ranges that are expected to be present when the plant is in any of the technical specification modes of operation.

2. Abnormal-Conditions that could exist for all areas for a short period of time that may occur once or more a year.

3. Accident-Environmental conditions that would be experienced as a result of high energy pipe breaks outside containment, or a large, intermediate or small LOCA or main stream line break inside containment.

All analyses performed to determine the service conditions were performed consistent with tne guidelines of IE Bulletin 79-013 and NUREG-0588 and in accordance with either TVA quality assurance I procedure EP 3.03 or General Electric's internal quality assurance program. B. Temperature and Pressure Inside Containment The controlling breaks for the pressure response of the drywell and wetwell and the temperature response of the wetwell are the large LOCA Design Basis Accident (DBA) and the Intermediate Break Accident (IDA). The DBA and a 0.5 ft2 steam leak produce the most severe temperature transient in the drywell. The containment pressure and temperature response for all breaks were evaluated by the methods discussed in General Electric Report No. NEDO-20533, June 1974. Mass i and energy releases were calculated using the methods also discussed in the above General Electric report. Details of the analyses are i provided in FSAR, section 14 and General Electric Report NEDO-24580. i l l l A UEnklin Research Center A-54 l a Nea w N r a -en

l TER-C5417-6 C. Outside Containment High Energy Line Breaks Plant areas outside containment were reviewed to determine areas where high energy piping was located and could potentially produce effects that would impact safety-related l equipment. The areas affected by high energy line breaks are l the reactor building and the main steam valve vaults. 1. Reactor Building The high energy lines located in the reactor building ares l (1) High Pressure Coolant Injection (HPCI) steam supply l to the pump turbine - 547'F, 1020 psia, quality - 1. I (2) Reactor Core Isolatien Cooling (RCIC) supply to the RCIC pump turbine - 547'F, 1020 psis, quality - 1. (3) Reactor Water Cleanup (RECU) system - 547*F, 1020 psia, quality - 0. Single-ended circumferential ruptures at the fluid conditions listed above were postulated. Mass and energy releases for all steam supply lines except one break of the RWCU were generated using the.%>dy critical flow correlation assuming an fL/D equal to zero. Upstream pressure and temperature, and therefore mass flow rates, were assumed to remain constant until the line was isolated. These steam supply lines isolate automatically on high temperature in the reactor building. Temperature sensors are located in the vicinity of the line to assure rapid detection and isolation. Isolation times include signal process time, valve stroke time, and break detection time. The sensors used are redundant, class lE, and electrically trained. l Mass and energy release of the remaining RWCU break was l generated using the RETRAN computer code. Only this break requires operator action for isolation. Isolation was assumed to occur 10 minutes af ter the break is. Detection based on high fluid temperature at the discharge of the nonregenerative heat exchangers. I L-The steam valve vault was modeled using three nodes and were input into the COMPARE-MODI computer code. No heat sinks were considered. l h d --2 A-55 i //.) Franklin Researc.h Center ac awwr

TER-C5417-6 The valve vaults at Browns Ferry were constructed with large blowout panels to provide pressure relief to the turbine building in the event of a pipe break. These paths were included in the model. 2. Radiation Environment The radiation environments inside the drywell and in the reactor building after a design basis LOCA were calculated consistent with the requirements of IE Sulletin 79-01B and NUREG-0588. Initial airborne sources in the drywell were calculated assuming an instantaneous release of 100 percent of the core inventory of iodine. Transfer of iodine from the drywell free volume to the water in the torus was conservatively calculated as a function of time until the airborne concentration was reduced by a factor of 200 (considered to be at equilibrium). Sources in the water in the torus were calculated assuming an instantaneous release of 1 percent of the core inventory of the solid fission products and the iodine transferred from the drywell. Airborne activity in the reactor building was calculated based on a design basis leak rate from the primary containment and design flow of the SG7s. Source terms were calculated at various time after an accident allowing for decay and dose rates were calculated with a point-kernel-with-buildup computer code. Radiation exposures in the reactor building due to recirculation of the torus water through the RHR and containment spray systems were also calculated. These dose rates were then integrated over the duration of the accident. 3. Main Steam Valve Vaults The high energy lines in the valve vaults are the main steam lines and the main fr.edwater lines. Breaks in the main steam line are controlled from an environmental standpoint due to the large line size and the high energy associated with the steam. Conditions of the main steam are 550'F, 1050 psia, quality - 1. A double-ended rupture of the main steam coincident with a break of the 4-inch RCIC stoam line was evaluated. Mass and energy releases were provided by General Electric. 3reak flow was terminated by isolation of the main steca lines based on signals from safety-related sensors. a 4-J:: 6 i .a.J Frankl% Research Center A-56

• oa a w n. r in

TER-C5 417-6 4. Operation Environmental Conditions An environmental listing of service conditions are tabulated in Table 1. The service conditions considered were pressure, temperature, humidity, and radiation. Normal and abnormal space ambient temperatures for l nonaccident conditions were obtained from information l used in the initial design phase of the plant in l conjunction with data accumulated at the plant site in various spaces, for all units, under extreme outside temperature conditions (100*F outside atmosphere). Pressures and temperatures for accident conditions were obtained from transient curves and analysis which studied the effects of a LOCA on reactor zone spaces. l Environmental service and conditions were only considered in the reactor zone and primary containment. The control bay and electrical board room were not considered since their atmospheres did not interface with the reactor zone environment. The environmental table of service conditions was developed for various plant conditions including the following: normal average day, abnormal conditions (outside temperature 96-100* and maximum river water temperature exists), LOCA/HEL3 inside primary containment, HELB outside primary contaiment. and tornado (sudden pressure drop by 3 pounds per square inch). I i l l l l l l ( <<fse + A-57 .a.. FranMn Resear.ch Center = cm on s w=. a -

TER-C5417-6 APPENDIX B - EQUIPMENT ITEM TABLE This appendix contains the list of safety-related electrical items for Browns Ferry Nuclear Plant Unit 3 provided by the Licensee in the October 31 response to IE Bulletin 79-013. This listing shows the equi ment items by manufacturer and model number, plant locations, and time required to function as determined by the Licensee. l l [ i 1 l l i 6 8-h- . J.' Franklin Research C. enter 3-1 . a w a# w a

TER-C5417-6 PLANT NAME: BRCWNS FERRY 3 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATICN NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 1 Solenoid Valve 8 EEB-32-1001 None AAA 8 EES-32-1002 None SO2 2 F' Indicating Switch 12 EEB-43-1001 None Fischer & Porter 12 EEB-43-1002 None 10A2235A-55AR10ll 3 Differential Pressure 14 EEB-64-1001 None Switch 14 EEB-64-1002 None Dwyer 14 EEB-64-1003 None 3302 14 EEB-64-1004 None 14 EEB-64-1005 None 15 EEB-64-1006 None 15 EES-64-1007 None 15 EEB-64-1008 None 15 EEB-64-1009 None 15 EEB-64-1010 None 15 EEB-64-10ll None 15 EEB-64-1012 None 14 EEB-64-1026 None 14 EEB-64-1041 None 15 EEB-64-1042 None 4 Solenoid valve 15 EEB-64-1013 None ASCO 15 EEB-64-1023 None HB830281RU 12 EEB-64-1024 None 14 EEB-64-1025 None 14 EEB-64-1028 None 5 Differential Pressure 14 EEB-64-1014 None Modifier 15 EEB-64-1015 None Honeywell 15 EEB-64-1038 None R7165-1078 Relay Assa. 122700 Terminal Assm. 6 Differential Pressure 14 EEB-64-1016 None Indicator Controller 15 EEB-64-1017 None Fischer & Porter 15 EEB-64-1018 None 53EL3311BBlB ESL-01 b B-2 /.d Franklin Research C. enter 4cammasNr

e TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 7 Differential Pressure 14 EEB-64-1019 None Transmitter 15 EEB-64-1020 None Fischer & Porter 15 EEB-64-1021 None 10B2494TSAB 8 Solenoid Valve 8 EEB-64-1022 None ASCO 8 EEB-64-1034 None EV200-924-2 8 EEB-64-1035 None 9 Terperature Element 6 EEB-64-1027 None Weed SP60llAA3C2755N42 10 Temperature Element 0 EEB-64-1039 None Weed 0 EEB-64-1040 None SP60llAA3C2755N42 11 Solenoid valve 13 EEB-64-1029 None ASCO 13 EEB-64-1030 None HB830081RU 15 EEB-64-1031 None 15 EEB-64-1032 None 12 Flow Transmitter 14 EEB-65-1001 None GE/MAC 50-554212BKZZ3 13 Solenoid valve 8 EEB-67-1001 None ASCO 9 EEB-67-1002 None HT8262A203A 9 EEB-67-1003 None 14 Pressure Transmitter 9 EEB-67-1007 None Bailey 8 EEB-67-1008 None 551 l 15 Flow Transmitter 12 EEB-04-1007 None GE/MAC 12 EEB-84-1008 None 555 l 16 Temperature Switch 12 EEB-69-1001 None l Fenwal 12 EEB-69-1002 None 18002-27 12 EEB-69-1003 None 12 EEB-69-1004 None 16 EEB-69-1005 None 16 EEB-69-1006 None 16 EEB-69-1007 None 16 EEB-69-1008 None W% B-3 4.;; Franklin Researc,h C. enter % e n r=w.

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 17 Solenoid valve 3 EEB-71-1001 None ASCO 3 EEB-71-1002 None HTX83008610 18 Solenoid valve 6 EEB-74-1001 None ASCO 6 EEB-74-1002 None 8300C61U 6 EEB-74-1003 None 6 EEB-74-1004 None 4 EEB-77-1006 None 19 Solenoid valve 3 EEB-75-1002 None ASCO 3 EEB-75-1004

one HB830081F 20 Solenoid Valve 12 NEB-64-49A None

~ ASCO HB830081F 21 Solenoid valve 8 NEB-64-053A 32 ASCO HB830081F 22 Solenoid Valve 6 EEB-76-1001 33 Valcor 6 EEB-76-1002 33 526D 6 EEB-76-1003 33 6 EEB-76-1004 33 6 EEB-76-1005 33 6 EEB-76-1006 33 6 EEB-76-1007 33 6 EEB-76-1012 33 6 EEB-76-1013 33 23 Solenoid Valve O EEB-76-1008 33 Valcoe O EEB-76-1009 33 5260 0 EEB-76-1010 33 0 EEB-76-10ll 33 24 Solenoid Valve 8 EEB-84-1001 34 Target Rock 8 EEB-84-1002 34 73FF-005 8 EEB-84-1003 34 8 EES-84-1013 34 25 Solenoid valve 12 EEB-84-1005 None ASCO 12 EEB-84-1006 None HT8211C94

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TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 26 Indicator Pressure 12 EEB-84-1009 None Converter 12 EEB-84-1010 None Fisher Controls 546 27 Pressure Switch 12 EEB-84-10ll None Custom Components 12 EEB-8 4-1012 None 630GH 28 Assembly 9, R20,5 EEB-90-0003 35, 36, 37 Nuclear Measurements 8,R18,0 EEB-90-0006 35, 36, 37 Corp. 8,R19,U EEB-90-0009 35, 36, 37 29 Thermostat 14 MEB-63-01 38 1 Honeywell T675A1506 30 Damper Motor 0,6,8,15 MEB-64-01 None Honeywell '~ M445A 31 Thermostat 2,3,4,5 MEB-64-02 39 Honeywell T675A1540 + i ~ 32 Motor-operated valve 9 MEB-67-01 40 Limitorque 7 NEB-1-013 40 SMB-000 8 NEB-23-029 40 33 Motor-Operated Valve O MEB-67-02 40 Limitorque 0 NEB-1-012 40 SMB-000 34 Motor-operated valve 6 MEB-71-01 40 Limitorque 6 MEB-73-01 40 SMB-000 35 Motor-operated valve 1 MEB-73-02 40 Limitorque 2 MEB-74-01 40 SMB-000 3 MEB-71-02 40 36 Motor 3 MEB-77-02 None GE 3 MEB-77-03 None SK4254XL2 l N MU Franklin Research Center B-5 a c== a en N % m-u. 4-r ,_' -- -'~

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 37 Motor 2 MEB-77-05 None GE 5 MEB-77-07 None 5K6226XJ201A 38 Motor-Operated Valve 12,13 MEB-78-01 None Rotork 14A 39 Pressure Solenoid 0 NEB-1-002 41 Operator Target Rock 1/2 SMS-A-01 40 2: essure Solenoid 0 NEB-1-002A 42 Operator 0 NEB-43-030 42 ASCO WPHTX8300868F 41 Differential Pressure 4 NEB-1-003 None Switch Indicator harton 278 42 Solenoid Operator 0 NES-1-005 None Automatic Valve Corp. C-5497 43 Solenoid Operator 7 NEB-1-007 None Automatic valve Corp. C-5497 44 Temperature Switch 7 NEB-1-008 43 Fenwal 17002-40 l 45 Temperature Switch 11 NEB-69-81 43 Fenwal 17002-40 46 Pressure Switch 9 NEB-3-015 44, 45 Barksdale 9 NEB-3-018 44, 45 l B2T-Al2SS 9 NES-3-021 44, 45 6 4 ..M Frankhn Research Center 3-6 <matmvm m

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITIAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 47 Pressure Switch 2 NEB-71-84 44, 45 Barksdale 2 NEB-73-128 44, 45 B2T-A12SS 48 Level Indicator 9 NEB-3-016 46 Switch 9 NEB-3-017 46 Yarway 9 NEB-3-019 46 4418C 9 NEB-3-022 46 9 NES-3-021 46 49 Pressure Switen 9 NEB-3-021A 47, 48 Barton 3 NEB-75-226 47, 48 288 50 Pressure Switch 4 NE3-68-72A 47, 48 Barton 2 NEB-71-a3 47, 48 288 51 Level Indicator 9 NEB-3-023 47, 48 Switch Barton 288A 52 Level Indicator 2 NEB-73-129 47, 48 Switch Barton 288A 53 Temperature Element 8 NEB-23-025 None Calmatic 8 NEB-23-027 None 158B706 LP016 8 NEB-74-209 None 54 Motor-Cperated valve 8 NES-23-026 49 j Limitorque 9 NEB-74-205 49 SMB-2 9 NEB-75-222 49 9 NEB-75-224 49 9 NEB-74-196 49 i -~ 8 NEB-74-196A 49 I 8 NEB-74-197 49 9 NEB-74-197A 49 9 NEB-75-235 49 s NEB-75-237 49 NEB-74-206 49 55 Motor-operated '7. ;:N NEB-68-069 49 v NEB-73-130 49 Limitorque SMB-2 dd$$Es r..) Franklin Research Center B-7 % w ww - --a

TER-C5 417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCFS 56 Motor-Operated Valve 1 NEB-73-149 49 Limitorque 3 NEB-75-217 49 SMB-2 4 NEB-75-234 49 57 Motor-operated Valve i NES-73-168B 49 Limitorque 6 NEB-73-147 49 SMB-2 6 NEB-74-204 49 6 NES-74-193 49 6 NEB-74-195 49 58 Flow Transmitters 8 NES-23-028 None GE 50-555111BOAA3AAA 59 Flow Transmitters 3 NEB-71-ll6 None GE 3 NES-75-220 None 50-55511130AA3AAA 1 NEB-73-165 Ncne 2 NEB-74-189 None 2 NEB-74-190A None 4 NEB-75-223 None 5 NEB-74-199 None 5 NEB-74-203 None 60 Motor-operated Valve 8 JEB-20-029 49 Limitorque 6 NEB-70-82 49 SMB-00 7 N1'.B-71-9 6 49 12 NEB-74-207 49 6 NEB-74-194 49 61 Motor-operated valve O NEB-71-85 49 Limitorque O NES-74-208 49 SMB-00 62 Motor-operated Valve 3 NEB-71-107 49 Limitorque 3 NEB-71-108 49 SMB-00 3 NEB-71-109 49 4 NEB-74-230 49 63 Solenoid Valve O NEB-43-030 42 + ASCO WPHTX8300B68F 64 Limit Switch 0 NEB-43-031 None Micro Switch 0 NEB-43-033 None OPD-AR CPD-AR30 6 de 3~0 i..d F.nklin Research C. enter om.on w ni. r,-ma m.

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATICN NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 65 Solenoid valve 12 NEB-43-032 42 ASCO X8300-B61F 66 Temperature Switch 14 NEB-63-034 None Fenwal 40-104014-103 67 Temperature Element 14 NEB-63-035 None Fenwal 28-232106-304 68 Pump Motor 14 NEB-63-037 None GE SK326PK-234A 69 Explosive 'ialve 14 NES-63-038 50, 51 Conax 1832-117 70 Solenoid Valve 8 NEB-64-039 42 ASCO 8 NEB-64-040 42 WPHTX8300B45F,R 12 NEB-64-047 42 8 NEB-64-053 42 8 NES-76-242 42 71 Limit Switch 0 EEB-1-1007 52 NAMCO O EEB-1-1009 52 l EA740-50100 0 EEB-1-1004 52 0 EEB-1-1005 52 72 Limit Switch 7 EEB-1-1008 52 NAMCO 7 EEB-1-1010 52 EA740-50100 7 EEB-1-1003 52 l 7 EEB-1-1006 52 l 73 Limit Switch 12 NEB-64-052 None NAMCO 8 NEB-64-054 None D1200G 8 NEB-64-056 None 8 Nc3-64-056A None l 8 NEB-76-239 None l 8 NEB-64-041 None 8 NEB-64-043 None 8 NEB-64-045 None 12 NEB-64-048 None l l 6

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TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 73 (Cont.) 8 NEB 0 50 None 8 NEB-76-239A None 8 NEB-76-239B None 8 NEB-76-239C None 8 NEB-85-268A None 74 Pressure Switch 8 NEB-64-046 53, 54, 55 Barton 289 75 Pressure Switch 3 NEB-71-115 53, 54, 55 Barton 1 NEB-73-164 53, 54, 55 239 1 NEB-74-188 53, 54, 55 3 NES-75-219 53, 54, 55 76 Pressure Transmitter 9 NEB-64-058 None GE/MAC 6 NEB-64-059 None 551032CAAEl 9 NEB-64-06J None 552032KAATl 3 NEB-71-097 None 556220BAAAJ 3 NEB-71-105 None 50-551032EAAsl 3 NES-71-110 None 50-551032GAAA1 2 NEB-73-157 None 50-551032CAAY1 1 NEB-73-163 None 50-551032EAAK1 2 NEB-74-190 None 50-551032GAAN1 5 NEB-74-200 None 6 NEB ~/4-210 None 77 Power Supply 12 NEB-64-060 None GE, 12 NEB-71-098 None Sa3001AAGK1 570012FAACl 78 Level Transmitter 6 NEB-64-061 56, 57 Rosemount 6 NEB-64-067 56, 57 1151 Series 79 Temperature Element 6 NEB-64-062 None American Standard 6 NEB-64-063 None 158B7079P051 80 Pressure Switch 9 NEB-64-064 58 Static-O-Ring 9 NEB-64-065 58 12N/AA4 9 NEB-64-066 58 81 Motor-Cperated Valve O NES-69-070 49 Limitorque O NEB-74-186 49 SMB-3 6 e dTf2Ed a ..d Franklin Research Center B-70 4 cm on m N r mma m.

TER.-C 5 417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMI' ITAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 1 82 Motor-Operated Valve O NEB-69-73 49 Limitorque SMB-0 83 Motor-operated Valve 11 NEB-69-74 49 Limitorque SMB-0 84 Motor-Cperated */alve 3 NEB-71-100 49 Limitorque 5 NEB-73-160A 49 SMB-0 2 NEB-74-179A 49 1 NEB-73-169 49 3 NEB-75-214 49 1 NEB-73-161 49 4 NEB-75-227 49 85 Temperature Element 2 NEB-74-213 None Scam 5 NEB-74-213A None S51-1 1 NEB-73-174 None' 3 NEB-71-120 None 86 Temperature Element 8 NEB-74-213B None Scam 12 NEB-74-213C None S51-1 f.7A NES-69-76 None i TB NEB-69-77 None 18 NEB-69-78 None 11 NEB-69-79 None 10 NEB-69-80 None 8 NEB-74-181 None 87 Temperature Element 6 NEB-74-213D None i scam 6 NEB-71-121 None SSl-1 6 NEB-73-175 None 88 Temperature Switch 3 NEB-71-089 3, 43 Fenwal 1 NEB-11-089A 3, 43 17023-6 1 NEB-73-131 3, 4.i 1 NEB-73-13 2 3, 43 1 NEB-73-136 3, 43 89 Temperature Switch 6 NES-71-090 3, 43 Fenwal 6 NEB-73-135 3, 43 17023-6 6 NF.B-73-141 3, 43 6 NEB-73-142 3, 43 l ?-B- .'.: Franklin Research Center B-ll s w w wm muna.

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 90 Valve 3 NEB-71-101 None Terry Turbines 3 NEB-71-102 None Type GS 3 NEB-71-103 None 3 NEB-71-122 None 3 NEB-71-123 None J NEB-71-124 None 3 NEB-71-125 None 91 Pressure Switch 3 NEB-71-104 44, 45 Barksdale PIH-M8"SSV 92 Pressure Switch 3 NEB-71-104 None Mercoid 1 NEB-73-158 None DA-7043-804 3 NEB-75-216 None DA-23-804 4 NEB-75-229 None 93 Pressure Switch 3 NEB-71-il2 58 Static-O-Ring i NEB-73-162 58 6N-AA21-V 6N-AA21 94 Square Root 12 NES-71-ll4 None Converter GE 565100AAACl 95 Motor-operated valve 3 NEB-71-117 49 Limitorque 3 NEB-71-ll8 49 SMB-1 3 NEB-71-119 49 3 NEB-75-221 49 2 NEB-74-179 49 96 Turbine Controls 1 NEB-73-148 None Terry Turbines 1 NEB-73-154 None Type CCS 1 NEB-73-151 None 1 NZB-73-155 None 1 NES-73-171 None 1 NEB-73-172 None 1 NEB-73-173 None 1 NEB-73-173A None 97 Pressure Switch 1 NEB-73-156 44, 45 Sarksdale D2H-M150SS 6 W-h~ /.3 Franklin Research Center B-12 = w wn.r -

~ TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 98 Motor-Operated Valve 1 NEB-73-167 49 Limitorque 1 NEB-73-166 49 SMB-4T 1 NEB-73-170 49 99 Level Switch 6 NEB-73-176 None Robertshaw SL-202-A2X 100 Pressure Switch 2 NEB-73-180 58 i Static-O-Ring 2 NEB-73-180A 58 SN-AA3 5 NEB-73-184 58 5 NED-73-184A 58 101 Motor-operated valve O NEB-74-191 49 Li:nitorque SMB-5T 102 Motor-operated valve 9 NEB-74-192 49 Limitorque r i SMB-4 103 Motor-operated valve O NEB-74-202 49 Limitorque SMB-4 104 Differential Pressure 4 NEB-74-198 48, 53 Switch Indicator l Barton 289A 105 Pump Motor 5 NEB-74-211 None GE 2 NEB-74-212 None 5K6348XC23A 106 Flow Switch 4 NEB-75-232 53, 54 Barton ~ 289 107 Pump Motor 4 NEB-75-238 None GE 3 NEB-75-238A None SK336XC198A 108 Solenoid Valve 8 NEB-76-240 42 ASCO 8 NEB-76-241 42 X8315 t

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TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 109 Hydrogen Element 0 NEB-76-?43 None GE 47E226428G2 110 Level Switch 0 NEB-77-244 None GEMS XM-36425 111 Solenoid Valve 6 NEB-77-249 None Versa VSG-3521 112 Limit Switch 6 NEB-77-249A None Micro Switch 6 NEB-77-249B None BZE6-2RN 113 Level Switch 2 NEB-77-250 None Autocon 5 NEB-77-251 None M-4 4 NEB-77-260 None 4 NEB-77-261 None 114 Temperature Element 0 NEB-77-252 None Thermo-Plect 4 NEB-77-259 None B7582-1 115 Level Switch 13 NEB-78-262 None Meletron 9241-6SS10A 116 Level Switch 13 NEB-78-265 44, 45 Barksdale D2H-M18SS 117 Solenoid valve 8 NEB-85-267 None ASCO 8 NEB-85-268 None HVA86-030 118 Position Switch 8 NEB-85-272 None Micro Switch 8 NEB-85-273 None BZE6-2RN 119 Solenoid Valve 8 NEB-85-274 None ASCO HVA-90-405-2A 44 a MJ Franklin Researen Center B-14 4 % e w= ., ~ -,. - ~

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 120 Level Switch 8 NEB-85-276 None Robertshaw SL-305-E3-X 121 Ion Chamber 7 NEB-90-279 None GE 7 NEB-90-280 None 237X731G001 7 NEB-90-281 None 7 NEB-90-282 None 122 Sensor and Converter 15 NES-90-283 None GE 15 NEB-90-284 Ncne 194X927G014,12 123 Fission Product 0 NEB-90-286 None Monitor 6 NEB-90-286A None GE No Model No. 124 TIP Valve Assembly 8 NEB-NM-287 None GE 136B1302G2 125 Transformer 12 EEB-APS-0001 None GE 12 EEB-APS-0002 None llCH2L4 13 EEB-APS-0003 None 126 Motor Control Center 9 EEB-APS-0005 None International Switch-12 EES-APS-0006 None board Corp. 127 Motor Control Center 8 EEB-APS-0004 None GE 7700 Series 128 Motor Generator 12 EEB-APS-0199 59 Louis Allis Co. 12 EEB-APS-0200 59 8-127033 12 EEB-APS-0201 59 12 EEB-APS-0202 53 129 solenoid valve O EEB-1-1001 None Target Rocic 0 EEB-1-1002 None 1/2 SMS-A-01-1 13 0 Junction Box Various Numerous 19, 20 l l Mh E .L..Enidin Research C. enter B-15 l

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TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 131 Terminal Block 4 EEB-77-0066 24, 25, 26 GE 15 EEB-78-0062 24, 25, 26 EB-5 and CR15182 0 EEB-84-0058 24, 25, 26 0 EEB-84-0061 24, 25, 26 12 EEB-63-0069 24, 25, 26 Various EEB-64-0068 24, 25, 26 6 EEB-76-0079 24, 25, 26 8 EEB-90-0158 24, 25, 26 9 EES-67-0044 24, 25, 26 O EEB-01-010 5 24, 25, 26 i 13 1 (Cont.) 7 EEB-01-0106 24, 25, 26 8 EEB-23-0039 24, 25, 26 12 EEB-43-0027 24, 25, 26 0 EEB-43-0028 24, 25, 26 12 EEB-43-0029 24, 25, 26 0 EEB-32-0015 24, 25, 26 0 EEB-74-0395 24, 25, 26 Various EEB-74-0396 24, 25, 26 Various EEB-73-0129 24, 25, 26 various EEB-75-0147 24, 25, 26 Various EEB-69-0106 24, 25, 26 Various EEB-71-0252 24, 25, 26 13 2 Electrical Penetration 0 EEB-NM-0025 15 Assemblies O EEB-NM-0026 15 GE O EEB-NM-0027 15 NSO4 0 EEB-NM-0028 15 0 EEB-NM-0029 15 0 EEB-NM-0030 15 0 EEB-NM-0031 15 0 EEB-NM-0032 15 0 EEB-NM-0033 15 0 EEB-64-0014 23 0 EEB-64-0015 23 6 EEB-76-0067 23 6 EEB-76-0068 23 6 EEB-76-0069 23 6 EEB-76-0070 23 6 EES-76-0071 23 0 EEB-68-0036 23 0 EEB-68-0037 23 0 EEB-68-0038 23 0 EEB-68-0039 23 0 EEB-69-0092 23 0 EEB-69-0093 23 0 EEB-01-0095 23 4k hbEnklin Research Center B-16 4 w.o. at Th nm n -

TER-C5417-6 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 13 2 (Cont.) O EEB-01-0096 23 0 EEB-01-0097 23 0 EEB-01-0098 23 0 EEB-01-0099 23 13 3 Electrical Penetration 0 EES-76-0072 22 Assembly GE Series 100 134 Switches 4 EEB-77-0069 61 GE and Cutler Hammer 0 EEB-74-0402 61 GE-CR2940 8 EEB-23-0042 61 CH-10250T 7 EEB-01-0109 61 Various EEB-75-0150 61 Various EEB-73-0138 61 Various EEB-74-0339 61 11 EEB-69-0110 61 Various EEB-71-0255 61 13 5 Cable (See Various Numerous Manufacturers List) l l l l i

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l l TER-C5417-6 .~ APPENDIX C - SAFETY SYSTEMS MR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED The Licensee has submitted a list of safety-related systems that must l function in order to mitigate the consequences of a design basis accident. This information was submitted in response to IE Bulletin 79-01B and was included in the Licensee's October 31 response. l 6 C-1 a .G" Franklin Research Center a w w w e men = ar--e-w--w w y --i-- 9 yn- .w, ,y

TER-CS417-6 e Main Steam o Feedwater e Fuel Oil e Residual Heat Removal Service Water e Raw Cooling Water e Ventilating e Air Conditioning e Control Air e Sampling e Standby Liquid Control e Primary Containment e Standby Gas Treat:nent e Emergency Equipment Cooling Water e Reactor Recirculation e Reactor Water Cleanup e Reactor Building Closed Cooling Water e Reactor Core Isolation Cooling e High Pressure Coolant Injection e Residual Heat Removal e Core Spray e Containment Inerting e Radwaste i e Fuel Pool Cooling e Containment Atmosphere Dilution e Control Rod Drive e Neutron Monitoring e Radiation Monitoring e Auxiliary Power 1 6 C-2 46 Franxiin Research Center

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TER-C5417-6 APPENDIX D - CABLE MANUFACTURERS LIST 1. Brand-Rex 1. Rome Cable 3. Cyprus 4. American Insulated Wire 5. Plastic Wire & Cable Corp. 6. General Ca.?ls 7. Continenta:. Wire & Cable 8. PWC 9. Tamaqua 10. Boston Insulated Wire 11. Okonite 12. Rockbestos 13. Belden Corp. 14. ITT Surp. 15. Sumitomo Shoji 16. Essex 17. Phelps Dodge 18. Triangle Conduit a Cable 19. GE Cable Corp. 20. Sies Electric 21. Graybar 22. Simplex Wire & Cable 23. Times Wire & Cable 24. Dearborn Wire 25. Alpha Wire Corp 26. Belden 27. Consolidated Wire 28. Anaconda 29. Collyer Insulated Wire ] 6 Mr=h ..tJ Franklin Research Center D-1

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TER-C5417-6 APPENDIX E - EQUIPMENT ITEM CROSS-REFERENCE LIST FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM SECTION 1 4.5.2.1 2 4.5.2.2 3 4.5.2.3 4 4.5.2.4 5 4.5.2.5 6 4.5.2.6 7 4.5.2.7 8 4.5.2.8 9 4.5.2.9 10 4.5.2.9 11 4.5.2.8 12 4.5.2.10 13 4.5.2.8 14 4.5.2.11 15 4.5.2.12 16 4.5.2.13 17 4.5.2.14 18 4.5.2.15 19 4.6.1 20 4.6.1 21 4.6.1 22 4.5.2.62 23 4.5.2.62 24 4.3.1.1 25 4.5.2.16 26 4.5.2.17 27 4.5.2.18 28 4.6.2 29 4.5.2.19 30 4.5.2.20 31 4.5.2.19 32 4.5.2.58 33 4.6.3 34 4.6.3 35 4.6.3 36 4.5.2.21 37 4.5.2.21 38 4.6.30 39 4.6.4 40 4.6.31 41 4.5.2.61 42 4.6.31

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TER-C5417-6 j FINAL TECHNICAL l EQUIPMENT EVALUATION REPORT ITEM SECTION 43 4.5.2.60 44 4.6.5 45 4.6.5 46 4.6.6 47 4.6.6 48 4.5.2.22 49 4.6.7 50 4.6.7 51 4.6.8 52 4.6.8 53 4.5.2.23 54 4.6.10 55 4.6.9 56 4.6.9 57 4.6.10 58 4.5.2.24 59 4.5.2.24 60 4.6.10 61 4.6.9 62 4.6.9 63 4.6.31 64 4.5.2.25 65 4.6.11 66 4.5.2.26 67 4.5.2.27 68 4.5.2.59 69 4.6.33 70 4.6.12 71 4.6.35 72 4.6.35 73 4.5.2.28 74 4.6.32 75 4.6.13 76 4.5.2.29 77 4.5.2.30 78 4.6.14 79 4.5.2.31 30 4.6.34 81 4.6.9 82 4.6.9 83 4.6.9 84 4.6.9 85 4.5.2.32 36 4.5.2.32 87 4.6.36 88 4.6.15 6 ad%$Em 6 E-2 $3J Franklin Research.C.e.nter

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