ML20004D222
| ML20004D222 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/31/1981 |
| From: | Crane C FRANKLIN INSTITUTE |
| To: | |
| Shared Package | |
| ML18025B526 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, TER-C5417-005, TER-C5417-005-DRFT, TER-C5417-5, TER-C5417-5-DRFT, NUDOCS 8106090014 | |
| Download: ML20004D222 (130) | |
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9 TECHNICAL EVALU ATION REPORT FIN AL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION l TMESSEE VALLEf AUTrCRITY l EPCMS FEFRY NLO.BR FCk8 STATICN LNIT 2 l NRC CCCXET NO. 50-260 NPC TAC NO. 42482 FPC PCCJECT C5417 l EG&G ICAMC, NC. SUBCCNTRACT NC. M515 FPC TASK 3 Prepared by Franklin Research Center The Parkway at Twentisth Street Philadelphia, PA 19103 FRC Group Leader: C. J. Crane t Prepared for EG &G Idaho, Inc. Idaho Falls, Idaho 83401 January 31.1981 This recert was crepared as an account of work ::erd ermec under a succontract from EG&G Icanc. Inc.. a pr:me centracter to the Unitec States Cecartment of Energy. Neitner EGlG ncr the Unitec States Government nor any agency thereof er any cf their emcicyees. l makes any narrr.nty, excressec or imcliec. cr assumes any :egai hacility or rescens.tihty for any tnirc carty's use. or the results of such use. cr any :nformat:en accaratus. ;reduct oc crccoas cisc:csec in tnis recort, er recresents tnat its use cy sucn inerc :: arty wouic not intnnge pnvately owned rignts. l l NOTE - THIS IS A ORAFT l Secause of senecule limitations. this recert craft nas not gone througn the ccmciete review cycle of FRC. While tne overall conclus:cn is expected tc remain the same. the reader is cautioned that scme cetails of the recert may change as the review is ccmcleted. I THIS DOCUMENT CONTA!NS 4 POOR QUALITY PAGES ..?_ Franklin Research Center A Division of i ne rranxan instrute
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a . 4 TECHNICAL EVALUATION REPORT FIN AL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION TSESSE VALLcY AUTICRITY EFL%S FEMY NLCLM EE STATICN LNIT 2 NRC CCCKET NO. 50-260 NRC TAC NO. 42132 FRC P ACJECT C5117 EG&G iC AHO. iNC. SU SCCNTRACT NO. 67515 FFC TASX 5 Prepared by Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 FRC Group Leader: C. J/ Crane Prepared for ! EG &G Idaho, Inc. Idaho Falls, Idaho 83401 l January 31.1981 This rescrt uas precare. 1 an acccunt of acrk per'crmec under a su:: contract ' rom EG&G Idanc. tnc.. a pnme centracter to :he United States Cecartment of Energy. Neither EG1G ncr the Unstec States Government nor any agency thereof, er any of their emcicyees. makes any warranty, expressac or impiiec, or assumes any .egal'iacility or rescensicdity for any third carty's use, or the results of such use. cr any infctmation accaratus. ;;reduct I cr process disciosec in this report, or represents that its use cy such third carty sculd not infnnge pnvately owned nyhts. NOTE - THIS IS A CRAFT 9ecause of schedule limitations. this report draft has not gene through :ne ccmciete l review cycle et FPC. While the overall cenctusion is ex;ected to remain the same, the reader is cautiCned that some details of the re;Crt may Change as the review is completed. A,
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I TER-C5417-5 CONTENTS Section Title Page l 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 3cepe of the Review . . . . . . . . . . 1-7 2 NRC CRITERIA FOR ENVIRCNMENTAL QUALIFICATICN. . . . . . 2-1
, 2.1 Criteria Provided by the NRC . . . . . . . . 2-1 l 2.2 Staff Positions and Supplemental Criteria . . . . . 2-1 1
2.2.1 Service conditions Inside containment for a Ioss-of-Coolant Accident. . . . . . . . 2-1 2.2.2 Submergence . . . . . . . . . . . 2-2 2.2.3 Equipment Located in Areas Normally Maintained at Room Conditions . . . . . . . . . 2-2 2.2.4 Si:nulated Service Conditions and Test Duration . . 2-3 2.2.5 Defer:nent of Qualification Review . . . . . 2-3 2.2.6 Test Sequence . . . . . . . . . . 2-4 2.2.7 Radiation . . . . . . . . . . . 2-4 3 METHCDOI4GY USED BY FRC . . . . . . . . . . . 3-1 4 TECHNICAL EVALCATION. . . . . . . . . . . . 4-1 4.1 Methodology Used by the Licensee . . . . . . . 4-1 4.1.1 Completeness of Equipment List . . . . . . 4-1 i 4.1.2 Definition of Equipment Operating Ti:ne Requirements. 4-2 4.1.3 Qualified Lif e . . . . . . . . . . 4-4 t 4.1.4 Licensee Event Reports (LER) . . . . . . 4-6 4.1.5 Licensee's Generic Positions With Respect to the DCR Guidelines . . . . . . . . . . 4-6 iii
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- 4 TER-C5417-5 CONTENTS Section Title Page 4.1.6 Required Signatures. . . . . . . . . 4-9 4.1.7 Chemical Spray . . . . . . . . . . 4-10 4.1.8 Description of Qualification / Replacement Plan 4-1,0 4.2 Equipment Qualified for Plant Life. . . . . . . 4-12 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 DCR Guide-lines Are Judged Acceptable. . . . . . . 4-12 4.3 Equipment Qualified Wita Restrictions . . . . . . 4-13 4.3.1 NRC Category II.a Equipment That Fully Satisfies All Applicable 3equirements of the DOR Guidelines and Eas a Service Life Less than Plant Life. . . . . 4-13 4.3.2 NRC Category II.b Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines Provided inat Specific Modifications Are Made. . . . . . 4-14 4.3.3 NRC Category II.c Equipment for Which Deviations From the DOR Guidelines Are Judged Acceptable . . . . . 4-14 4.4 NRC Category 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 J Equipment Which Has Qualification Testing Scheduled but Not Completed. . . . . . . 4-16 a
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e e e TER-C5417-5 CONTENTS Section Title Page 4.5.2 NRC Category IV.b Equipment for Which a Qualificacion Documentation in Accordance With the Guidelines Has Not Been Established. . . . . . . . . . . 4-16 4.6 NRC Category V Equipment Which Is Unqualified. . . . . . . . 4-34 4.7 NRC Category VI Equipment for which Qualification is Deferred . . . . 4-44 5 CONCLUSIONS . . . . . . . . . . . . . . 5-1 6 REFERENCES . . . . . . . . . . . . . . 6-1 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS APPENDIX S - EQUIPMENT ITEM TABLE APPENDIX C - SAFETY SYSTEMS FOR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED APPENDIX D - CABLE MANUFACTURERS LIST APPENDIX E - EQUIPMENT ITEM CROSS-REFERENCE
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- 1. INTRCCCCTION .
1.1 PURPOSE OF THE REVIrd The NRC Office of Inspection and Enforcement (IE) issued Bulletin 79-013, I
- " 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 12 electrical equipment required to function under postulated accident conditions and to submit a report on this action.
The objectives of the NBC Equipment Environmental Qualification Review program are to evaluate nuclear power plant safety-related electrical equipment in accordance saith criteria established by the NRC and to identify
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(1) equipment whose qualification documentation is adequate, i.e.,
- substanciare s 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 reasonable assurance that the equipment is capable of performing it specified safety function.
To meet the overall program gcals, the objective of this Technical Evaluation Report is to review the Licensee's submittals to determine if the
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Licensee reviewed its safety-related electrical equipment for environmental qualification in accordance with the DCR Guidelines and NUREG-0588 as required
. by IE Sulletin 79-013. The NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. If discrepancies are found, the audit will be extended.
1.2 GENERIC ISSUE BACKGRCUND Safety-related electrical equipment must be capable of performing design safety functions under all normal, abnormal, and accident conditions. Of particular concern is the assurance that equipment will remain operable during 6 A enter 1-1 *
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TER-C5417-5 and following exposure to the harsh environmental conditions (i.e., temperature, pressure, hum.dity (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 feca - the complete spectrum of postulated break sires, break locations, and single failures consequent to a less-of-coolant accident (LOCA) , main steam line break ptSLB) inside the reactor containment, or a high energy line break (HELB) 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 pe-formance, thereby establishing assurance that the poten':ial for common-mode failure is minimired. Qualification criteria applied during the licensing of the older nuclear plants have been modified over the years, and industry standards cencerning 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, and 381-77. NRC NUREG documents 0 413 and 0588 have been developed to address this tcpic. In particular, NCREG-058a_(published for ccmment in December 1979) formally presented the NRC staff positions regarding selected areas of envircnmental qualification of safety-related electrical equipment in the resolution of General Technical Activity A-24, " Qualification of Class 1E Safety Related Equipment." The positions documented therein are applicable to plants that are er will be in the construction permit er cperating 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 10CFR50, Aopendix A, General Design Criteria for Nuclear Pcwer Plants, Section I, Criteria 4. This criterion states in part that " structures, systems and components important to safety shall be designed to acccemodate the effects of and to be ecmpatible with the environmental conditions associated with normal cperation, maintenance, testing, and postulated accidents, including less-of-coolant accidents. "
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i ( S R-CS417-5 In additior., qualification requirements are also embodied in 10CFRSO Appendix A, General Design Criteria 1, 2, and 23 and Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Criteria III and XI. These requirements are applicable to safety-related equipment located inside as well as outside of containment. The NBC 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 these 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; hcwever, no regulatory guide was issued adopting the IEEE 323-71 standard. For plants whose Safety Evaluation Reports were issued af ter July 1,1974, the ccamission issued Regulatory Guide 1.89 which in most rerpects 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 enviren- ~ mental qualification (SZP 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 qualificaticn dccumentation. _. Preliminary NRC review of Licensee responses led to the preparation of NUREG-0458, an interim NBC assessment of the environmental qualification of electrical equipment. This document concluded that no significant safety deficiencies requiring imediate remedial actions were identified." However, it was recommended that additional effort should be devoted to examining the
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installation and environmental qualification documentation of specific electr Mal equipment in all operating reactors. 6 1-3 + en u.J Franklin
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i 1 TER-C5417-5 On May 31, 1978, the NRC Cffice of Inspection and Enforcement issued IE Circular 78-08, "Enviror. mental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants," which required all Licensees of c erating r plants (except those included in the SE? program) to examine their installed safety-related electrical equipment and ensure appropriate qualification documentation for equipment function under postulated accident conditions. , Subsequently, on February 9,1979, the NBC Office of Inspection and Enforce-ment issued IE Bulletin 79-01, which 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 the secpe of equipment addressed, definition of harsh environments, and adequacy of support documentation. It became apparent that generic criteria , were needed to evaluate the electrical equipment environmental qualification , for both SEP and ncn-SEP operating plants. Therefore, during the second half of 1979, the Division of Cperating Reactors (DOR) of the NRC issued internally a document entitled " Guidelines for Evaluating Environmental Qualificatien of Class lE Electrical Equipment in Cperating Reactors." (The document is hereaf ter referred to as the " DOR Guidelines. ") The document was prepared as ; a screening standard for reviewing all cperating plants, including SEP plants. Originally it was intended that the Licensees would evaluate their qualification documentation in accordance with the DOR Guidelines. Fewever, initial NRC review of this documentatien, which was ccmpiled to support Licensee submittals, revealed the need for obtaining independent evaluations and for accelerating the qualification review program. In October 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 , 6 M4 1-4 .
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aN TER-C5417-5 and to present the results in the form of a Technical Evaluation Report for each plant included in this program. On January 14, 1980, the NRC Office of Inspection and Enforcement issued the DOR Guidelines and IE Bulletin 79-013, 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 review was expanded to include high energy line breaks (inside and outside containment) in addition to equipment aging and submergence. The NRC advised the Licensees that the criteria contained in the DOR Guidelines would be used in its review of Licensee submittals; problems arising from this review would be resolved using NUREG-0588 as a -guide. In early February 1990, the NRC decided that Indian Point Units 2 and 3 and Zion Units 1 and 2 should be included within SEP Topic III-12 for the purpose of equipment envirenmental qualification review. On February 21, 1980, the NRC and representatives of the SEP Plant Cwners Group held an cpen meeting at NRC headquarters to discuss an accelerated review peogram in accordance with the DOR screening guidalines. Represen-tatives of the Indian Point Cnits and Sicn Station also attended this meeting. The NEC formally issued to all Licensees represented at the meeting 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 NRC on an accelerated schedule. For non-SEP plants, the NBC 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
*For References, see Secticn 6.
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O e . TER-C5417-5 review of the Licensees' responses to IE Bulletin 79-01B, 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 79-01B dated February 29, 1980. In April 1930, the NRC organirational structure was modified and the Equipment Qualification Branch was formed within the new Division of Engi-n eering . Responsibility for reviewing the status of equipment qualificaticn for all plants was assigned to this branch. On May 27, 1980, the NRC issued Memorandum and Order CLI-80-21, (67] 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 ccmpliance with the DCR Guidelines or NUREG-0588 must be completed no later than June 30, 1982.
In October 1980, EG&G awarded Franklin Research Center (FRC) a centract to provide assistance in the equipment environmental qualificatien review for . 13 of the plants whose Licensees responded to IE Bulletin 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 BACKGRCUND 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 Bulletin 79-01B, a response to significant questions raised during the public meetings, and two Crders. The Ceder dated May 30, 1980 required the Licensees to ccmply with the previously issued Commission Memorandum and Ceder of May 27, 1980 (CLI-80-21). The above Ceders 6
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O e TER-C5417-5 required the Licensees to complete the tasks identified in IE Bulletin 79-018
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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 79-018, 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 (EELB) and whose environment is adversely affected by that event. In additien, IE Bulletin 79-01B 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 tne limiting conditions resulting from (i) the entire spectrum of postulated line breaks resulting 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
- recirculated from inside containment to accomplish long-term cooling subsequent to an accident. Qualification aspects not included within the scope of this evaluation are:
e seismic qualification l e equipment protection against natural phencmena e equipment operational service conditiens (e.g., vibration, troltage, and frequency deviations) e equipment located where it is subject to outdoor environments e equipment protection against fire hazards e equipment pretection against missiles. ge 1-7
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- 2. ARC CRITERIA FOR ENVIRONMENTAL QUALIFICATION 2.1 CRITERIA PRCVIDED BY THE NRC The DCR screening guidelines used by FRC to evaluate the electrical equipment environmental qualification program were:
e " Guidelines for Evaluating Environmental Qualification of Class lE
?.1ectrical Equipment la Cperating Reactors" (64]
e " Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Is To Be Addressed" [64] e NUREG-0588, " Interim Staff Position on Environmental cualification of Safety-Related Electrical Equipment." (69] These guidelines were issued by the NRC in February 1980 for implementation by all Licensees. 2.2 STAFF POSITIONS AND SUPPLDENTAL CRITERIA The NRC identified the following staff positions and supplemental criteria to be used in conjunction with the referenced DCR screening guidelines. i 2.2.1 SERVICE CONDITIONS INSIDE CONTAINMENT ICR A LOSS-OF-COCLANT ACCIDENT (DCR GUIDELINES SECTION 4.1) For Pressurized Water Reactors (PWRs) , the DCR Guidelines state that the containment temperature and pressure conditions as a function of time should
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be based on the most recent NBC-approved service conditions specified in the Final Safety Analysis Report (FSAR) or other Licensee documentation. In the l specific case of pressure-suppression type containments, the following minimum high temperature conditions may be used: (1) Boiling Water Reactor (BWR)
- Drywells -- 340'? for 6 hours and (2) PWR Ice Condenser Lower Compartments --
l 340*F for 3 hours. As stated in Supplement 2 to IE Bulletin 79-013, [65]
*these values are a screening device, per the Guidelines, and can be used in I a 4A 2-1 ,
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TER-C5417-5 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 centsinment with due consideration given to analytical uncertainties. ne 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 impact of the spray on required equipment should be accounted for. , ne adequacy of a plant-specific profile is dependent on the assumptiens and design considerations at the time the profiles were develcped. The DOR Guidelines and NUREG-0588 provide guidance and considerations required to determine if the calculated plant-specific temperature / pressure profiles encompass the LCCA and HELB accidents inside containment. 2.2.2 SUBMERGENCE (DOR GUIDELINES SECTION 4.1, SUBITEM 3; and SECTION 4.3.2, SUBITDi 3) Squipment 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 79-01B (65] provides the folicwing additional criterien: If the equipment satisfies the guidance and other requirements of the DOR Guidelines or NUREG-0538 for the IDCA and HELB accidentJ, and the Licensee demCnstrates that its failure will not adversely affect any safety-related function or mislead the cperator after submergence, the equipm<nt can be censidered exempt from the submergence portion of the qualification requirements. 2.2.3 EQUIP W LOCATED IN AREAS NORMALLY MAINTAINED AT ROCM CONDITIONS (DOR GUIDELINES SECTION 4.3.3) Supplement 2 of IE Bulletin 79-01B [65] permits deferment of the review 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 t) nuclear radiation emanating fecm circulation of fluids containing radioactive subs:ances. At the Licensee's option, the review may be deferred until after Febtuary 1, 1981. 4___ 2-2 .
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TER-C5417-5 By June 30, 1982, all safety-related electrical equipment potentially exposed to a harsh environment in nuclear generating stations licensed to operate on 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 and 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 extremes not associated with accident conditions and to document 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 SIMULATED SERVICE CONDITIONS AND TEST DURATICN (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 conditiens return to normal. Supplement 2 to IE Bulletin 79-013 [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 I hour l it excess of the time assumed in the accident analysis. The staff has indicated that time 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. The 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 DEFERMEYr CF QUALIFICATION REVIEW
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l Supplement 3 to IE Bulletin 79-013 [66] permits the submittal of ( qualificatien documentation regarding the mI Action Plan equipment and the equipment required to achieve and maintain a cold shutdown condition to be delayed as follows: o Qualification informatien for installed WI Action Plan equipment must be submitted by February 1,19 81. 6 4 2-3 6 ff3 Franklin Research Center a om a e n. %a.ma enu. s.
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TER-C5417-5 e Qualification information for future TMI Action Plan equipment (reference NUREG-0737, when issued) , which requires NRC pre-implementation review, must be submitted with the pre-implementation review data. e Qualification information for TMI Action Plan equipment currently under NRC review should be submitted as soon as possible. e Qualification information for TMI Action Plan equipment not yet 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 GUIDELINES SECTION 5.2.3) Supplement 2 to IE Bulletin 79-013 [65] provides the following additional criteria:
" Sequential testing requirements are specified in NUREG-0588 and the DCR Guidelines. Licensees must follow the test requirements of the applicable document.
- 1. If the test has been completed without aging in sequence, 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 cging in the proper sequence . These programs would then fall in the first or second categosr.'
2.2.7 RADIATION (DCR GUIDELINES SECTICNS 4.1.2, 4. 2.2, and 4. 3. 2, SUBITEM 2) Supplement 2 to IE Bulletin 79-OlB (65] provides the following additional criteria:
"Both the DCR Guidelines and NUREG-0588 are similar in that they provide the methods for determining the radiation source term when considering LCCA events inside containment (100% noble gases /50% iodine /14 partic-ulates) . These methods c.cnsider the radiation source term m'ilting from an event which completely depressurizes the primary system and releases ,
the source term inventory to the containment. 2-4 *
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i TER-C5417-5 NUREG-0578 provides the radiation source term to be used for determining the qualification doses for equipment in close proximity to recirculating fluid systems inside and outside containment as a result of LOCA. This method considers a LOCA 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 qualifying equipment following non-LOCA events both inside and outside containment (10% noble gases /10% iodine /0% particulates) . When developing radiation source terms for equipment qualification, the Licensee must ensure consideration is given to those events which provide the most bounding conditions. The following table summarizes these considerations (3CS = reactor coolant system): LOCA Non-LOCA HELB Outside Containment NUREG-0578 NUREG-058 8 (100/50/1 (10/10/0 in RCS) in RCS) Incide Containment Larger of NUREG-0588 NUREG-0588 (100/50/1 (10/10/0 in Containment) in RCS) or NUREG-0578 (100/50/1 in RCS) Germaa equivalents may be used when consideratien of the centributions of beta exposure has been included in accordance with the guidance given in the DCR Guidelines and NUREG-0588. Cobalt-60 is one acceptable gamma radiation source for environmental qualification of refety-related equipment. Cesium-137 may also be used.' \
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- 3. METHODCLOGY USED BY FRC c.
IE Bulletin 79-01B required the Licensee to:
- e provide a master list which identifies the systems and electrical equipment required to function during and subsequent to an accident and to maintain the plant in a safe condition provide the environmental service conditions e
e identify the submergence levels e provide written evidence of the qualification of the equipment identified e evaluate the qualification documentation using the DCR Guidelines and NUREG-0588
, e submit a Licensee Event Report (LER) for electrical equipment -
determined not to be environmentally qualified. r The requirements of IE Bulletin 79-01B were requested under provisions of I 10CFR50.54 ( f)" , Conditions of Licenses," which requires the Licensee to submit written statements, signed under oath or affirmation, to enable the Commission to determine whether or not a license should be modified, suspended, or revoked. To provide assurance that the Licensee implemented the requirements of IE Bulletin 79-01B and to provide a basis for the NRC Safety Evaluation Report (SER) , FRC developed this Technical Evaluation Report (TER) by: l e assessing the Licensee's responses in relation to the general I requirements of tae DOR Guidelines as augmented by the supplements to l the 79 -01B Bulletin e using NUREG-0588 to resolve open issues, i- The results and conclusions contained in this report are valid assuming that the Licensee's analyses of test reports referenced in the Licensee 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
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- l TER-C5437-5 test reports, incorporating the results of the reviews with the conclusions of the TERs, when developing the plant-specific SERs.
The 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 2 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 environmental service conditions. This analysis resulted in a reduced listing containing 140 different equipment items 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 to: e NRC DCR Guidelines, as modified by NRC staff interpretations e Licensee definition of harsh service environments (Appendix A) . e analysis and/or justification of qualification e Licensee-proposed remedies for qualification deficiencies. Topics not within the scope of FRC evaluation are: l e completeness of the Licensee's listing of safety-related equipment e acceptability of Licensee-provided environmental service conditions I e acceptability of Licensee-stated position concerning safety system or component function e review and acceptability of qualification test reports and other qualification documentation. l
*In this report, the term " safety-related electrical 4quipment" refers to i
the equipment defined by the two NRC Guidelines referenced in Section 2.1. 6
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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 below. All equipment item numbers discussed in Section 4 of this report are associated with Reference 68. The NBC 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 containment, and manufacturer's nameplate data. The manufacturer and model number from the nameplate data were compared to information given in the System Component Evaluation Work Sheets (SCI,WS) of j the Licensee's report. The details of this site inpection are documented in I the IE Inspection Report Number 50-260/80-38 and will be addressed by the NRC.
.i
. NRC QUALIFICATICN CATEGORIES AND DEFINITIONS l
l e NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR 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 NBC Category I,b ! E(UIPMENT FOR WHICH DEVIATIONS FRCM THE DOR GUIDELINES ARE JUDGED AC:lEPTABLE This category includes equipment items which do not satisfy one or more
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TER-C5417-5 e NRC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR 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 equipcent is qualified for a specific time intervsl which is less than plant life. e NRC Category II.b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES PROVIDED THAT SPECIFIC MDDIFICATIONS 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 datte. When the modifications are complete, the equipment can be considered qualified. e NRC Category II.c EQUIP *ENT FOR WHICH DEVIATICNS FRCM THE DOR CUIDELINES ARE JUDGED ACCEPTABLE , This category includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelinest however, either sufficient 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 the applicable qualification documentation associated with the p neral equipment environmental qualification program. e NRC Category III EQUIPMENT THAT IS EXEMPT FROM QUALIFICATICN This category includes equipment items which are exempt from qualification on the basis that (i) the equipment 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 ecmponent can be accomplished by some other designated component which is fully qualified, or (iii) the equipment is not subject to a potentially adverse l 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. e NRC Category IV.a , EQUIPMENT WHICH HAS QUALIFICATION TEi..lG SCHEDULED BUT NOT COMPLETED The qualification of equipment items in L'his category has been judged deficient or inadequate based upon review of the documentation provided by the Licensee. However, the Licensee has stated that the equipment item i: bbnklin Research Center 3-4 ' 4 en=.a ae rh. n n
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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 foe each item. e NRC Category IV.b EQUIPMENT FOR WHICH QUALIFICATICN DOCUMENTATICN IN ACCORDANCE WITH THE GUIDELINPS 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 re'lecting comprehensive qualification documentation have not been made available for review. Specific justification for interim plant cperation should be provided for each item. e NRC Category V EQUIPMENT WHICH IS UNQUALIFIEL The DOR Guidelines require that complete and auditable record reflecting a comprehensive qualifica*. ion methodology and program be referenced and made available for review of all Class la equipment. 1 The qualification of equipment items in this category has been judged to be deficient or inadequate, based upon 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) 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 item has not passed the required tests. , e NRC Category VI EQUIPMENT FCR WHICH QUALIFICATION IS DEFERRED This category includes equipment items which have been addressed by the
- Licensee in the equipment environner.tal qualification submittals; however, the l qualification review of this equipmunt has been deferred by the NRC in accerdance with criteria presented in Sections 2.2.3 and 2.2.5 of this repcrt.
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- 4. TECHNICAL EVALUATION 4.1 METHODOLOGY USED BY THE LICENSEE The Licensee has submitted for Browns Ferry Units 1, 2, and 3 a rather voluminous equipment environ:wntal 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 !3,1980. All previous responses to IE Bulletin 79-013 (April 30 and July 18, 1980) are said to be superseded by this lastest 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 FBC has generated the following observations and comments. 4.1.1 COMPLETENESS OF EQUIPMENT LIST The Licensee discussed the approach used in selecting the equipment for l which qualification zust 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 (LOCA's) and High Energy Line Break (BELB) accidents. Only that equipment either required to function for accident zitigation (Category a, as defined in
. NUREG-058 8, Appendix E) or required not to fall (Category b, as l defined in NUREG-0588, Appendix E) during accident mitigation, including those required for cold shutdown, are contained in this report.
e The Evaluation Work Sheets (EWS) in Appendix C [68] and their supporting appendices provide documentation of qualification as
- defined by the DOR Guidelines.
e Browns Ferry Nuclear Emergency Cperating Instructions were also used to identify safety functions, safety systems, and ccaponents. e If a safety-related component's location in the plant was found to be outside the harsh areas, the item was deleted from the equipment list 6 M
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TER-C5417-5 (although it still is required to be qualified for its nonaccident service environ:nents) . Before an item could be deleted, all associated items, especially cabling, were identified and their 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 79-01B Supplement 2 requires that qualification documentation for all operating reactors (as of May 23, 1980) be evaluated using the DCR Guidelines. When sufficient detail is not provided by the DCR Guidelines, NUREG-05R8 Category II can be used. In addition, criteria to be used for evaluation of replacement components 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 construction 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 notes that the DOR Guidelines require the Licensee to review their emergency operating procedures to determine the electrical components needed or relied upcn 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 EQUIPMENT CPERATING TIME REQUIREMENTS The Licensee has defined the equipment operating time as follows: Cperating time was defined as the time period during which a component
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TZR-C5417-5 available to perform its function. This specified time period was given sufficient scope to incorporate all reasonable operating times required for the components in the category. The following operating time categories were used: M - One hour following accident initiation l l X - One day following accident initiation 1 ( Y - Thirty days following accident initiation 3 - One year following accident initiation W-Z Items marked as "W-Z" are components that fit into operating i category A for the first hour following accident initiation and I 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 and then to remain closed. X-Z Items marked as "X-Z" are components that fit into operating category A for the first 24 hours and then fit into operating category B for the year following the accident. Y-Z Items marked as "Y-Z" are components that fit into operating category A for the first 30 days and then fit into operating category B for the remainder of the year following the accident. t Operating time categories were assigned based upon the review of I components' functions. For ccmponents that perform multiple functions, each function was censidered and the worst-case time requirement used for the components. General functions were defined as having the following operating times categories: l W & W-Z Primary and secondary containment isolation (including SOTS initiation) following a LOCA or HELB inside primary containment (i.e. , the specific line that breaks); scram initiation (RPS), and 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 HELB's outside primary containment (except for the line broken); scram initiation (RPS) and scram for HELB's outside primary containment (except for a main steam line break in the valve I vault) . Y & Y-Z High pressure DCCS I t .- All other functions. 5 MME:: 4-3 *
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TER-C5 417-5 FRC EVALUATION: FRC concludes that the Licensee's approacn to operating time is acceptable. s 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 f or saf e shutdown of the plant. The DCR Cuidelines 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 detailed maintenance records to demonstrate that those components which can be degraded are replaced on a scheduled basis in order to restore the equipment and minimize the likelihood of equipment J f ailure to perform a safety-related function. Qualified life is the maximum period of normal service under specified conditions for which 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 specified safety function for an applicable accident and to remain functional as long as required af ter the accident. The qualified life may depend on carrying out a specified maintenance program. The qualified life of some 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 where justified by new information that permits a reanalysis of the goalification program.
It is necessery to establish a qualified life for every type of safety-related equipment that requires environmental qualification. A conservative choice of qualified life must be made to account for the . assumptions and approximations made in the qualification program. I
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TER-C5417-5 The Licensee stated: At the time of procurement of the equipment, documented evidence of aging effects was not a requirement; however, TVA intends to meet the DOR Guidelines in Section 7.0. If the equipment contains material subject to aging degradation (the guidelines require that this determination be made) , an analysis was done to determine the l maintenance or change out interval. When there was insufficient documentation to determine the thermal or radiation aging effects on a piece of equipment, a program of either further analysis of materials (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 replaccmants, 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 qualification. FRC notes that the salient points of the Licensee's methodology are: j e If equipment contains materials subject to aging degradation, an i analysis was conducted to determine the maintenance or change out
, interval.
e When insuf ficient documentation existed to allow determination of aging effects, an analysis program or type testing was instituted. o 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 (i) 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 l eliminated and (ii) that the Licensee's basis approach to aging is 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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TER-C5417-5 4.1.4 LICENSEE EVENT REPORTS (LER) The Licensee 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 saf ety function. Section 5.2 of the report provides a Summary of Equipment Qualification Status which included the LER number issued when the above determination has been made. FRC notes, however, that the Licensee has lef t 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 their listing. 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 betwoon the service conditions specificed and the actual conditions which could realistically be expected in a design basis 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 conditions for type testing needs to be considered only if Section 4.0 and Section 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 79-01B, specificed and demonstrated accuracies of all instruments for their trip functions and/or post-accident requirement must be provided. When the 6
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during the environmental extremes 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 peccurement specifications required and the vendor's demonstrated accuracies are much more stringent than system requirements, (2) surveillance tests are conducted periedly as required by the technical specifications to
, confirm the validity of the manufacturer's stated accuracy.
FRC concludes that the Licensee's position is acceptable for interim operation until full qualification can be obtained. C. OPERATING DATA The Licensee states: Substantial percentages of the systems components installed in , plant locations other than inside primary containment, have well e established industrial rating at or above the limits required for operation during and/or af ter the required DBE's. In cases whc;e operating data is used as a justification for interim qualification. This qualification will be supplemented at a later date by either type testing and/or further analysis. If neither of these options are available, a replacement plant was instituted. FRC notes that NBC required a definitive resolution by November 31, 1980 from the Licensee on all qualification issues, The Licensee's position is in variance with this requirement. D. RELATIVE HUAIDITY The Licenses states: 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.
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TER-C5417-5 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. E. TYPE TESTING The Licensee states: In Section 5.1 of the DCR Guidelines, type testing is preferred but not required for equipment subjected to severe temperature, pressure, and steam service condition. However, analysis is acceptable if supported by test data, for the other service conditions. At the time of equipment procurement, type testing was not a required method of proving qualification. To the extent that an analysis is not conclusive to verify qualification per the DCR guidelines, a type testing program or a replacement plan was initiated. TVA will provide justification for the interim operation until adequate qualification information is available to - seet the DCR Guidelines. FRC notes that the DOR Guidelines state , Type Testing is the preferred method of qualification for electrical equipment located inside containment required to mitigate the consequences of design basis events, i.e., Class IE equipment (see Section 3.0 above) . As a minimum,the qualification for severe temperature, pressure, 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 the.t 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. l F. RADIATION The Licensee states: e Beta Radiation - According to Section 4.1 of the DOR Guidelines, beta radiation har low penetrating power in comparison to gamma , rays of equivalent energy. Of the general classes of electrical I equipment in the plant containment (e.g., cables, instrument transmitters, valve operators, containment 9enetrations), i electrical cable is considered the most vulnerable to damage frem I beta radiation. For other equipment whose enclosure provides b
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TER-CS 417-5 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 20 gauge or less, an analysis of the l
i qualification of the equipment related to beta radiation was l included as attachments to the EWS's. i e Gamma Radiation - From Table C-1 in Appendix C in the DOR Guidelines and references 1 and 2 below, there is substantial test d ata available to demonstrate that most conventional material used in electrical equipment has a gamma radiation threshold exceeding 104 rads; the exception is solid-state devices containing N-MOS integrated circuits which have a threshold of 103 rads (see Table C-1) . Teflon has a threshold for damage of approximately 3.5 x 104 rada (for 20 percent decreases in elongation) . Electrical properties (e.g., resistivity) of these materials are sufficiently conserative initially, such that substantial changes can be tolerated without causing equipment failures or malfunction. Threshold is defined from the above referenced table as the radiation exposure required to change at least one physical property of the material. The t'treshold is ngi a point of failure or end of useful life; therefore, there is a cand of tolerance from the threshold point to the failure point whien may vary by an order of magnitude or more. On the above basis and the existing test data, it is not considered i necessary to perform a qualifications test or analysis on electrical equipment for radiation of less than 104 rads which would degrade the saf ety functicn of the equipment. FRC agrees with the Licensee's position 4.1.6 REQUIRED SIGNATURES The Licensee has stated: e To ensure ccepleteness and accuracy of the EWS signatures of a preparer, reviewer, and quality assurance engineer are required on each of the EWS. Any appendixes for which the preparer or reviewer of EWS was not directly responsible will also contain preparer and reviewer signatures. e The most significant changes to the EWS were as follows: 1) use of appendixes, 2) use of permanent notes, 3) required signatures, ar.d 4) 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. l 6 g_2 4-9 ,
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i TER-C5417-5 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 INS sheets.) FRC notes that the DOR Guidelines require domineralized water sprays to be addressed. In addition, the effects of in-leakage must be considered. The i Licensee has not complied with this requirement. 4.
1.8 DESCRIPTION
OF QUALIFICATION / REPLACEMENT PLAN The Licensee states: It is TVA's intention to comply fully with the requirements of Bulletin 73-013. This section addresses the requirements stated in item 4 of the bulletin for " outstanding items. " It is not possible to submit a deLiled qualification / replacement plan at this time. The following items nave a great impact on our inability to supply.a detailed schedule at this times i a. Li:sitations on industry's capability for testing large numbers of components,
- b. Availability of qualified replacement equipment.
4
- 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. When we receive schedules of testing from Wyle Lab, we will inform the NBC as stated in your letter dated Oc~.ober 1,1980, from D. G. Eisenhut to licensees of operating plants. TVA will make a best faith effort to test equipment as soon as possible. Howe'rer, if problems are encountered with either the testing or qualificabiliN of the equipment, the ! justification for continued operation wial 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 listed below, i
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TER-C5417-5 Category I - Components qualified to DOR guidelines.
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Category II - Components for which analysis indicating qualification but that lack documentation to prove qualification to DOR quidelines. Category III - Items that will os qualified by either analysis or type testing or a combination of these :nethods. Catan.ory 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. 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 infor: nation to NRC by November 1, 1980. With this information, on exact schedule for equipment replacement and specific justification for interim operation must be provided for any item which does not conform to Guidelines requirements. f i . l l 6 4-a-4-11 .
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. o TER-C5417-5 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 EQUIPMENT THAT FULLY 3ATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES (NBC Category I.a) This section includes equipment items which are fully acceptable on the I 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 Unu 2, no equipment items fall into this category. 4.2.2 EQUIPMENT FCR WHICH DEVIATIONS FRCM THE DCR GUIDELINES ARE JUDGED ACCEPTABLE (NBC Category I.b) ) This section includes equipment items which do not satisfy one or :nore of the applicable criteria defined in the DOR Guidelines but for which sufficient information has been presented to determine that the specific deviations are acceptable. For Browns Ferry Unit 2, no equipment iteras fall into this category. _ 1 4 O s d-S- 4-12
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TER-C5417-5 4.3 EQUIPMENT QUALIFIED WITH RESTRICTIONS This section includes equipment items fully acceptable on the basis that ( .4. ) all criteria defined in Section 2 of ' tis report are satisfied; (ii) the equipment is qualified for a time interval less than plant lifer or (iii) the l equipment requires specific modifications which, when completed, will establish full qualification. 4.3.1 NRC Category II.a EQUIPME.Vr THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE The following equipment items are fully acceptable on the basis that all applicable criteria defined in the DCR Guidelines are satisfied and that the i equipment is qualified for a specific time interval which is less than plant lLfe. I 4.3.1.1 Equipment Item No. 27 Solenoid valve Target Rock Model 73FF-005 l (Licensee Reference 34)
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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 l time interval less than plant life. 4.3.1.2 Equipment Item No.136 Electrical Penetration Assembly GE Model NSO4 (Licensee Reference 23) The Licensee has provided documentation that shows this equipment to be qualified to function in a post-accident environment and that it is qualified for a timw interval less than plant life. 1 i An 4-13 '
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TER-C5417-5 4.3.1.3 Equipment Item No. 138 Electrical Penetration Assembly Physical Sciences Corp. Model PSC P/N 2022C (Licensee Reference 21) The Licensee has provided documentation that shows this equipment to be unqualified in the area of aging effects and qualified for a specific time interval less than plant life. _ 4.3.2 NRC Category II.b EQUIPME E THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES PRCVIDED THAT SPECIFIC MODIFICATICNS ARE MADE Equipment items in this category will be fully acceptable and will satisfy all applicable criteria defined in the CCR Guidelines provided that specific :nodifications are :nade on or before the designated date. When the modifications are ccmpleted, the equipment can be considered qualified. For 3rewns Ferry Unit 2, no equipment items fall into this category. 4.3.3 NRC Category II.c - EQUIPMEM FCR *AHICH DEVIATIONS FROM THE DCR GUIDELINES ARE JUDGED ACCEPTABLE This section includes equipment items which do not satisfy one or :nors of the applicable criteria defined in the DOR Guidelines; however, either sufficient bases have been presented to allow a deter:sination 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 that plant ' life based on review of other applicable qualification documentation associated with the general equipment environmental qualification program. For Browns Ferry Unit 2, no equipment items fall into this category.
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o . TER-C5417-5 4.4 NBC Category III EQUIPMENT THAT IS EXEMPT FRCM QUALIFICATION Ihe eqcipment items in this category are exempt frota goalification on the basis that (i) the equipment does not provide a safety function (i.e., should
.vst 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 subjected 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 2, there are no equipment items that f all into this category.
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TER-C5417-5 4.5 EQUIPMENT FOR WHICH DOCUMENTATION CONTAINS DEVIATIONS FROM THE GUIDELINES THAT ARE JUDGED UNRESCLVED This section includes equipment items which are deficient on the basis that all criteria defined in the DOR Guidelines are not satisfied. However, the equipment item is either scheduled to be tested or is judged to have a high likelihood of operability. 4.5.1 'T Category IV.a
. QUIPME!ff WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT eUMPLETED The qualification of equipment items in this category has been judged deficient or inadequate based upon our review of the documentation provided by the Licensee. However, the Licensee has stated that the equipment item is scheduled to be tested by a designated date. Sie 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 Unit 2, there are no equipment items' that fall into this category.
4.5.2 NBC Category IV.b EQUIPMENT FOR WHICH QUALIFICATICN DOCUMENTATION IN ACCORDANCE WITH
':HE GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of the following equipment items is deficient or inconclusive based upon FRC's review of the documentr.tlon 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 has not -
been made available for review. Specific justification for interim plant operation should be provided for each item. 4.5.2.1 Equipment Ites Nos. I and 2 Solenoid valves 1: Atkomatic Model 15830WP-VPI 2: AAA Model SO2 (Licensee reference not cited) The Licensee has not provided qualification information for this equipment ite:n and reque ses permission for continued use of the solenoid valve based on , 4 2- 4-16
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TER-C5417-5 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. 3 Flow Indicating Switch Fischer & Porter Model 10A2235A-55AR1011 (Licensee reference not cited) This equipment item has not been qualified, but the manufacturer's
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specifications indicate that this type switch has seen tested and found to operate successfully at temperatures of 250*F and atmospheric pressure. T7A states that it will type test or replace this equipment (no date specified) . 4.5.2.3 Equipment Item No. 4 Differential Pressure Switch Dwyer Model 3302 (Licensee reference not cited) This equipment ites 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. 5 Solenoid Valve ASCO Model HB8302SlRU
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The Licensee fath4 to submit qualification documentation for this l equipment ites, but bases justificatica for continued operation on tests of similar valves from the same manufacturer. The Licensee will type test this item or replace it with qualified equipment during the next refueling outage. 42.- 4-17 .
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TER-C5417-5 4.5.2.5 Equipment Item No. 6 Pressure Differential Modifier Bone /well Mode 1: Relay Assembly R7165-1078 Terminal Assembly 122700 (Licensee reference not cited) The Licensee has f ailed 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. 7 Pressure Differential Indicating Controller Fischer & Porter Model 53EL3311BBlB 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 Ites No. 8 l Pressure Differential Transmitter Fischer & Porter Model 10B2494TSAB
~I (Licensee Reference 62)
The Licensee has provided documentation that shows this item to be qualified for radiation dose after an accident. Other environmental conditions have not been evaluated, however, and the Licensee will either type test this equipment or replace it with a qualified device during the next refueling outage. ; 4.5.2.8 Equipment Item Nos. 9 and 10 Temperature Element Weed Model SP60llAA3C275SN42 (Licensee reference not cited) The Licer'see 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. l 6 I
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TER-C5417-5 4.5.2.9 Equipment Item Nos.11,12, and 14 Solenoid valve ASCO Models HB830081RU, HV200-924-1F, and HTS 262A203A (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 t qualified equipment during the next refueling outage. 4.5.2.10 Equipment Ites No. 13 Flow Transmitter GE/NAC Model 50-554 212BK 33 (Licensee reference not cited)
?ae 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. 15 Solenoid valve ASCO Model HT8262A203A (Licensee reference not cited) l The Licensee states that qualification documentatior. is unnecessary for this equipment since the system will be replaced during the next refueling outage. l 4.5.2.12 Equipment Item No. 16 l Pressure Transmitter asiley 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. 4.5.2.13 Equipment Item No. 17 Flow Transmitter GE/MAC Model 555 (Licensee reference not cited) The Licensee has failed to provide qualification documencation to show that this item will successfully function in a post-accident environment. The 6 d 4-19
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TER-C5417-5 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. 18 Temperature Switch Penwal Model 18002-27 (Licensee reference not cited) 2e 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. 4.5.2.15 Equipment Item No. 19 Solenoid valve ASCO Model HTX8300861U (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. 4.5.2.16 Equipment Item No. 20 Level Switch Robertsbaw SL-200 (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 aquipment. 4.5.2.17 Equipment Ites No. 21 Solenoid valve ; I ASCO Model S300C61U l (Licensee reference not cited) The Licensee has failed to submit sufficient qualification documentation I for this equipment and does not state the intention to replace or type test it. I l ! 6
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TER-C5417-5 4.5.2.18 Equipment Item No. 22 Solenoid valve ASCO Model HTX8300C61U (Licensee reference not cited) 2e 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. 4.5.2.19 Equipment Item No. 26 Solenoid valve ASCO Model HB830081RF (Licensee reference not cited) The Licensee has failed to submit sufficient qualification documentation for this equipment and does not state the intention to replace or type test it. 4.5.2.20 Equipment Ites No. 28 Solenoid valve AfC Model HT8211C94 (Licensee reference not cited) f 3e Licensee has failed to provida qualification documentation to show t j 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. 21 Equipment Item No. 29 Indicator pcessure Converter Fisher Controls Model 546 (Licensee reference not cited) me Licensee has failed to provide qualification documentation to show l , 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. s g4 4-21
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TER-C5417-5 4.5.2.22 Equipment Item No. 30 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 funnion in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage. 4.5.2.23 Equipment Item No. 31 Solenoid valve , ASCO Model WPET8316E36 (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. 33 and 35 Thermostat 1 Honeywell Models T675A1508 and T675A1540 ' (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, by June 1982. ._ 4.5.2.25 Equipment Item No. 34 Damper Motor Honeywell Model M445A l (Licensee reference not cited) The Licensee has failed to provide qualification dccumentation 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, by June 1982. 6
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TER-C5417-5 4.5.2.26 Equipment Item No. 40 Motor GE Model 5K4254XL2 (Licensee 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 Licensee will either type test the item or replace it with qualified equipment during the next refueling outage. 4.5.2.27 Equipment Ites No. 51 Level Indicator Switch Yarway Model 4418C (Licensee Rs ference 46) The Licensee has fai:>,4 to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment. The Eicensee will retest this equipment. 4.5.2.28 ?quipment Item No. 56 Temperature Element Calmatic Model 158B7061P016 (Licensee refe.ence not cited) The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licenses will either type test the item or replace it with qualified equipment during the next refueling outage. 4.5.2.29 Equipment Item Nos. 61 and 62 ! Flow Transmitter l GE/NAC Model 50-555111BDAA3AAA ! (Licensee reference not cited) The Licensee has failed to provide qualification docu*.entation to show that this item will successfully function in a post-accident environment and The Licensee will either type test the item or replace it with qualified
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TER-C5417-5 4.5.2.30 Equipment Item No. 67 Limit Switch Micro Switch Models CPD-AR and CPD-AR30 (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 License will either type test the item or replace it with qualified equipment during the next refueling outage. 4.5.2.31 Equipment Item No. 69 Temperature Switch Fenwal Model 40-104014-103 (Licensee reference not cited) The Licensee has f ailed 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. 4.5.2.32 Equipment Item No. 70 Temperature Element Fenwal Model 28-232106-304 ' (Licensee reference not cited) The Licensee has failed to provide qualification documentation to shcw 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 d 4 ring the next refueling outage. 4.5.2.33 Squipment Item No. 76 , Limit Switches NAMCO Model D1200G (Licensee reference not cited) The Licensee has failed to obtain 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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I TER-C5417-5 4.5.2.34 Equipment Item No. 79 Pressure Transmitter GE/MAC Model Series 55 and 50 (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 i during the next refueling outage. 4.5.2.35 Equipment Item No. 80 PoM r Supply GE Models 570012FAAC1 and 583001AAG: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. 4.5.2.36 Equipment Item No. 92 Temperature Element American Standard Model 15887079P051 (Licensee reference not cited) The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident envirorunent. The Licensee will either type test the item or replace it with qualified equipment. 4.5.2.37 Equipment Item Nos. 88 and 89 Tegerature Element Scan Model SS1-1 (Licensee reference not cited) l Se 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. 5 M3 ' 4-25 *
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4 TER-C5417-5 4.5.2.38 Equipsont Item Hus. 93 and 99. Valve Turbine Control Terry Turbines Model Type 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. 4.5.2.39 Equipment Item No. 95 ' Pressure Switch Marcoid 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. 4.5.2.40 Equipment Item No. 97 , Square Root Converter GE Model 565100AAAC1 , (Licensee reference not cited) The Licensee has failed to provide qualification documentation to show 4 that this item will successfully function in a post-accident environment. The Licensee will either type test the ites or replace it with qualified equipment. 4.5.2.41 Equipment Item No. 102 - Level Switen l Robertshaw Model SL-202-A2X l (Licensee 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 ites or replace it with qualified equipment. 4.5.2.42 Equipment Ites No. 108 Pump Motor ; GE Model SK6348XC23A ' i (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 perform further tests to verify qualification of this equipment. __ 6 4-a- 4-26
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t l TER-c5417-5 4.5.2.43 Equipment Item No. 110 Pump Motor GE Model SK6336Xc198A (Licensee reference not cited) The Licensee has failed to provide sufficient qualification 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. 4.5.2.44 Equipment Item No. 112 l Rydrogen Element GE Model 47E226428G2 (Licensee reference not cited) I'he Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. 4.5.2.45 Equipment Item No. 113 Level Switch GEMS Model XM-36425 (Licensee reference n.'t cited) The Licensee has failed to provide qualification documentation to show that this item will successf ully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment. l l l Equipment Item No. 114 4.5.2.46 Solenoid valve Versa Model VSG-3521 (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 8-A' 4-27 '
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i TER-C5417-5 4.5.2.47 Equipment Item No.115 Limit Switch Micro Switch Model B3E6-2RN (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 Item No.116 Level Switch Autocon Model M-4 (Licensee reference not cited) The Licensee has failed to provide qualification documentation to show that this item will succes- 117 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 Item No. 117 Temperature Element Thermo-Elect Model 37582-1 (Licensee reference not cited) The Licensee has failed to provide qualification documentation to show that this ites will successfully function in a post-accident environment. The Licensee will either typo test the item or replace it with qualified equipment. 4.5.2.50 "quipsesit item No.118 Level Switch Meletron Model 9241-6SS10A (Licensee reference not cited) the Licensee has failed to provide qualification documentation to show that this ites will successfully . ion in a post-accident environment. The Licensee will either type test the item or replace it with qualifiid equipment. I i Da 4-28 l ..d Franidin Research Center .
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4.5.2.51 Equipment Item No. 120
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Solenoid Valve ASCO Model HVA86-030 (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 l 4.5.2.52 Equipment It e No. 121 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 i Licensee will either type test the item or replace it with qualified equipment.
- 4.5.2.53 Equipment Item No. 122 CRD Scram Inlet valve '- ASCO Model HVA-90-405-2A (Licensee reference not cited) i The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will sither type test the item or replace it with qualified equipment.
i 4.5.2.54 Equipment Item No. 123 Level Switch Robertshaw Model SL-305-E3-X (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
- - Licensee will either type test the item or replace it with qualified equipment.
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i l TER-C5417-5 l 4.5.2.55 Equipment Item No. 124 i Ion Chamber GE Mode. 237X7 31G001 (Licensee reference not cited) , the Licensee has failed to previde qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either f.ype test the item or replace it with qualified equipment. 4 . 5. 2. 5 ti Equipment Item No. 125 Sensor and Converter GE Model 194X927G014,12 (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. 4.5.2.57 Equipment Itita No. 126 Fission Product Monitor GE, No Model No. (Licensee reference not cited) The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident antironment. The Licensee will either type test the item or replace it with qualified equipment. t 4.5.2.58 Equipment Item No. 127 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. The Licensee will either type test the item or replace it with qualified equipment. O___,. 4-30 i.d Franklin Research Center a 4ca ana#n=r en -
TER-C5417-5 4.5.2.59 Equipment Item No. 128 Motor Control Center International Switchboard Corp. No Model No. (Licensee reference not cited) The Licensee has failed to provide qualification doctmentation to show that this item will successfully function in a post-accident environment. The i Licensee will either type test the item or replace it with qualified equipment. l The Licensee is pursuing the acquisition of the appropriate qualification information. 4.5.2.60 Equipment Item No. 129 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 poet-accident environment. The Licensee will either type test the item or replace it with qualified equipment. De Licensee is pursuing the acquisition of the appropriate qualification information. l i 4.5.2.61 Equipment Item No. 131 l Transformer l GE, No Model No. 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. 4.5.2.62 Equipment Item No.132 Solenoid valve Target acck Model 1/2 SMS-A-0-111 (Licensee reference not cited) ne 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. 0
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TER-C5417-5 4.5.2.63 Equipment Item No. 36 Motor Operated valve Limitorque SMB-000 (Licensee Reference 40) The Licensee has provided documentation that shows this item to be qualified in all areas except operating time. However, the Licensee states that substantive aging tests have been conducted which more than satisfy the requirements of the DOR Guidelines. FRC finds this evidence to be inconclusive and necessitating further testing. 4.5.2.64 Equipment Item No. 71 Pump Motor GE Model SK326PK-234A (Licensee refccence not cited) The Licensee states that redundant equipment is available to mitigate the accident and, consequently, suggests that this equipment item need not be qualified. No qualification information is presently available to the Licensee or FRC. The Licensee should pursue qualification of this equipment. 4.5.2.65 Equipment Item Nos. 45 and 46 Pressure Solenoid Operator _ Automatic valve Corp. C5497 (Licensee Reference 42) The Licensee bs provided insufficient documentation to enable evaluation of qualification for this equipment item. 4.5.2.66 Equipment Item No. 44 Differential Pressure Indicator Switch aarton 278 (Licensee reference not cited) The Ltcensee has failed to provide qualification documcntattien to show th&t this item will successfully function in a post-accident enviro"Jent. The Licensee requests approval for interim operation based on thi fa c-accident information provided by redundant low pressure instrumentation of MSIVs.
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,[ + TER-C5417-5 4.5.2.67 Equipment Item Nos. 24 and 25 Solenoid valve Valcor Model 256D (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 Bulletin 80-23, validity of the testing should be verified. 4.5.2.68 Equipment Item No.135 Electrical Penetration Assembly GE Series 100 (Licensee Referenc's 33) The Licensee has provided documentation that snows this equipment to be qualified to function in a post-accident environment. However in view of IE Bulletin 77-06, the qualification status should be verified. 6
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TER-C5417-5 4.6 NRC Category V EQUIPMENT WHICH IS UNQUALIFIED The DOR Guidelines require that complete and auditable records reflecting a comprehensive qualification methodology and program be ref erenced and made available fo. 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) documen-tation 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 documentation indicates that the equipment itera has not successfully passed required tests. The following equipment items are therefore considered unqualified. 4.6.1 Equipment Ites No. 23 Solenoid valve ASCO Model HB30081F (Licensee Reference 32) The Licensee has provided documentation that shows this equipment to be unqualified. The Licensee will retest the item or replace it with qualified equipment. 4.6.2 Equipment Iters No. 32 Component Assembly Nuclear Measurement Corp. Model Not Stated (Licensee References 35, 36, and 37) The Licensee has provided documentation that shows this equipment dcas not fulfill Guidelines requirements for temperature, humidity, and radiation dose. The Licensee will retest these monitors to deter: sine if they will function in the post-accident environment specified in this area of the plant. l
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l I TER-C3417-1 4.6.3 Equipment Item Nos. 37 and 39 Motor-Operated valve Limitorque Model No. SMB-000 (Licensee Reference 40) 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. ( 4.6.4 Equipment Item No. 38 Motorized valve Actuator Limitorque SMB-000 (Licensee Reference 40) The Licensee has provided documentation that shows this item to be unqualified in the area of operating time. However, the Licensee judges this equipment item to be qualified based on aging docamentation. 4.6.5- Equipment Item No. 42 Pressure Solenoid Operator Target Rock Model 1/2 SMS-A-O-1 (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 replace it with qualified equipment. l 4.6.6 Equipment Item Nos. 47 and 48 Temperature Switch Fenwal Model 17002-40 l (Licensee Reference 43) { The Licensee has provided documentation that shows this equipiaent to be qualified in all areas except radiation and aging. The Licensee will retest this equipment or replace it with qualified items.
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TER-C5417-5 4.6.7 Equipment Item Nos. 49 and 50 Pressure Switch 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. 4.6.8 Equipment Item Nos. 52 and 53 Pressure Switch Barten Model 288 (Liceasee References 47 and 48) The Liccaee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment. 4.6.9 Equipment Item Nos. '.4 and 55 Level Indicator Switen 3arton Model 288A (Licensee References 47 and 48) , The documentation provided by the Licensee shows this equipment to be - unqualified to successfully function in a post-accident er vironment. ~ 4.6.10 Equipment Iter. Nos. 58, 59, 64, 65, 84, 85, 86, 87, and 98 Motorized valve Actuators Limitorque Models SMB-2, SMB-00, SMB-3, SMB-0, and SMB-1 (Licensee Reference 49) The documentation provided by the Licensee fails to show that this equipment item is qualified to meet post-accident environmental ~ specifications. The Licensee states that it will subject this equipment to a retest to verify possible qualification. 4.6.11 Equipment Item Nos. 57, 60, and 63 Motorized Valve Actuators Limitorque Models SMB-2 and SMB-00 (Licensee Reference 49) The Licensee has failed to provide adequate agina documentation for this equipment item. The Licensee justifies permanent exemption from this DOR ' Guidelines based on Li:sitorque Test Reports 30003, 3-0027, and 600198, which __ 6 A_ 4-36 ,
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TER-C5417-5 show that this equipment perfor:ned successfully at temperatures higher than post-accident temperstures, albeit for a shorter time. Consequently, in its fudgment, this item is qualified. In response to the Licensee's position, FRC finds that this equipment ! eesains unqualified. l 1 4.6.12 Equipment Item No. 68 Solenoid valve ASCO Model X8300-B61F { (Licensee Reference 4 2) 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. 4.6.13 Equipment Item No. 73 Solenoid valve ASCO Model WPHTX8300B45F,R 8 (Licensee Reference 42) The Licensee has provided test report documentation that shows this item 1 to be unqualified in the area of test duration. Aging effects for this valve have not been evaluated. 4.6.14 Equipment Item No. 78 i* Flow Switch Barten Model 289 (Licensee References 53-55) The Licensee has provided documentation that shows this equipment to be i unqualified in the areas of radiation, test duration, and aging. The Licensee f will subject this equipment to further qualification testing or replace it
~ with qualified equipment.
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0 '. TER-C5417-5 4.6.15 Equipment Item No. 81 Level Transmitter Rosemount Model 1151 Series (Licensee References 56 and 57) Me Licensee has provided documentation that shows this equipment is unqualified in the areas of operating time and radiation. Aging qualification has not been dccumented. l 4.6.16 Equipment Item Nos. 91 and 92 Temperature Switch Fenwal Model 17023-6 (Licensee Ref erences 3 and 43) The Licensee has provided documentation that shows this item is unqualified in the areas of radiation and aging requirements. The Licensee states that the effects of aging due to the nor:nal environmental conditions are censidered negligible. ~ FRC finds this equipment to be unqualified. 4.6.17 Equiment Item No. 94 - Pressure Switch Barksdale Model PIH-M85SSV (Licensee References 44 and 45) ne Licensee has provided documentation that shows this equipment to be unqualified in the areas of temperMure, radiation and operating time. The Licensee it will retest or replace this equipment with qualified devices. 4.6.18 Equipment Item No. 96 Pressure Switch Static-O-Ring Models GN-AA21 and 6N-AA21-V (Licensee Reference 58) The Licensee has provided documentation that shows thist equipment is unquelified in the areas of temperature, radiation, and operating time. The Licensee it will retest thSs equipment and replace it if it proved to be unqualified to suitably function in a post-accident environment. a b 2.h 4-38 aj5nknn Researen center *
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TER-C5417-5 4.6.19 Equipment Item No.100 Pressure Switch Barksdale Model D2H-M150SS (Licensee References 44 and 45) The Licensee has provided documentation that shows this equipment to be unqualified in the arecs of temperature, operating time, and aging effects. The Licensee will retest this equipment to verify qualification or replace it with qualified equipment. 4.6.20 Equipment Item No.101
,L Motor Operator Limitorque Model SMB-4T (Licensee Reference 49)
The Licensee has provided test data that shows this equipment to be unqualified in the areas of temperature and operation duration. t 4.6.21 Equipment Item No.103 Pressure Switch 3tatic-O-Ring Model SN-AA3 [ _ (Licensee Reference 58) i The Licensee has provided documentation that shows this equipment to be unqualified in the areas of radiation, temperature, operating time, and aging effects. The Licensee will either retest or replace this equipment to provide L. satisfaction of the DOR Guidelines. i'
'- 4.6.22 Equipment Item Nos. 104 and 106 Motor Operator l L1:sitorque :lodels SMS-ST and SMB-4 i
(Licensee Reference 49)
,- The Licensee has provided docusintation from Limitorque Test Reports 600197, B-0027, and B-0003, which show that this equipment is unqualified in the areas of temperature, operating time, and radiation effects. The Licensee
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will continue testing to verify conclusions of the previously referenced test reports. Tg, 4-3a dj) Franklin a w ar n. Resear.ch r . m Center i
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TER-C5417-5 ) 4.6.23 Equipment Item No. 105 , Motor Operator Limiterque Model SMB-4 (Licensee Reference 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. 4.6.24 Equipment Ites No. 107 Differential Pressuse Indication Switch Barton Model 289A (Licensee References 48 and 53) The Licensee has provided documentation that shows this equipment to be unqualified in the areas of temperature, radiation, and operation time. 4.6.25 Equipment Item No.109 Flow Switch Barton Model 289
- fLicensee References 53 and 54) ,
The Licensee has provided documentation that shows this equipment to be unqualified in the areas of radiation, operating time, and aging effects. The Licensee will either provide further qualification documentation for this item or replace it with qualified equipment. 4.6.26 Equipment Item No. 111 Solenoid Valve ASCO Models X8315 and C28 (Licensee Reference 42) The Licensee hau referenced ASCO qualification test report AQ5-21678/TR - covering the 8300 series ASCO valves and finds them qualified in all areas except operation time and aging effects. In TVA's judgmerit, this equipment is _ of sufficient quality to function successfully in e design based post-accident t environment. FRC judges this equipment iters to be unqualified until further documentation can be provided to verify qualification. s 4-40 d[ranklin Fesearch a cama e The Frer ma e C. enter
TER-C5417-5 4.6.27 Equipment Item No.119 Level Switch Barksdale Model D2H-M18SS (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. r 4.6.28 Equipment Item No. 130 Motor Generator
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Louis Allis Model 8-127033 (Licensee References 4 and 59) l l The Licensee ha.s provided documentation that shows this equipment te be unqualified in the areas of operating time and aging effects. l t i 4.6.29 Equipment Item No. 134 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.
4.6.30 Equipment Item No. 137 Electrical Fenetration Asceably Physical Sciences Corp. Model PSCP/N2019C (Licensee Reference 14) The Licensee has provideo documentation that shows this equipment to be unqualified in the areas of operating time and aging effects. l
, 4.6.31 Equipment Item No. 139 Switches GE and Cutler Ma-r Models GE-CR2940 and CH-10250T (Licensee Reference 61) l The Licensee has provided documentation that shows this item is unqualified in the areas of operating time and radiation. The Licensee will
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continue equipment testing to determine the ultimate qualification of this equi; ment item. 4 4-41
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TER-C5417-5 4.6.32 Equipment Item No. 41 Motorized Valve Actuators ' Rotock 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. 4.6.33 Equipment Item No. 77 Pressure Switch Barton 289 (Licensee References 53, 54, and 55) The Licensee has provided documentation that shows this device to be unqualified in the areas of test duration and aging. 4.6.34 Equipment Item No. 72 Explosive Valve Conax Model 1832-117 (Licensee References 50 and 51) , The Licensee has provided data from test report References 50 and 51, which show 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 ~ successfully for up to 30 days in a post-accident environment. However, this information has not resolved qualification of this equipment item. 4.6.35 Equipment Item Nos. 43 and M Pressure Solenoid Operator ASCO WPHTX 8300B68F (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 testing is necessary to show that this equipment is qualified to adequately I operate in a post-accident environment. 5 g)_. 4-42 J.d Franidin Research Center *
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TER-C5417-5 4.6.36 Equipraent Item No. 83 Pressure Switch Static-0-Ring Model 12N/AA4 , (Licensee Refercnce 58) , l The Licensee has provided documentation that shows this equipment to be unqualified in the areas of operating time, radiation, and aging. l c 4.6.37 Equipment Ites Nos. 74 and 75 Limit Switch
,_ NAMCO Model EA740-50100 (Licensee Reference 52)
! The Licensee has provided documentation from Reference 52 (Acme-Cleveland 1 l Development Company Test Report 2/20/78) that shows the equipment to be l qualified in all areas for up to 7 years. However, the reports notes that the Licensee must use a qualified method for sealing the switch. The sesi has not been addressed. I i 4.6.38 Equilment Item No. 90 Tegerature Element i- Scram Model S51-1 (Licensee reference net cited) The Licensee has provided documentation which shows this equipment to be unqualified in the areas of aging and temperature requirements. l [ , L M f l 6 4J.7J Franklin Research Center 4-43 . 4 os= man at n. % wuses.
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TER-CS417-5 4.7 NBC Category VI EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED , This section includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittal but for which qualification review of this equipment has been deferred by the NRC in accordance with criteria presented in Sections 2.2.3 and 2.2.5 of this report. 4.7.1 Equipment Item No. 133 Junction Boxes . Various Model Nos. (Licensee References 19 and 20 FRC judges junction boxes to be non-electrical equipment and, hence, chooses not to evaluate their longevity or reaction to post-accident environmental conditions in this TER. rd 4.7.2 Equipment Item No. 140 Cable - See Manufacturers List The Licensee has failed to provide documentation that correlates cable type with its respective manufacturer and plant location to enable a proper evaluation of its environmental qualification. FRC, therefore, defers - qualification until substantive documentation has been provided by TVA. i l l 61 4...J Frankila Research Center 4-44 , l
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- 5. CONCLUSIONS FRC'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 2 plant has resulted in the following categories :
NBC Cog liance With The DOR Quantity Of Category Guideline Requirements Etruipment 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 Deviatior4s are Judged Acceptable II.a Equipment Fully Satisfies All Applicable Requirements for Less Than Plant Life 3 II.b Equipment Fully datisfies 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 FRC Tb Be Satisfactory for Imss Than Plant Life Based on Total EM Program Review 0 III Equipment is Exempt from Qualification 0 IV.a Equipment has Qualification Testing Scheduled 0 IV.b Ecruipment has High Likelihood of operability; However, Proper Qualification Documentation is Not Available 78 v Equipment is Unqualified 57 VI Equipment for Which Qualification 2 Is Deferred - O 5-1 a Research C.e.nter M Franidin,n. aw. r en .
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TER-C5417-5 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. The evaluation results are largely based on the available qualification documentation provided by tha Licensee. The results of the review do not necessarily imply that the equipment is unreliable, unsafe, or represents a significant plant safety issuer they do imply, however, that qualification documentation is inadequate ano that additional information is required. The Equipment Environmental Qualification Summary 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 compliarce 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 unqualified or qualification not established. L = A limiting condition witn respect to qualification in that the qualified life has not been established by the Licensee. O = NRC Qualification Category. R = Replacement of the equipment by the Licensee is planned. i O 5-2 AUJ* Franklin o or n.Research
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TER-C5417-5
- 6. REFERENCES
- 1. IPCEA S-61-402 Paragraph 3.9 and Appendix D.
- 2. WA Engineering Report No.1443.
- 3. Wyle Laboratory Report No. 43854-3.
- 4. NUREG-0588 Material List.
- 5. WA 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 1928.
- 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 Raport 1950B.
- 21. TVA Engineering Report 1925.
- 22. TVA Engineering Report 1926.
- 23. TVA Engineering Report 1921.
- 24. GE Letter dated 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.
~
- 27. MIL-C-4 914 2.
- 28. GE Report EPAQ-57.
- 29. GE Report EPAQ-60.
- 30. GZ Report EPAQ-10.
- 31. GE Prototype Test Data - Epoxy Life Tests.
- 32. ASCO Report No. AQS-21678/TR.
dh
...U FranMn Research Center 6-1
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. TER-C5417-5
- 33. Valcer Coc. No. QR-526 dated February 15, 1979.
34. Targ*at 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 MEB-63-01.
- 39. Appendix II to Sheet M23-64-02.
- 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 QSR018A012.
- 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
- 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 E12-3 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 '.0/10/79
- 60. TVA Engineering Report 1927 1
- 61. Wyle Lab Report QSR-002-A-0 2
- 62. Franklin Institute-F-C2815 Final Report
- 63. Rotock Report, "A" Range Nuclear Qualification
- 64. Letter from G. Lainas, NBC, to A. Schwencer, NRC. -
Subject:
Electrical Equipment Environmental Qualification, dated February 19, 1980. 6
# _N 6-2 ZEnklin Research Center a s w a. nmen m
B TER-C5417-5
- 65. Letter from Norman C. Moseley, NRC, to B. 3. Grier, J. P. O'Reilly, J. G. Keppler, K. V. S12fritz, R. H. Engelken, NRC. Subjects lE Supplement No. 2 Bulletin 79-013, Environmental Qualification of Class LE Equipment, $ated September 29, 1980.
- 66. Letter f rom Nor: nan C. Moseley, NRC, to B. H. Grier, J. P. O'Reilly, J. G. Keppler, K. V. Sezfritz, R. H. Engelken, NRC. Subjects lE Supplement No. 3 Bulletin 79-013, Environmental Qualification of Class lE Equipment, dated October 24, 1980.
- 67. U.S. NRC Memorandum and Order (CLI-8 0-21) pursuant to the Petition for Emergency and Remedial Relief filed with the NRC on November 4, 1977.
- 68. TVA Response to NRC .'E Bulletin 79-013, Environr.cntal Qualification of Class lE Equipment for Browns Ferry 1, 2, and 3, dated October
( 31, 1980. l
- 69. NUREG 0508 t
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TER-C5417-5 APPENDIX A - E.WIRONMENTAL SF.RVICE CONDITIONS This appendix contains temperature-pressure profiles or tables that are ref erenced 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 temperature / pressures given in either figures or tables are assumed to
~
linearly return to ambient in 24 hours. The three tables are as follows: e Table B.O (1,2,3) , Room Number, Name, and Plant Locatior. This table relates the room number to a room name and to a specific plant location (See plant arrangement drawings, sheets 1-6 for plant locations). See pages A-2 through A-9. e Table 8.00 (1,2,3) - Environmental Temperature / Pressure Curves - Room Number Designation Tnis table relates various room numbers to figures or Table B.1 (1,2,3) which are in this appcidix for temperature and pressure. See pages A-10, A-ll, and A-19 through A-53. e Table B.1 (1,2,3) - Temperature / Pressure t This table gives selected temperature / pressure values for selected l areas that are not contained in a profile. See pages A-12 through A-18. i 6 M A-1 . Jd) 4c Franklin aw wResearc.h- Center
-.#,. -w-. ,- ,, - . - - - , - - . - - - , - +,7- p -- , , , , , ,- - - ---,,, , - , - - , - . - . , - - - - - - - - - , - -
1 1 e , I 1 TER-C5417-5 I TAs u B.0 ft.2.3) Room 4moer. Name. and Mant location Plant Location
- toom go. noom Name fSheet 1-6) 0 Instow Primary Containment (Drywell) Sheet 2 00 Inside Primary Containannt (Wetwell) '.etwell 1 HPC! Pumo (or Turbine) Rocm; elevation 519.0' Sheet 1 2 5. W. 4HR kwe Acos; elevation 519.0' Sheet 1 3 N. W. 2!C! and Core Soray Pumo Room; elevation 519.0' Sheet 1 4 4. E. Core Soray Pao Room; elevation 519.0' Sheet 1 5 5. E. RNt Pamp toom; elevation 319.0' Sheet 1 6 Pressure Suppression Chamoer (HPC!
Torus Room); elevation 519.0' Sheet 1 7 Main Steam Yault Roan Sneet 2 8 Doen Aree; elevation $65.0' Sheet 2 3 Goon Areas; elevation 593.0' Sheet 3 10 RWCU Puo Acom; elevation 593.0' Sheet 3 - 11 GCW wat Exchange Room; elevation 533' Sheet 3 12 Coen Areas; elevation 621.25 Sheet 4 13 South Goen Areas; elevation 629.0' Sheet 5 14 %or+n Coen Area; elevation 639.0' Sheet 5 15 units 1-3 Refueling Floor; elevation 664.0' Sheet 6 16 Unit 13; elevation 593; RWCU SW receiving tant rm sheet 3
' Unit 1 locatioes same as Unit 3.
Table B o s a FIGOR,c.- eg.p' ,';ED .,_ .. hLUEnkiin Research C. enter
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l 4 TER-C5417-5 TABLE 9,0 (1,2,3) (continued) l
%on %meer. %me, and slant Location Roan %. Plant Location Room %me (Sheet 1-4) 17A Unit 1-3; elevation $39; RWCU Dominere112er A Sheet 5 175 Unit 1-3; elevation 639; PWCU Domineralizer B Sheet 5 18 Unit 13; elevation 621.25; Clean un Domin Ylv Rm Sheet 4 l
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TER-C5417-5 With respect to environmental service conditions, the Licensee ha s stated: A. Service Conditions The environmental conditions present in plant areas that can affect safety-telated equipment have been established. The following - categorier were used to bound anticipated olant conditions.
- 1. Normal - The temperature, pressure, humidity, and radiation ranges 1 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 uay 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 aarvice conditions were performed consistent with '.ae guideliner of IE Eulletin 79-01B and NUREG-0588 and in accordance with either TVA quality assuranco 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 I4X:A Design Basis Accident (DBA) and the Intermediate Break Accident _ (ISA) . The DBA and a 0.5 f t2 steam leak produce the most severe temperature transient in the drywell. The containment pressure and tamperature response for all breaks were evaluated by the methods discussed in General Electric Report No. NEDO-20333, June 1974. Mass and energy releases were calculated using the methods also discussed in the above General Electric report. Details of the analyses are provided in FSAR, Section 14 and General Electric Report NEDO-24580. 6 8-O- A-54 i.4 Franklin Research Center 4%wm r n - 4
TER-CS417-5 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 equipment. The areas affected by high energy line breaks are th; .eactor building and the main steam valve vaults.
- 1. Reactor Building
- The high energy lines located in the reactor boilding
! are: l (1) H_gh Pressure Coolant Injection (HPCI) steam supply to the pump turbine - 547'F,1020 psia, quality - 1. (2) Reactor Core Isolation Cooling (PCIC) supply to the RCIC pump turbine - 547'F, 1020 psia, quality '. l (3) Reactor Water Cleanup (RECU) system - 547'F, 1020 psia, quality - 0. Sinale-ended circumferential ruptures at the fluid conditions listed above were postulated. Mass and energy releases for all steam supply lines except one j break of the RWCU were generated using the Moody 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 ti7es include signal process time, valve stroke time, and break detection time. The sensors used are redundant, class lE, a,d electrically trained. Mass and energy release of the remaining RWCU break was 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 base <' on high fluid temperature at the discharge of the nonregenerative heat exchangers. The steam valve vault was modeled using three nodes and were input into the COMPARE-MOD 1 computer code. No heat
._ sinks were considered.
l 6
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- l ..J Franklin 4 o~a wResea.rch w r. .= Center i
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l TER-C5417-5 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. %diation 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 Bulletin 79-013 and NUREG-0588. Initial airborne sources in the dr*/well were calculated asnuming an instantaneous release of 100 percent of the ; core inventory of iodine. Transfer of iodine from the i drywell free volume to the water in the terus was causervatively calculated as a function of time until the airborne concentration was reduced by a facror 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 i 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 , SGTs. m Source terms were calculated at varior time after an accidene allowing for decay and dose rates were calculated with a point-kernel-with-buildup computer code. Tadiation exposures in the reactor building due to recirculation of the torus water through the RER and containment spray systems were also cal;ulated. These dose rates were then integrated over the duration of the accident. l
- 3. Main Steam Valve Vaults The high energy lines in the valve vaults are the main steam lines and the main feedwater 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 A double-ended rupture of the main steam coincident with , a break of the 4-inch RCIC steam line was evaluated. Mass and energy releases were provided by General Electric. Break flow was terminated by isolation of the main steam lines baned on signals from safety-related sensors. ,
#-:26 A-56 ,
. 2 Frankiin
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TER-C5417-5
- 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 nonaccident conditions were obtained from information used in the initisi dasign phase of the plant in I conjunction with data accumulated at the plant site in l
, _ various apaces, for all units, under extreme outside temperature conditions (100*F outside atmosphere) . <- Pressures and temperatures fur accident conditions were obtained from transient curves and analysis which studied the effects of a LCCA on reactor zone spaces.
Environmental service and conditions were only l 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) , 3 LOCA/HELB inside primary containment, HELB cutside primary containment, and tornado (sudden pressure drop p by 3 pounda per square inch) .
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TER-C5417-5 APPENDIX S - EQUIPMENT ITEM TABLE This appendix contains the list of safety-related electrical items for Browns Ferry Nuclear Plant Unit 2 provided by the Licensee in the October 31 response to IE Bulletin 79-013. This listing shows the equipment items by manufacturer and model numbers, plant locations, and time required to function as determined by the Licensee. t a r .- 4 3-1 42 Franidin Research Center awwNr- w y,.g - --r-e+. - w--
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TER-C5417-5 PLANT NAME: BROWNS FERRY 2 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 1 Solenoid Valve 8 EEB-23-1001 None Atkomatic 15830WP-VFI 2 Solenoid Valve S EEB-32-1001 None AAA EEB-32-1002 None S02 ,
- 3. Flow Indicating 12 EEB-43-1001 None Switch 12 EEB-43-1002 None Fischer & Porter 10A2235A-55AR10ll 4 Differential Pressure 14 EEB-64-1001 None Switch 14 EEB-64-1002 None Dwyer 14 EEB-64-1003 None 3302 14 EES-64-1004 None 14 EEB-64-1005 None 15 EEB-64-1006 None 15 EEB 1007 None 15 EEB-64-1008 None 15 EEB-Al-1009 None 15 EEB-64-1010 None 15 EEB-64-1011 None 15 EEB-64-1012 None 14 EEB-64-1026 None 14 EEB-64-1041 None 15 EEB-64-1042 None -
5 Solenoid valve 15 EEB-64-1013 None ASCO 15 EEB-64-1023 None EB830281RU 12 EEB-64-1024 None 14 EEB-64-1025 None 14 ZEB-64-1028 None l s l dWI$22
- t. J Franklin Researen Center B-2 .l 4 cm. mon or n renn n
TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION
~
NO. DESCFIPTION LOCATION PAGE REFERENCES REFERENCES 6 Differential Pressure 14 KEB-64-1014 None Modifier 15 EEB-64-1015 None Honeywell 15 EEB-64-1038 None R7165-1078 Relay Assm. 122700 Terminal Assa. 7 Differential Pressure 14 EEB-64-1016 None
~~
Indicator Controller 15 EEB-64-1017 None Fischer & Porter 15 EEB-64-1018 None 53EL33113Bl3 ESL-01 8 Differential Pressure 14 EEB-64-1019 None Transmitter 15 EEB-64-1020 None Fischer & Portar 15 EEB-64-1021 None 10B2494TBAB 9 Temperature Element 6 EEB-64-1027 None
-- Weed SP6011AA3C275SN42 1
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- GE/MAC 50-554212BKZZ3 14 Solc-old Valve 8 EEB-67 -1001 None
"' ASCO 9 EEB-67-1002 None HT8262A203A 9 EEB-67-1003 None 15 Solenoid V41ve 6 EEB-76-1014 None ASCO 6 EEB-76-1015 None HTS 262A203A 6 EMB-76-1017 None 6 EEB-76-1018 None 6 EEB-76-1019 None 6
6 EEB-76-1020 None 6 EEB-76-1021 None pf1_3 8
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c TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE 2EFERENCES P.EFERENCES 16 Pressure Transmitter 8 EEB-67-1009 None Bailey 9 EEB-67-1010 None 551 17 Flow Transmitter 12 EEB-84-1007 None GE/MAC 12 EEB-84-1008 None 555 18 Temperature Switch 12 E.?B-69-1001 None Fenwal 12 EEB-69-1002 None 18002-27 , 12 EEB-69-1003 None 12 EEB-69-1004 None 12 EEB-69-1005 None 12 EEB-69-1006 None 12 EEB-69-1007 None 12 EEB-69-1000 None , 19 Solenoid Valve 3 EEB-71-1001 None ASCO 3 EES-71-1002 None HTX8300861U 20 Level Switch 4 EEB-73-1001 None Robertshaw 4 EEB-73-1003 None SL-200 21 Solenoid Valve 6 EEB-74-1001 None ASCO 6 EEB-74-1002 None 8300C61U 6 EEB-74-1003 None 6 EEB-74-1004 None 22 Solenoid valve 3 EEB-75-1001 None ASCO 3 EEB-75-1003 None HTX8300C61U ! 23 Solenoid Valve 3 NEB-64-OL3A 32 ASCO HB830081F 24 Solenoid Valve 6 EEB-76-1001 33 Valcor 6 EEB-76-1002 33 5260 6 EEB-76-1003 33 f 33 6 EEB-76-1004 6 EEB-76-1005 33 6 EEB-76-1006 33 6 EEB-76-1007 33 ( 6 EEB-7 6-1012 13 6 EEB-76-1013 33 5 fa
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TER-C5417-5 EQUIPMENT LICENSEE ITE4 ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 25 Solenoid valve O EEB-76-1008 33 Valcor 0 EEB-76-1009 33 5260 0 EEB-76-1010 33 0 EEB-76-10ll 33 26 Solenoid valve 4 EEB-77-1005 None ASCO HB830081RF 27 Solenoid Valve 8 EEB-84-1001 34 Target Rock 8 EIB-84-1002 34 73FF-005 8 EEB-84-1003 34 8 EEB-84-1013 34 28 Solenoid Valve 12 EEB-84-1005 None ASCO 12 EEB-84-1006 None HT8211C94 29 Indicator Pressure 12 EEB-84-1009 None Converter 12 EEw-84-1010 None Fisher Controls 546 30 Pressure Switch 12 EEB-84-10ll None Custom Components 12 EEB-84-1012 None 630GH 31 Solenoid valve 8 EEB-85-1001 None ASCO 8 EEB-85-1002 None l WPHTS316E36 32 Component Assembly 9, R13, S EEB-90-0002 35, 36, 37 Nuclear Measurements 8, R10, U EEB-90-0005 35, 36, 37 m Corp. 8, R12, U EEB-90-0008 35, 36, 37 No Model No. 33 Thermostat 14 MEB-63-01 38 Honeywell T675A1508 34 Damper Motor 0 MEB-64-01 None Honeywell M445A 35 Thermostat 2, 3, 4, 5 MEB-64-02 39 Honeywell *
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TER-C5417-5 EQUIPMENT LICENFEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 36 Motor-operated valve 9 MEB-67-01 40 Limitorque 7 NEB-1-013 40 SMB-000 8 NEB-23-029 40 37 Motor-Operated Valve O MEB-67-02 40 Limitorque O NEB-1-012 40 SMB-000 38 Motor-operated Valve 6 MEB-71-01 40 Limitorque' 6 MEB-73-01 40 SMS-000 39 Motor-operated Valve 1 MEB-73-02 40 Limitorque 2 MEB-74-01 40 SMB-000 3 MEB-71-02 40 40 Motor 2 MEB-77-02 Ncne GE 4 MEB-77-03 None 5K4254XL2 2 MEB-77-04 None 5 MEB-77-06 None 41 Motor-Cperated Valve 12, 13 MEB-78-01 None Rotock
~ 14A 42 Pressure Solenoid 0 NEB-1-002 41 Operator Target Rock 1/2 SMS-A-01 43 Pressure Solenoid 0 NEB-1-002A 42 Operator 0 NED-43-030 42 ASCO WPETx8300868F 44 Differen. .1 Pressure 4 NEB-1 303 None Indicat Switch Barton 278 45 Solenoid Operator 0 NEB-1-005 None Automatic Valve Corp.
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TER-C5417-5 EQUIPMENT LICENSEE
.- ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGF REFERENCES REFERENCES 46 Solenoid Operator 7 NEB-1-007 None Automatic Valve Corp.
C-5497 47 Temperature Switch 7 NEB-1-008 43 Fenwal 17002-40 1 ., 48 Temperature Switch 11 NEB-69-81 43 Fenwal 17002-40 49 Pressure Switch 9 NEB-3-015 44, 45 Barksdale 9 NEB-3-018 44, 45 32T-A12SS 9 NEB-3-021 44, 45 50 Pressure Switch 2 NEB-71-84 44, 45 c- Barksdale 2 NEB-73-128 44, 45 32T-A12SS i.
. 51 Level Indicator 9 NES-3-016 46 Switch 9 NEB-3-017 46
- Yarway 9 NEB-3-019 46 4418C 9 NEB-3-022 46 9 NEB-3-021 46
~
l 52 Pressure Switch 9 NEB-3-021A 47, 48 l Barten 8 NEB-75-226 47, 48 l 288 53 Pressure Switch 4 NEB-68-72A 47, 48 l Barton 2 NEB-71-83 47, 48
<_ 288 54 Level Indicator 9 NEB-3-023 47, 48 Switch Bar ton 288A f
55 Level Indicator 2 NEB-73-129 47, 48 Switch Barten 288A 56 Temperature Element 8 NEB-23-025 None. I Calmatic 8 NEB-23-027 None ! . . , 15dB7061P016 8 NEB-74-209 None 6
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TER.-C 5 417-5 EQUIPMENT LICENSEE ITEM Im SUBMITTAL QUALIFICATION No. DESCRIPTICN LOCATION PAGE REFERENCES REFERENCES 57 Motor w.arated valve 8 NES-23-026 49 Limitorque 9 NEB-74-205 49 SMB-2 9 NEB-75-222 49 9 NEB-75-224 49 9 NES-74-196 49 8 NEB-74-196A 49 8 NEB-74-197 4? 9 NEB-74-197A 45 - 9 NEB-75-235 49 9 NEB-75-237 49 9 NES-74-206 44 53 Motor-operated valve O NED-68-069 49 Limitorque O NEB-73-130 49 SMB-2 59 Motor-Cperated valve 1 NEB-73-149 49 Limitorque 3 NEB-75-217 49 SMB-2 4 NEB-75-234 49 60 Motor-Operated Valve 6 NES-73-168A 49 Limitorque 6 NEB-73-147 49 SMB-2 6 NEB-74-204 49 6 NEB-74-193 49 6 NEB-74-195 49 Flow Transmitters NES-23-028 61 8 None GE 50-555111BOAA3AAA 62 Flow Transmitters 3 NEB-71-ll6 None GE NED-75-220 None 50-555111SOAA3AAA 1 NEB-73-165 None
~
2 NEB-74-189 None 2 NEB-74-190A None 4 NEB-75-223 None 5 NES-74-199 None , 5 NEB-74-203 None 63 Motor-operated valve 8 NEB-23-029 49 Limitorque 6 NEB-70-82 49 SMB-00 7 NEB-71-96 49 12 NEB-74-207 49 6 NEB-74-194 49 64 Motor-operated valve O NES-71-85 49 Limitorque O NEB-74-208 49 , SMS-00
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TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES
- 65 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 66 Solenoid Valve O NEB-43-030 42
+ ASCO 4PHTX8300868F 67 Limit Switch 0 NEB-43-031 None Micro Switch 0 NEB-43-033 None CPD-AR CPD-AR30 68 Solenoid Valve 12 NEB-43-032 42 ASCO X8300-B61F r- . NEB-63-034 None 69 Temperature Switch 14 Fenwal 40-104014-103 70 Temperature Element 14 NEB-63-035 None l Fenwal 28-232106-304 71 Pump Motor 14 NEB-63-037 None GE l 5K326PK-234A
~
72 Explosive Valve 14 NEB-63-038 50, 51 Conax 1832-117 73 Solenoid Valve 8 NEB-64 -039 42 ASCO 8 NEB-64 040 42 WPHTX8300B45F, R 12 NEB-64 -047 42 8 NEB li-053 42 8 NEB .5-242 42 l
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74 Limit Switch 0 EEB-1-1007 52 NAMCO O EEE-1-1009 52 l 52 i EA740-50100 0 EEB-1-1004 0 EEB-1-1005 52 i 75 Limit Switen 7 EEB-1-1008 52 NAMCO 7 EEB-1-1010 52 ,
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TER-C5417-5 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 76 Limit Switch 12 NES-64-0 52 None NAMCO 8 NEB-64-054 None D1200G 8 NEB-64-056 None 8 NEB-64-056A None 8 NEB-76-239 None 8 NEB-64-041 None 8 NEB-64-043 None 8 NEB-64-045 None 12 NEB-64-048 None 8 NEB-64-050 none 8 NEB-76-239A None 8 NEB-76-239B None 8 NEB-76-239A None 8 NEB-85-268A None 77 Pressure Switch 8 NEB-64-046 53, 54, 55 Barton 289 . 78 Pressure Switch 3 NEB-71-il5 53, 54, 55 Barton 1 NEB-73-164 53, 54, 55 289 1 NEB-74-188 53, 54, 55 3 NEB-75-219 53, 54, 55 79 Pressure Transmitter 9 NEB-64-058 None GE/MAC 6 NEB-64-059 None 551032CAAEl 9 NEB-64-068 None 552032KAATl 3 NEB-71-097 None 556220BAAAl 3 NEB-71-105 None 50-551031EAAEl 3 NEB-71-110 None 50-551032GAAK1 2 NEB-73-157 None 50-551032CAAY1 1 NES-73-163 None 50-551032EAAK1 2 NEB-74-190 None 50-551032GAAN1 5 NES-74-200 None 6 NEB-74-210 None 80 Power Supply 12 NEB-64-060 None GE 12 NEB-71-098 None 583001AAGK1 570012FAACl al Level Transmite=r 6 NEB-64-061 56, 57 Rosemount 6 NEB-64-067 56, 57 1151 Series a d-h- B-10 , *1
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TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 82 Temperature Element 6 NEB-64-062 None American Standard 6 NE3-64-063 None 158B7079P051 83 Pressure Switch 9 NEB-64-064 " S tatic-O-Ring 9 NEB-64-065 ~4 12N/AA4 9 NEB-64-066 58 1
! 84 Motor-operated Valve O NEB-64-070 49 Limitorque O NEB-74-186 49 SMB-8 35 Motor-operated valve O NEB-69-73 49 Limitorque SMB-0 86 M.*or-Operated Valve 11 NEB-69-74 49 t -- Limitorque SMB-0 87 Motor-operated valve 3 NEB-71-100 4?
' Limitorque 2 NEB-73-160 49 SMB-0 2 NEB-73-169 49 1 NES-75-214 49
~
3 NEB-73-161 49
~
1 NEB-75-227 49 l I 88 Temperature Element 2 NEB-74-213 None Scam 5 NEB-74-213A None S51-1 1 NEB-73-174 None 3 NEB-71-120 Nene
.. 89 Temperature Element 8 NEB-74-213B None
- Scam 12 NEB-74-213C None
! ,- S51-1 17A NEB-69-76 None 17B NEB-69-77 None 18 NEB-69-78 None 11 NEB-69-79 None 10 NEB-69-80 None
- 8 NEB-74-181 None l
90 Temperature Element 6 NEB-74-213D None Scam 6 NEB-71-121 None S51-1 6 NEB-73-175 None 5
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PER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 91 Temperature Switch 3 NEB-71-089 43, 3 Fenwal 1 NEB-71-089A 43, 3 17023-6 L NEB-73-131 43, 3 1 NEB-73-132 43, 3 1 NEB-73-136 43, 3 92 Temperature Switch 6 NEB-71-090 43, 3 Fenwal 6 NEB-73-135 43, 3 17023-6 6 NEB-73-141 43, 3 6 NEB-73-142 43, 3 93 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 NES-71-123 None 3 NEB-71-124 Non*. , 3 NEB-71-125 Ncne 94 Pressure Switch 3 NEB-71-104 44, 45 Barksdale PIH-M85SSV .- 95 Pressure Switch 3 NEB-71-106 None Mercoid 1 NEB-73-158 None DA-7043-804 3 NEB-75-216 None OA-23-804 4 NEB-75-229 None 96 Pressure Switch 3 NEB-71-112 58 S tatic-O-Ring 1 NEB-73-162 58 GN-AA21 GN-AA21-V 97 Square Root Converter 12 NEB-71-ll4 None GE 565100AAACl , 98 Motor-Operated Valve NEB-71-ll7 49 Limitorque 3 NEB-71-113 49 SMB-1 3 NEB-71-119 49 3 NEB-75-221 49 2 NEB-74-179 49
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TER-C5417-5 EQUIPMENT LICENSEE Im ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 99 Turbine Controls 1 NEB-73-148 None Terry Turbines 1 NEB-73-154 None Type CCS 1 NEB-73-151 None 1 NES-73-155 None 1 NEB-73-171 None 1 NES-73-172 None
~
1 NEB-73-173 None 1 NEB-73-173A None 100 Pressure Switch 1 NEB-73-156 44, 45 3arksdale D2H-M150SS 101 Motor-Cperated Valve 1 NEB-73-167 49 Limitorque 1 NEB-73-166 49
'_ SMB-4T 1 NEB-73-170 49 m 102 Level Switch 1 NEB-73-176 None Robertshe.
SL-202-A2X 103 Pressure Switch 2 NEB-73-180 58
- Static-O-Ring 2 NEB-73-180A 58 5N-AA3 5 NEB-73-184 58 5 NEB-73-184A 58
! 104 Motor-Operated Valve O NEB-74-191 49 Limitorque SMB-5T 105 Motor-operated Valve 9 NEB-74-192 49 Limitorque t_ SMB-4 106 Motor-operated Valve O NEB-74-202 49 Limitorque SMB-4 107 Differential Pressure 4 NEB-74-198 48, 53 _ Switch Indicator Barton 289A 108 Pump Motor 5 NEB-74-211 None GE 2 NEB-74-212 5K6348xC23A 6 d-B- - s
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TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION - NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 109 Flow Switch 4 NEB-75-232 53, 54 Barton 289 110 Pump Motor 4 NEB-75-238 None GE SK6336xC198A 3 NEB-750238A None 111 Solenoid Valve 8 NEB-76-240 42 ASCO 8 NEB-76-241 42 X8315 C28 112 Hydrogen Element 0 NEB-76-243 None GE 47E226428G2 113 Level Switch 0 NEB-77-244 None GEMS XM-36425 114 Solenoid Valve 6 NEB-77-249 Nons Versa VSG-3521 115 Limit Switch 6 NEB-77-249A None Micro Switch 6 NEB-77-249A None B2E6-2RN 116 Level Switch 2 NED-77-250 None Autocon 5 NEB-77-251 None M-4 4 NEB-77-260 None 4 NEB-77-261 None 117 Temperature Element 0 NEB-77-252 None Thermo-Elect 4 NEB-77-259 None B7582-1 118 Level Switch 13 NEB-78-262 None Meletron 9241-6SS10A 119 Level Switch 13 NEB-78-265 44, 45 3arksdale D2H-M18SS 120 Solenoid Valve 8 NEB-85-267 None '
.<f35CO 8 NEB-85-268 None
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TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 121 Position Switch 8 NEB-85-272 None Micro Switch 8 NEB-85-273 None B E6-2RN 122 Solenoid Valve 8 NEB-85-274 None ASCO BVA-90-405-2A 123 Level Switch 8 NEB-85-276 None Robertshaw SL-305-E3-X 124 Ion Chamber 8 NEB-90-279 None GE 7 NEB-90-280 None 237X731G001 8 NEB-90-281 None 7 NE3-90-282 None i 125 Sensor and Converter 15 NEB-90-283 None GE 15 NEB-90-284 None
~~
194X927G014,12 126 Fission Product 0 NEB-90-286 None Monitor 6 ND-90-286 A None GE
- No Model No.
< 127 TIP Valve Assembly 8 NES-NM-287 None l GE j 136B1302G2 l 128 Motor Control Center 12 EEB-APS-0010 None International Switchboard Corp. No Model No. 129 Motor Control ': enter 9 EEB-APS-0008 None GE 8 EEB-APS-0210 None j 7700 Series _. 130 Motor Generator 12 EEB-APf-0195 59 Louis Allis Co. 13 EEB-APS-0196 59 8-127033 13 EEB-APS-0197 59 12 EEB-APS-0198 59 i 6
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TER-C5417-3 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION - NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 131 Transformer 12 EEB-APS-0205 None GE 12 EEB-APS-0206 None 4160 V - 480 V 13 EEB-APS-0208 None No Model No. 13 2 Colenoid Valve O EEB-1-1001 None Target Rock 0 EEB-1-1002 None 1/2 SMS-A-01-1 13 3 Junction Box Various 19, 20 13 4 Terminal Block 4 EEB-77-0065 24, 25, 26 GE 13 EEB-78-0061 24, 25, 26 EB-5 CR15182 8 EEB-84-0057 24, 25, 26 8 EEB-84-0060 24, 25, 26 12 EEB-63-0068 24, 25, 26 - Various EEB-64-0067 24, 25, 26 6 EEB-76-0078 24, 25, 26 , 8 EEB-90-0159 24, 25, 26 9 EEB-67-0043 24, 25, 26 7 EEB-01-0103 24, 25, 26 0 EEB-01-0104 24, 25, 26 8 EEB-23-0038 24, 25, 26 0 EEB-32-0014 24, 25, 26 0 EEB-43-0030 24, 25, 26 various EEB-74-0393 24, 25, 26 Various EEB-74-0394 24, 25, 26 Vatious EEB-73-0128 24, 25, 26 Various EEB-75-0146 24, 25, 26 Various EEB-69-0107 24, 25, 26 - Various EEB-71-0251 24, 25, 26 l 135 Electrical 0 EEB-76-0048 22 Penetration Assembly 0 EEB-76-0049 22 GE O EEB-01-00 94 22 Series 100 0 EEB-68-0031 22 0 EEB-68-0034 22 - 0 EEB-69-0060 22 l 0 EEB-64-0026 22 ' O EEB-71-0243 22 . 0 EEB-73-013 3 22 0 EEB-74-0364 22 6
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- e6 TER-C5417-5 EQUIPMENT LICENSEE ITEM ITEM ~"BMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 136 Electrical 0 E~'-71-0245 23 Penetration Assemoly GE NSO4 13 7 Electrical O EEB-NM-0015 14 Penetration Assembly 0 EEB *;n-0016 14 Physical Sciences O EF' NM-0017 14 Ccep. 0 E s-NM-0018 14 PSC P/N 2019C 0 EEB-NM-0019 14 0 EEB-NM-0020 14 0 ZEB-NM-0021 14 13 8 Electrical Penetration 0 EEB-01-0091 21 Assembly 0 EEB-01-0092 21
- Physical Sciences O EEB-01-009 3 21 Corp. O EEB-43-0003 21 r^
PSC P/N 2022C 0 EEB-76-0044 21 0 EEB-64-0059 21 O EEB-69-0061 21 0 EEB-73-013 2 21 0 EEB-74-0365 21 0 EEB-74-036C 21 0 EEB-71-0244 21 0 EEB-68-0032 21 0 EEB-68-0033 21
, 139 Switches 4 EEB-77-0068 61 l
GE and Cutler Hammer 0 EEB-74-0401 61 l GE-CR2940 8 EEB-23-0041 61 ( CH-10250T 7 EEB-01-0108 61 EEB-75-0149 Various 61 various EEB-73-0137 61 various EEB-74-0398 61 11 EEB-69-0109 61 Various EEB-71-0254 61
~~
140 Cable Various Numerous (See Manufacturers , E List) d' I$s: .
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TER-C5417-5 APPENDIX C - SAFETY SYSTEMS FOR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED The Licensee has submitted a list of safety-related systems that must function in order to :nitigate the consequences of a design basis accident. This infor: nation was submitted in response to IE Bulletin 79-01B and was included in the Licensee's October 31, 1980 response. e 9 f % I I se 6
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- . . - . , . ._ _ . - . . _ , . . _ - _ . . - - , , . ~ , . . , _ . , . . , _ _ - _ . _ . . . , , _ . - , _ . _ ,
TER-C5417-5 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 Costainment e Stanby Ca: 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 ! e Fuel Pool Cocling l o Containment Atacsphere Diluation e Control Rod Drive e Neutron Monitoring - e Radiation Monitoring e Auxiliary Power . O l C-2 *
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TER-C5417-5 l APPENDIX D - CABLE MANUFACTURERS LIST , 1. Brand-Rex i 2. Rome Cable ! 3. Cyprus
- 4. American Insulated Wire
- 5. Plastic Wire & Cable Corp.
- 6. General O bie
- 7. Continental Wire & Cable S. PWC
- 9. Tamaqua
- 10. Boston Insulated Wire
- 11. Ckonite
- 12. RockbestCs
- 13. Belden Corp.
- 14. ITT Surp.
., 15. Sumitomo Shoji
- 16. Essex
- 17. Phelps Dodge
- 18. Triangle Conduit & Cable
- 19. GE Cable Corp.
- 20. Sies Electric
- 21. Graybar
- 22. Simplex Wire & Cable
- 23. Ti:nes Wire & Cable
- 24. Cearborn Wire
- 25. Alpha Wire Corp.
- 26. Belden
- 27. Consolidated Wire
- 28. Anaconda
- 29. Collyer Insulated Wire 6
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TER-C5417-5 APPENDIX E - EQUIPMENT ITEM CRCSS-REFERENCE FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM NO. SECTION 1 4.5.2.1 I 2 4.5.2.1 3 4.5.2.2 4 4.5.2.3 5 4.5.2.4 6 4.5.2.5 7 4.5.2.6 8 4.5.2.7 9 4.5.2.8 10 4.5.2.8
~
11 4.5.2.9 12 4.5.2.9 13 4.5.2.10 14 4.5.2.9 15 4.5.2.11 16 4.5.2.12 17 4.5.2.13 13 4.5.2.14 19 4.5.2.15
- 20 4.5.2.16 21 4.5.2.17 22 4.5.2.18 23 4.6.1 24 4.5.2.67
! 25 4.5.2.67 26 4.5.2.19 27 4.3.1.1 28 4.5.2.20 29 4.5.2.21 30 4.5.2.22 31 4.5.2.23 32 4.6.2 33 4.5.2.24 i 34 4.5.2.25 35 4.5.2.24 l l 36 4.5.2.63 37 4.6.3 6 i
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4 TER-C5417-5 FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM NO._ SECTION 38 4.6.4 39 4.6.3 40 4.5.2.26 41 4.6.32 42 4.6.5 43 4.6.35 44 4.5.2.66 45 4.5.2.65 46 4.5.2.65 47 4.6.6 43 4.6.6 49 4.6.7 , 50 4.6.7 51 4.5.2.27 52 4.6.8 53 4.6.8 54 4.6.3 55 4.6.9 56 4.5.2.28 57 4.6.11 58 4.6.10 59 4.6.10
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TER-C5417-5 FINAL TECHNIO L EQUIPMENT EVALUATION REPORT ITEM NO. SECTION 76 4.5.2.33 ' 77 4.6.33 78 4.6.14 F 79 4.5.2.34 80 4.5.2.35 81 4.6.15 82 4.5.2.36 83 4.6.36 84 4.6.10 85 4.6.10 86 4.6.10 87 4.6.10 38 4.5.2.37 89 4.5.2.37 90 4.6.38 91 4.6.16 92 4.6.16 93 4.5.2.38 94 4.6.17 95 4.5.2.39 96 4.6.18 97 4.5.2.40 98 4.6.10 99 4.5.2.;3 100 4.6.19 101 4.6.20 102 4.5.2.41 103 4.6.21 104 4.6.22 105 4.6.23 106 4.6.22 107 4.6.24 108 4.5.2.42 109 4.6.25
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TER-C5417-5 FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM NO. SECTION 114 4.5.2.46 115 4.5.2.47 116 4.5.2.48 117 4.5.2.49 118 4.5.2.50 - 119 4.6.27 j L20 4.5.2.51 121 4.5.2.52 ' 122 4.5.2.53 123 4.5.2.54 124 4.5.2.55 125 4.5.2.56 125 4.5.2.57 _2 127 4.5.2.53 128 4.5.2.59 1 129 4.5.2.60 13 0 4.6.28 131 4.5.2.61 4 132 4.5.2.62 11_3 4.7.1 , 134 4.6.29 13 5 4.5.2.68 136 4.3.1.2 ' 13 7 4.6.30 138 4.3.1.3 13 9 4.6.31 140 4.7.2 i s 6
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