Text

Equipment Environ Qualification,Quad Cities Unit 1, Final Technical Evaluation Rept
	ML20126M364
Person / Time
Site:	Quad Cities
Issue date:	06/11/1981
From:	Crane C; FRANKLIN INSTITUTE
To:	;
Shared Package
ML20126M363	List: ML20126M358; ML20126M364;
References
	IEB-79-01B, TER-C5417-012, NUDOCS 8106170080
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O TECHNICAL EVALUATION REPORT EQUIPMENT ENVIRONMENTAL QU ALIFICATION COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR POWER STATION UNIT 1 emm NRC OCCKET NO. 50-254 NRC TAC NO. 42478 FRC PROJECT C5417 i

FRC TASK 12

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EG&G ICAHO, NC. SUSCCNTRACT NO. X 7615 i

Prepared by Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 FRC Group t.eader: C. J. Crane Prepared for EG&G Idaho, Inc.

Idaho Falls, Idaho 83401 June 11, 1981 This report was prepared as an account of ' work performed under a subcontract from EG&G Idaho, Inc., a prime contractor to the United States Department of Energy. Neither EG&G nor the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, or any information, apparatus, product or process dis.

closed in this report, or represents that its use by such third party would nct nfrtnge privately owned rignts.

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NOO Franklin Research Center A Divisien cf The Franklin Institute The Benprrun Fannhn Pertway. PMs., Pa. 19103(215) 4 8 1000 83061 70ON

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TECHNICAL EVALUATION REPORT EQUIPMENT ENVIRONMENTAL QU ALIFICATION COMMONWEALTH EDISON CCMPANY OUAB CITIES NUCLEAR POWER STATION UNIT 1 1

NRC OCCKET NO. 50-254 FRC PFCJECT C5417 NRC TAC NO. 42478 y

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EG&G (CAHO,INC SUSCCNTRACT NC. X 7515 Prepared by Franklin Research Center The Parkway at Twentieth Street Philadelphia, P A 19103 FRC Group Leadar: C. J. Crane Prepared for EG&G fdaho,Inc.

Idaho Falls, Idaho 83401 June 11, 1931 l

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l This report was prepared as an account of work performed under a subcontract from EG&G Idaho, Inc., a prime contractor to the United States Department of Energy, Neither EG&G nor the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any regal liability or responsibility for any third party's use, or the results cf such use, or any information, apparatus, pr0 duct or process dis-closed in this re0crt. cr recresents that its use by sucn thirc carty sculd n0t mfrtnge Orivately Owned rignts.

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TER-C5417-12 CCNTENTS Section Title Page 1

I}CRCDUCTICN.

1-1 1.1 Purpose of the Evaluation.

1-1 1.2 Generic Issue Background 1-1 1.3 Scepe of the Evaluatien 1-7 2

NRC CR:"'IRIA FCR EW!RCNME! CAL QUAL ?! CATION.

2-1 2.1 Criteria Provided by the NBC 2-1 2.2 Staff Positiens and Supplemental Criteria.

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

2-1 2.2.2 Submergence.

2-2 2.2.3 Equipment Lccated in Areas Normally Maintained at Recm Conditiens.

2-2 2.2.4 Simulated Service Conditions and Test Ouration.

2-3 2.2.5 Deferment of qualificatien Review 2-3 2.2.6 Test Sequence 2-4 2.2.7 Radiation 2-4 3

ME'.'HCDCLCGY USED BY FRC.

3-1 4

TECHNICAL EVALCATICN.

4-1 4.1 Methodology Used by the Licensee 4-1 l

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. 4.1.1 Ccmpleteness of Equipment List 4-1 l

l 4.1.2 Environmental Service Conditions 4-2 4.1.3 Aging and qualified Life 4-6 4.2 NRC Category I Equipment That Satisfies the General Requirements of the DCR Guidelines and IE Sulletin 79-013.

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CCNTENTS Section Title Page 4.3 NRC Category II Equipment That the Licensee Will Modify or Relocate 4-11 4.4 NRC Category III Equipment That the Licensee Believes To Be Exempt Fr Qualification 4-13 4.3 NBC Category IV Equipment That Has Qualification Testing 4-14 Scheduled but Not Completed.

4.6 NBC Category V Equipment That Coes Not Satisfy One or Mere of the General Requirements of the DCR Guidelines and IE Sulletin 79-013.

4-13 4.7 NFC Categcry VI Equipment for Which Qualification Is Ceferred 4-43 4.3 Su= nary of the Evaluatien 4-30 5

CCICLUSICNS.

5-1 6

REFERENCES 6-1 APPENDIX A - ENVIRCNMENTE SERVICE CONDITICNS APPENDIX 3 - LISTING CF SAFETY-REI.ATED ELECTRICE Z:QUIPMENT APPENDIX C - SAFETY SYSTEMS FOR '4ICH ENVIRCNMENTE QUEIFICATICN IS TO BE ADDRESSED i

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INTRODUCTION 1.1 PURPCSE OF *'HE EVA"UATICH The NRC Office of' Inspection and Enforcement (IE) issued Bulletin 79-018,

" Environmental Qualification of Class 1E quipmenta in January 1980. This Bulletin required the Licensee to perform a detailed evaluation of the envircnmental qualification of Class 1E electrical equipment required to function under postulated accident cenditions and to submit a repcet en this action.

"'he cojectives of the NPC Equipment Environmental Qualification Review program are to evaluate nuclear pcwer plant safety-related electrical equipment in accordance with criteria established by the NPC and to identify (1) equipment wncse qualification documentation is adequate, i.e.,

sutstantiates that the equipment is capaole'ef performing its specified design basis safety function when it is expcsed to a harsh environment and (2) equipment whose qualificatien documentatien is deficient, i.e., does not give reasonable assurance that the equipment is capable of performing its specified

. safety function.

To meet the overall pregram goals, the objective of this Tecnnical Evaluation Report is to review the Licensee's submittals to determine if the Licensee reviewed its safety-related electrical equipment for environmental qualification. in accordance with the DOR Guidelines and NUREG-0588 as required by IE Bulletin 79-01B.

The NRC will perform an audit of the qualification documentation references as part of its safety evaluation pecgram.

If discrepancies are found, the audit will be extended.

1.; OENERIC ISSUE 2ACKGECUND Safety-related electrical equipment must be capable of performing design saferv functions under all ncemal, abncemal, and accident etnditiens. Cf particular rencern is the assurance that equipment will demain cperacle during 1-1

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TER-C5 417-12 and following exposure to the harsh environmental conditions (i.e.,

temperature, pressure, humidity (s team), chemical sprays, radiation, and submergence) imposed as a result of a design basis accident. These harsh environments are generally defined by the limiting conditions resulting from the ecmplete spectrum of postulated break sizes, break locations, and single failures consequent to a less-of-coolant accident (I CCA), main steam line break (MSI.3 ) inside the reactor containment, or a high energy line break (HEI.3) outside reactor containment (such as a mt in 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 performance, thereoy establishing assurance that the potential for ccmmon-ecde failure is minimized.

Qualification criteria applied during the licensing of the older nuclear pcwer. plants have been mcdified over the years, and specific industry standards concerning qualification have been revised as the design of reactor systems has changed and as regulatory and operating experience has accumulated. Examples of such standards are IEEE Standards 279-71, 3 3-74, 383-74, 317-76, 334-74, 331-77, 382-80, and 627-80.

NRC NUREG documents 0 413 and 0538 have caen deveicped to address this tcpic. In particular, NUREC-0583 (published for comment in December 1979) formally presented the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment in the resolution of General achnical Activity A-24, " Qualification of Class IE Safety Related Iquipment." The positions documented therein are applicable to plants that are or will be in the construction permit or operating license review process.

Although qualification standards and regulatory requirements have undergone considerable development, all of the currently operating nuclear power plants are required to comply with 10CTR50, Appendix A, General Design criteria fer Nuclear Pcwer Plants,Section I, criterien 4.

Tnis criterion states in part that " structures, systems and ccmponents important to safety shall be designed to acccmmodate the ef fects of and to ::e compatab'e with tne envircnmental conditions asscciated with normal operation, maintenance, testing and postulated accidents, including icss-of-ccolint accidents."

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. Qualification requirements 'are also emcodied in 10CFRSO Appendix A, General Cesign 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 I

inside'as'well as outside containment.

The NRC staf f 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 staf f has also used a variety'of methods to assure that these general require-ments are met for electrical safety-related equipment.

n the oldest plants, qualification was based on the fact that electrical ccmponents were' of hign industrial quality. Af ter 1971, qualification was judged en the basis of IEZZ 5td 323-71; hewever, no regulatory guide was issued adepting this standard.

Fer plants whose' Safety Ivaluation Repcets were issued after July 1, 1974, the Commission issued Regulatory Guide 1.89, which in mest respects adopted the most recent standard, II: :: Std 323-74.

In 1977, the NPC staff instituted the Systematic Evaluation Program (SI?)

to determine the degree to which the older operating nuclear pcwer plants deviated from current licensing criteria. The sucject of electrical equipment environmental. qualification.(SEP Tepic I!!-12) was selected for accelerated evaluation as part of this program. Seismic qualification of equipment was to be addressed as a separate SEP topic.

In Iecember 197 7, the NRC issued a generic letter to all SEP plant licensees requesting that they determine the adequacy of existing equipment qualification documentation.

Preliminary NRC review of licensee responses led to the preparation of NUREG-0458, an interim NRC assessment of the environmental qualification of electrical equipment. This document concluded that "no significant safety deficiencies requiring immediate remedial actions were identified." However, it was recc= mended that additional effort should :e fevoted c: examining.ne I

installation and envirenmental qualification documentation of specific electrical equipment in all operating reactors.

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TER-CS417-12 Cn May 31, 197 9, - the NRC Office of Inspection and Enforcement issued IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical i

Equipment at Nuclear Power Plants," which required all licensees of operating plants. (except those included in the SEP program) to examine their installed safety-related electrical equipment and ensure appropriate cualification documentation for equipment function under postulated accident conditiens.

L Subsequently, on.mbruary 8,1979, the NRC Of fice of Inspection and Enforce-ment issued IE Bulletin 79-01, which was intended to raise the status of IE

- Circular 79-08 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.

Tne review of the licensee responses indicated certain deficiencies in the scope of equipment addressed, definition of harsh envircnments, and adequacy of support documentation.

It oecame apparent that generic criteria were needed to evaluate the electrical equipment environmental qualification for both SEP and nco-SEP cperating plants. Therefore, during the second half of 1979, the Division of Operating Reactors (DCR) of the NRC issued internally a dccument entitled " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors' (29].*

(The document is hereaf ter referred to as the " DOR Guidelines.') The document was prepared as a screening standard for reviewing all operating plants, including SEP plants. It was originally intended that the licensees would evaluate their qualification documentation in accordance with the DCR Guidelines. Hcwever, initial NRC review of this documentation, which was compiled to support licensee submittals, revealed the need for obtaining independent evaluations and -for accelerating the qualification review program, f

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d' TER-C5417-12 Cn January 14, 1980, the NRC Of fice of Inspection and Enforcement issued the DCR 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 f acilities, i

excluding the 11 facilities undergoing the SEP review. This Bulletin cited the CCR Guidelines as the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification. The scope of the review was expanded to include high energy line breaks (inside and cutside containment) in addition to equipment aging and submergence. The NRC advised the licensees that the criteria contained in the OCR Guidelines would be used in' its review of licensee submittals; proclems arising frem this review wculd be resolved using NUREG-0588 as a guide.

In early rebruary 1980, the NRC decided that Indian Point Units 2 and 3 and Zion Units 1 and 2 anould be included witnin SEP Tepic III-10 for the purpose of equipment environmental qualification raview.

On February 21, 1980, the NPC and representatives of the SEP Plant Owners Croup held an Open meeting at NRC headquarters to discuss an accelerated review pregram in accordance with the OCR screening guidelines. Re pr e sen-tatives of the Indian Point Units and Fion Station also attended this mee ting. The NRC formally issued to all licensees represented at the meeting the DCR Guidelines document which included a second document, " Guidelines for Identification of That safety Equipment of SEP Cperating Reactors for Which Environmental qualification Is to Be Addressed" (29], 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 NRC Office of Inspection and Enforcement formed a task force including a principal reviewer in each region and a tas< 1eader frem headquarters. The regicnal memcers were assigned respcnsibility for the l

technical review of the licensees' responses to :E Bulletin 79-013, and the L

tasx leader was assigned responsibility f:e tne everall ::cedination of :ne l

review ef fort with NRC staf f to assure overall censistency.

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TER-C5417-12 reviewers held meetings with the licensees in their respective regions, wnich resulted in staf f positions being issued in a supplement to IE Bulletin 79-018 dated Mbruary 29, 1980.

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

On May 27, 1980, the NRC issued Memorandum and Ceder CLI-80-21 (3ll),

specifying that licensees and applicants must meet the requirements set forth in the CCR Guidelines and NUREG-0588 regarding environmental qualificatien of safety-related electrical equipment in order to satisfy 10CFR50, Appendix A, General Design Criteria,Section I, Criterion 4.

This Crder also establisned that the Safety Evaluation Reports on this subject, to be prepared by the NRC staf f, must be. issued on February 1,1981 and that all subsequent actions to be taken by licensees to achieve full ccmpliance with the COR Guidelines or NtTREG-0588 must be ecmpleted no later enan June 30, 1982.

O.e staf f held regional meetings with the licensees and interested parties during the week of July 13, 1980. Tne staff issued a second supplement to II sulletin 79-013, a respense to significant questions raised during the public meetings, and two Ceders. The Crder, dated May 30, 1980, required the licensees to ecmply with the previously issued Ccmmission Memorandum and Crder of May 27, 1980 (CLI-80-21). The above Crders required the licensees to complete the tasks identified in II Bulletin 79-013 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 Mbruary 29, 1980s and the second and third supplements to IE Sulletin 79-OlB, highlighting the staf f positions af fecting the licensees' j

responses, were issued en Septer,ber 29 and Cetecer 24, 1980, respectively.

In Occceer 1980, EG&G ldaho, :nc. awarded Tran<lin Resear:n Center IFRC) a contract to provide assistance in the equipment environmental qualification review for 13 of the plants whose licensees responded to E Bulletin 79-013.

TRC was to evaluate the *icensees' equipment envircnmental qualification l

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1.3 SCOPE OF THE EVALUATICN Environmental qualification of safety-related electrical equipment was selected by the NRC for accelerated review. Tnerefore, the scope of this report is limited to equipment that must function to mitigate the consequences of a LCCA or HELB and whose environment is adversely affected by these In addition, IE Bulletin 79-013 requires environmental qualification events.

in acccedance with the "CR Guidelines cc NUREG-0588 for all safety-related electrical equipment exposed to a harsh envirenment. Marsh envircements include the limiting conditions resulting from (i) the entire spectrum of postulated line breaks resulting frem a LOCA cr HE13 inside and outside containment and (ii) radiation from fluids that are recirculated frem insido centainment to acecmplish long-term ecoling subsequent to an accident.

Oualificatien aspec s ne.t included within the secpe of this evaluatien arer o seismic qualificaticn equipment protection against natural pher.cmena o

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

o and frequency deviations) o equipment located where it is sucject to cutdece envirenments equipment protection against fire ha:ards o

equipment protection against missiles.

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2.

NRC CRITERIA NR ENVIRCNMENTAL QUALIFICATICN 2.1 CRITERI A PRCVIDED BY THE NRC The DCR screening guidelines used by FRC to evaluate the electrical equipment environmental qualification programs were:

o aGuidelines for Evaluating Environmental qualification of Class IE Electrical Equipment in Operating aeactors (29]

a o " Guidelines for Identification of mat safety Equipment of SEP Cperating Reac:ces for Whien Environmental qualification Is T: 3e Addressed" (29]

o NCREG-0533, " Interim Staff ;csition en Environmental qualificatien of Safety-Related Electrical quipment" (34).

These guidelines were issued for implementation to all licensees by the NRC in February 1980.

2.2 STAFF PCSITICNS AND SUPPLDtENTAL CRITERIA 3e NRC identified the following staf f positions and supplemental criteria to be used in conjunction with the referenced DCR screening guidelines.

2.2.1 SERVICE CCNDITIONS INSIDE CCNTAINMENT PCR A ", CSS-CF-CCCLANT ACCIDENT (DCR Guidelines section 4.1) i i

Mr pressurized water reacters (PWRs ), the DCR Guidelines state tnat the l

containment temperature and pressure conditions as a function of time snculd be based on the mcst recent NRC-approved service ccnditions specified in the Final Safety Analysis Report (FSAR) or other licensee documentation.

In the specific case of pressure-suppression type centainments, the f olicwing minimum hign temperature conditions may ce used (1) boiling water reaccce (3WR) drywells -- 340*F for 6 hcurs and (2) PWR ice cendenser icwer compartments --

340*F for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . As stated in Supplement 2 to II Bulletin 79-01B (30),

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.ieu o f a plan t-specific profile, provided tha t expected pressure and humidity cceditiens as a f uncticn of time are acccunted for. "

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TER-C5417-12 Service conditions should bound these expected for coolant and steam line breaks inside containment with due consideration given to analytical uncertainties. The steam line' break condition should include superheated

. conditions, the peak temperature, and subsequent temperature / pressure profiles as functions of time.

If containment spray. is to be used, the impact of the spray on required equipment should be assessed.

We adequacy of a plant-specific profile depends on the assumptions and design considerations at the time the profiles were developed. The DCR Guidelines and NUREG-0588 provide guidance and considerations required to determine if the calculated plant-specific temperature / pressure profiles enecmpass the LCCA and HELS accidents inside containment.

2.2.2 SUBMERGENCE (CCR Guidelines Section 4.1,- Subitem 3; and Section 4.3.2, Suc: tem 3)

Equipment submergence (inside or outside containment) shculd be addressed where the possibility exists that suomergence of equipment may result from HELas or other postulated cccurrences. Supplement 2 to IE Bulletin 79-013

[30] provides the following additlenal criterien If the equipment sataafies the guidance and other requirements of the OCR Guidelines of NUREG-0588 for the LCCA and HELS accidents, and the licensee demonstrates that its failure will not adversely affect any safety-related function er mislead tne operator af ter sucmergence, the equipment can be censidered exempt fecm the' submergence portion of the qualification requirements.

2.2.3 EQUIPMENT LOCA*ED IN AREAS NCRMALLY MAINTAINED AT RCCM CONDITIONS (DOR Guidelines Section 4.3.3)

Supplement 2 of IE Bu11etin,79-01B (30] permits deferment of the review of environmental qualification for all saf aty-related equipment items located in plant areas where the' equipment is not exposed to the direct ef fects of a HEL3 ce to nuc' ear radiation emanating from circulation of fluids centaining i

radicactivi substances. At the licensee'4 cption, the review may be deferred until afte? Feb rua ry 1, 19 81.

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TER-C5417-12 By June 30, 1982, all safety-related electrical equipment potentially exposed to a harsh environment in nuclear generating stations licensed to operate en 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 shutdewn condition and to mitigate the censequences of the accident. It is the responsibility of the licensee to evaluate the qualification of safety-related electrical equipment to functicn in environmental extremes not associated with accident conditions and to document it in a form that will be available for the NRC to audit, qualificatien to assure functioning in mild environments must be ecmpleted by June 30, 1982.

2.2.4.SIMCIATID SERVICE CONDITICNS AND TIST OURATION (OCR Guidelines Section 5.2.1)

The Guidelines require that the test chamber environment envelop the required service conditiens for a time equal to the period from the initiation of the accident until the service conditions return to ncemal. Supplement 2 to IE 3ulletin 79-013 (30] provides the fo11 ewing additional criterien:

"2quipment designed to perform its safety-related function within a sncet time into an event must be qualified for a period of at least i hcur in excess of the time assumed in the accident analysis. The staff has indicated that time is the most significant facter 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 accidenet 'small and large breaks) bounded by the single test."

2.2.5 DEFERMENT CF QUAI.IFICATICN Rr/IEW Supplement 3 to IE Bulletin 79-01B (31) permits the submittal of qualification documentation regarding TMI Action Plan equipment and the equipment required to achieve and maintain a cold shutdewn conditien to be delayed as fo11ews:

ualification information for installed TMI Acticn Plan equipment o

must be submitted by February 1, 1981.

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4 TER-C5417-12 Qualification information for. future mI Action Plan equipment (ref.

o NUREG-0737, when issued), which requires NRC pr e-implementation i

review,.must be submitted with the pre-implementation review data.

o Qualification information for mI Action Plan equipment currently under NRC review should be submitted as soon as possible.

Qualification information for-mI Action Plan equipment not yet o

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

o The qualificacion information for equipment required to achieve and maintain a cold Shutdown condition... will' not be submitted later than February 1,1981."

2.2.6 TEST SEQUENCE (DCR Guidelines Section 5.2.3) l

.Suppiement 2.to IE Sulletin 79-013 (30] provides the fo11cwing additional criteria:

" Sequential testing requirements are specified in NUREG-0588 and the OCR Guidelines.. Licensees must follow tne test requirementa of the applicaole document.

1.

If the test has been ecmpleted without aging in sequence, justification for such a deviation must ce submitted.

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

3.

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

2.2.7 RADIATICN (DCR Guidelines Sections 4.1. 2, 4. 2. 2, and 4. 3. 2, Subitem 2)

Supplement 2 to II Bulletin 79-01B (30]. provides the following additional. criteria a3cth the OCR Guidelines and NUREG-0588 are similar in that tney previde the methods for determining the radiation source term when censidering l

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t TER-C5417-12 LTA events inside containment (100% noole gases /50% icdine/it partie-ulates). These methods consider /che radiation source term resulting from an event which completely depressuri es the primary system and releases the source term inventory to the containment.

NUREG-0578 provides the radiation source term to be used fer determining tne qualification deses for equipment in close pecximity to recirculating fluid systems inside and outside'of containment as a result of LCCA.

This method censiders a ICCA 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-LCCA events both inside and outside containment (10% nccle gases /10% iodine /0% particulates).

When developing radiation source terms for equipment qualification, the Licensee must ensure consideration is given to those events wcich provide the most beunding conditions. Se following taole summarizes these censideratiens:

LCCA Mon-LCCA REL3 Cutside Centainment NUREG-057 8 NCPIG-058 8 (100/50/1 (10/10/0 i n RCS ) ( * ]

in RCS)

Inside Centainment Larger of NUP2G-0588 NUREG-0588 (100/50/1 (10/10/0 in containment) in RCS) or NUREG-0578 (100/50/1

^

in RCS)

Gamma equivalents may be used when consideration 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 safety-related equipment. Cesium 137 may also be used."

3e numcers in parentheses represent % ncble gases /1 icdine/% particulates.

RCS means reactor coolant system.

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3.

METHODCLCGY USED BY F1C

' /

The Licensee, Ccmmonwealth Edison Ccmpany, identified an extensive list of safety-related electrical equipment

items in various locations of Quad Cities Nuclear Power Station Unit 1 in its submittals to the NRC.

FRC analyzed the Licensee's listing and grouped all identical or generically identical equipment items located within plant areas that are exposed to the same environmental service conditions. This analysis resulted in a reduced listing containing 148 different equipment items tnat formed the basis fer the review. In this repert, the term " equipment item" refers to a specific type of electrical equipment, designated by manuf acturer and medel, which is representative of all identical or generically identical equipment in a plant area exposed to the same enviccamental service cenditions (e.g., Flew Transmitter, Fiscner & Pceter, Mcdel 1032496, iccated within centainment).

Appendli A contains the environmental service cenditions for each locatien,

. Appendix 3 contains the tabulation of the equipment item groupings (the taoulatien 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 as being essential to safety.

I2 Bulletin 79-013 required the licensees to l

l o provide a master list that identifies the safety systems and Class 12 electrical equipment required to function during and subsequent to an accident and to maintain the plant in a safe condition identify the environmental service conditions o

>+

o identify the maximum submergence levels previde written evidence (System Ccmpenent Evaluatien '4cr< Sheetsi of e

the envircnmental qualificatien cf the equipment identiflad in the master list to demonstrate the espability of the equipment to function under postulated accident ccnditions l

l l

'In this report, the term *saf ety-related electrical equipment" refers tc the equipment defined by the NRC Guidelines ref erenced 'in 3ection 2.1.

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TER-CS417-12 o evaluate the qualification documentation using the CCR Guidelines and i

NUREG-0588 and, for equipment not having adequate qualification, to identify plans and schedules for establishing qualification o submit a Licensee Event Report (LER) for Class lE electrical equipment determined to be unqualified.

Tbe responses to IE aulletin 79-013 were requested by the NRC under provisions of 10CFR50.5 4 (f), " Conditions of Licenses," which requires the licensees to submit written statements, signed under oath.

To provide assurance that. the licensees satisfy the eequirements of IE Bulletin 79-Ola and to provide a basis for the NRC Safety Evaluation Report (SER), FRC was requested to develop this Technical Evaluation Report (TER) by assessing the l

licensees'. responses in relation to the general requirements of the CCR Guidelines as augmented by the supplements to II Sulletin 79-013.

The results and cenclusiens contained in this repcet are valid assuming that the ' Licensee 's analyses of test reports referenced in the Licensee sucmittal are correct. Review of test reports was not within the secpe of FRC's assignment.

However, the NRC staf f will audit selected analyses and test reports, incorporating the results of the reviews with the conclusions of the TERs, when develeping the plant-specific SERs.

Each equipment item listed in Appendix 3 was assigned to one of ene NRC categories defined in Table 3-1 af ter review of the associated System Compenent Ivaluation Work ' Sheet provided by the Licensee.

Topics not within the scope of the FRC evaluation ares o completeness of the licensee's listing of safety-related equipment o acceptability of licensee-provided environmental service conditions o - acceptability of licensee-stated positions concerning safety systems or component function o review and acceptability of qualification test reports and other qualification documentation.

The NRC Cf fice of Inspecticn and. Enf orcement estaclianed a program :

conduct an ensite verification inspection of selected Class II equipment to verify proper installation of equipment, everall interface integrity, iccation 3-2

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TER-C5417-12 with respect to flood level for equipment inside containment, and manufac-turer's nameplate data. The manufacturer and model number from the nameplate data were to be compared to information given in the System Component Evaluation Week Sheets of the licensee's report. The specific details of this site inspection are documented in an internal NRC Memorandum (351.

The information in this report will be used by the NRC in developing the plant-specific SER.

Table 3-1.

NRC CATEGCRIES AND OEFINITICNS o NRC Category I EQUI?ME!C THAT SATISFIES THE GENERAL REQUIREME:CS OF THE OCR GUIOELINES AND IE BULLETIN 79-013 This category includes equipment items for which the System Ctmponent Evaluatien WorX Sheets are judged to be in ecmpliance with IE Sulletin 79-013, its supplements, and tne genersi requirements of the OCR Guidelines.

For these equipment items, the licensee 's System Ccmponent Evaluatien Werk Sheets indicate that the requirements of II Sulletin 79-013 have been satisfied, assuming that tne licensee's analyses of qualification dccumentatien are ecmplete and ccerect.

o NRC Catego y II EQUIPME;C THAT THE LICENSEE WILL MCDITY CR RELCCATE This category includes equipment items that the licensee has stated will be modified ce relocated in order to ecmply with the OCR Cuidelines require-ments.

o NRC Category III EQUIPMENT THAT THE LICENSEE BELIEVES *O BE EXEMPT TRCM QUALIFICATICN This category includes equipment items that the licensee believes to be exempt from qualification on the basis that (1) the equipment does not provide a safety function (i.e., should not have been included in the master list of safety-related equipment submitted by the licensee), or (2) the specific safety-related function of the equipment can be acecmplished by seme other

-designated equipment that is fully qualified.

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4 TER-CS41'-12 Table 3-1 (Cont.)

(

o NRC Category IV EQU*PMENT THAT HAS QUALIFICATION TESTING SCHEDULED BUT NOT CCMPLETED This category includes equipment items that the licensee has determined to be deficient or inadequate with respect to qualificatien. Mcwever, the licensee has stated that the equipment item is seneduled to be tested by a designated date.

> NRC Category V EQUIPME!C THAT DCES NCT. SATISFY CNE OR MCRE CF THE GE!rl.RAL REQUID.E!CS OF THE DOR GUIDELINES AND IE SULLETIN 79-013 This category includes equipment items gudged to be deficient er l

inadequate with respect to the general requirements of the CCR Guidelines and l

IE Bulletin 79-013 based on a review of the licensee's System Component Evaluation Woek Sheets.

I o NRC Ca tsgery VI.

ECUIPME!C FCR WHICH CUALIFICATICN !S DEFERRED i

his category includes equipment items that have been addressed by the l

licensee in the equipment environmental qualification submittals; hewever, the i

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

acccedance with criteria presented in Sections 2.2.3 and 2.2.5 of tais l

repcet.

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6 TER-C5417-12 4.

TECHNICAL EVALUATION i

l General observations concerning the Licensee's approach to qualification are included in Section 4.1.-

Sections 4.2 through 4.7 identify the equipment items

placed in each of the major NRC qualification categories in accordance with FRC's technical evaluation of the Licensee's documentation. The results of the evaluation are summarized in Section 4.8.

4.1 ME'"BODCLOGY USED BY THE LICENSEE Tnis secticn includes observations concerning the Licensee's methodology and procedures, as described in Reference 33, for ccmplying with the requirements of IE Bulletin 79-01B.

4.1.1 COMPLETENESS CF EQUIPMEN'" LIST In Section 4.2 of Reference 33, the Licensee states l

The QCNPS FSAR and emergency procedures were reviewed to identify the engineered safety feature systems required to mitigate the consequences of the pcstulated accidents discussed in Section 4.1.

These systems are needed to achieve reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, and to prevent the release of radioactive materials into the environment in amounts in excess of the guidelines of 10 OTR 100.

FRC believes that the Licensee's approach is appropriate. However, the following situations may result in the need for the Licensee to increase the number of equipment items requiring full qualification because they are exposed to harsh environmental service conditions (see Section 4.1.2):

o Other HELE accidents may need to be considered.

n

In this repcrt, the term " equipment item" refers to a specific type of electrical equipment, designated by manufacturer and model, whien is representative of all identical or generically identical equipment in a plant area exposed to the same environmental conditions (e.g., Flow Transmitter, Fischer & Porter, Model 10B2496, located within containment).

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TER-C5417-12 o Temperature or nuclear radiation exr 'res may be more severe than assumed in this analysis because ast.ed operating time is not long enough, or other. assumptions did not conform to the Guidelinec requirements, o Equipment was assumed to be exempt from qualification.

The Licensee has not indicated that the submittal of qualification information for equipment installed in response to the TMI Action Plan and to accomplish cold shutdown has been deferred (see Section 2.2.5).

No equipment is specifically identified on the master list as being required for these J

purposes.

i 4.1.2 ENVIRCNMEW3L SERVICE CCNDITICNS l

4.1.2.1 GENEPAL CCMME'ITS In Section 4.1 of Reference 33, the Licencee states:

Where compenents, because of their location, could be subjected to differing environments for the varicus sccidents, the mest severe environmental conditions were utill:ed for qualification....Where qualification could not be demonstrated for the entire spectrum of conditions simultaneously, components were evaluated for the conditions associated with each individual accident. Environmental conditions are based on the specific accidents for which the components must function.

FRC concurs that this is the proper approach, but a review of the equipment data sheeta indicates that it was not always followed. Also, the Licensee of ten considered only the environment that exists during the first minute (more or less) of an accident, rather than a period of one hour plus expected operating time, as is required by the Guidelines and Supplement 2 to IE Bulletin 79-013.

The Licensee also describes the following approach to application of

)

design basis event (DBE) conditions to equipment:

C:mponents which are exposed to harsh environments during accidents for wnien they are not required to function do not require qualification for these environments. Where qualification testing is to be performed, testing will be performed for each postulated environment separately.

FRC censiders that all safety-related equipment having the potential for ecmmon-mode failures due to envircnmental stresses must'be qualified if any 4e 4-2

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4 l

TER-C5 417 -1.

such failure would adversely affect connected circuits. Equipment that has no active function during a DBE cannot be exempted from qualification for this reason only. In addition, qualification for a short operating period would not be sufficient if equipment failures occurring after a minimum required operating period would adversely affect connected circuits. FRC notes that short operating periods are described for some of the equipment listed in the l

Licensee's submittal. It is not obvious that the environments specified would remain as described if. the additional 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of operating time required by the Guidelines (see Section 2.2.4 of this report) were added to the stated 1

I operating time. For many equipment items, the environmental service conditions during the first hour following an accident are much more severe than those listed by the Licensee (for the first minute) as requirements for which qualification must be demonstrated.

4.1.2.2 TEMPERAT*JFI/ PRESSURE /HtHIDI"'Y The Licensee states the following:

Inside the Drywell J

For the LOCA/EELB inside the etntainment, worst case environmental conditions are established by the LOCA resulting from a double-ended recirculation line break.

Outside the Drywell, Subject to HELB

- For a HELB outside the containment, Special Report No.12 identifies the l

high energy lines and the location of postulated breaks.

Nonharsh Areas Plant areac which are not covered in the above referenced Appendix C l

tables are considered nonharsh environmental areas with respect to HELB and post-LOCA radiation. These areas are either maintained in a suitable

(

environmental condition by safety-related heating, ventilating, and air

'conditiening [ EVAC) equipment, or are considered nenharsh because they are controlled to less than 104*F prior to the postulated accidents and are relatively large open areas with no large motors or other equivalent heat sources.

Where environmental conditiens are maintained by EVAC equipment, the HVAC system is provided with redundant components and/or bacxup power supply for reliable operation. Safety-related EVAC systems are provided for the following areas M _h 4~3 1 Franklin Researen C. enter l

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TER-C5417-12 l

l 1

a.

Control room, cable spreading room, battery rooms, computer room, and i

electrical equipment room b.

Standby diesel generator room c.

EPCI roca d.

Residual heat removal corner rooms l

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l e.

Core spray /RCIC corner rooms.

l Environments were considered nonharsh when the temperature was controlled l

to 104'F or less and the maximum integrated radiation dose was less than 4

5 x 10 rads. Areas where infrequent temperature extremes up to 120*F could occur, and temperature variatiens are not a result of the l

postulated accidents are considered as mild environments. Equipment in these areas functions normally in the 'same environment as postulated for post-accident conditions. For nenharsh and mild environments,

' qualification data is e st required.

FRC considers the Lisensee's approach to oe less conservative than j

permitted by the Guide 11aes 1.

Inside the Crywell. The Licensee has provided no information to

)

justify the statement that LOCA conditions are more severe than MSLB conditions. Supplement 2 to II Bulletin 79-01B requires that the Licensee consider a full spectrum of MSLB events (see Secticn 2.2.1 of this report).

2.

It is not clear that all HELB accidents have been considered, as is required by Supplement 2 to IE Bulletin 79-01B.

3.

Nonharsh Areas. Power plant equipment is usually designed for an j

environment of 50-104'F, 30-70% RH, and negligible radiation dese.

These operating ranges are not intended to indicate that the equipment is expected to fail if the temperature rises to 105'F, but rather that performance may be questionable if the temperature rises above 105'F and tne equipment is exposed to high humidity and l

radiation dose rates. For individual' equipment items with a maximum specified operating temperature of 120*F, FRC concurs that this is a

)

nonharsh environment, provided that the elevated temperature is not a result of a OBE.

{

l 4.1.2.3 NUCLEAR RADIATICN

, The Licensee states:

1 The QCNPS FSAR does not provide integrated radiation dese inside the drywell. Studies were performed to establish the integrated doses inside d&

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TER-C5417-12 the dryvell for a postulated LOCA. The integrated doses for i day, 30 days, and 1 year are provided in Appendix C [ Appendix A of this report).

The study methodology is described in Section 4.3.5.

Radiation doses are evaluated for actual equipment operating times.

Outside the Drywell, Post-LOCA Radiation Exposures Integrated doses have been calculated for areas outside the drywell.

Doses were established for 1 day, 30 days, and 1 year exposure.

4 Integrated doses of less than 5 x 10 rads during a component's service life are evaluated as nenharsh environmental conditions. Integrated doses of 5 x 104 rads and greater are evaluated as harsh environmental conditions. Appendix C provides integrated doses as a function of exposure time for areas containing components identified in Appendixes B.1 and B.2.

Radiation Study Methodology A rad'.ation study was performed to establish integrated deses to equipment following a pcstulated LO2A. The core fission product inventory was based on General Electric document " Radiation Source Information for N" REG-0578 Implementation, Computer Run Identified as SN"M3 7007S" dated Novemcer 1979.

The fission products were diluted into the appropriate fluid media as l

follows:

Fluid Noble Gases (%)

Halocens (%)

Other f%)

1 Suppression pool liquid 50 1

Reactor coolant liquid 100 50 1

Containment atmosphere 100 25 Reactor steam 100 25 Dilution of the fission products was considered using the fluid volume as the dilution media.

For components located inside the drywell, only gamma doses were

[

considered if the component was enclosed in a ncnorganic material (e.g.,

valve motor actuators in metal enclosures). The gamma dose was established based on immersion of the component in the gaseous drywell atmosphere for the time which the component must remain functional. For components enclosed in organic material (e.g., cable), beta radiatien doses were calculated. Where components enelesed in organic materials are installed in metal enclosures (e.g., cable in conduit or flex-conduit), beta radiation will be neglected. Inspections have been 4-5 L5nKhn,*Researen Center ACnwoona he prenamn menane

i TER-C5417-12 performed in the Quad Cities Unit 2 drywell, confirming that all equipment and cable is enclosed in nonorganic materials. Beta doses have therefore not been considered.

For components located outside the drywell, source terms were established for piping systems containing reactor steam, reactor coolant liquid, suppression pool liquid, and containment atmosphere. Since the piping wall thickness is sufficient to shield against beta radiation, only gamma radiation need be considered. Each Class 1E component was located with respect to the piping systems containing post-LOCA radioactive fluids.

The integrated dose was established based on the piping source term, distance from pipe to component, and component operating time Where a ecmponent could receive doses from more than one piping system, the doses were added to derive a total dose. Appendix C (Appendix A of this repcet), Table C-3, provides integrated deses as a function of time calculated 1 fact frem the greatest single source in each major plant area.

FRC notes that certain electronic equipment items, such as process parameter transmitters, may experience performance degradation at radiation dose levels lower than 50 krd. Appendix C to the Guidelines indicates radiation damage threshold values in the 1-to 10-krd range for seme electronic subcomponents. For other types of electcical equipment which do not contain electronic ecmpenents, noticeable degradation is not expected t'c cccur below 50 krd.

Use of actual operating times less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , as noted above and implemented throughout the equipment data sheets in Reference 33, to determine nuclear radiation dose levels for qualification does not comply with the Guidelines requirement that equipment subject to harsh environments be l

qualified for operating time plus 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Licensee should reevaluate the equipment radiation dose values (both inside and outside containment) to assure conformance with the DOR Guidelines requirements.

4.1.3 AGING AND QUALIFIED LIFE The *1censee states the fo11cwing:

In this study, the need to consider aging is based on the evaluation of ecmpenent design and applicatien. The effects of aging have also been considered based on Inclosure 4 to NRC Bulletin 79-013, " Guidelines for Ivaluating Invironmental Qualification of Class II,Ilectrical Iquipment in Cperating Reactors' and NUREG-0588, " Interim Staff Positten en Invircnmental qualificatien of Safety-Related 21ectrical Iquipment.

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4 4

TER-C5417-12 a.

Components Located Inside the Drywell The environmental conditions inside the drywell are defined as harsh (Sections 4.3.1 and 4.3.4) and hence the effects of thermal and radiation aging are evaluated for all Class 1E electrical components, b.

Components Located outside the Drywell 1.

Radiation Aging The components which are located outside the drywell and steam tunnel are exposed to insignificant amounts of radiation during normal operating conditions. The effects of radiation aging are therefore not considered in the qualification evaluation of these components.

Under postulated accident conditions some components may be 4

exposed to greater than 5 x 10 rads (integrated radiation dose). The effects of this short-ter= radiation exposure are considered in the qualification evaluation.

Components located inside the steam tunnel are evaluated for radiation aging.

2.

Thermal Aging Most areas outside the drywell are maintained in a suitable environmental condition by safety-related HVAC equipment. The normal maximum environmental design temperature is 104'F, which in this study is defined as a nenharsh environment (Section 4.3.4).

Thermal aging for these components is not required since the normal and post-accident environments are nenhext.h. In addition, temperature extremes (up to 120*F) may oe:ur in some j

plant areas. However, these conditions would result only during periods of extreme outdoor temperatures. Equipment designed and installed per industry standards would be capable of satisfactory operation without exhibiting age-related degradation due to these temperature extremes. Therefore, the ef f ects of thermal aging are not considered for components located in areas where the maximum ambient temperature is maintained at 120'F or below.

Review of the Licensee's System Component Evaluation Worx Sheets (SCEWS) indicates that the Licensee has net complied with the Guidelines requirements L%

4-7 Lv. 7. rankhn meseeren Center a cm a om. n.aon moan.

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TER-C5 417-12 concerning the evaluation of aging degradation and determination of qualified life. In most instances the SCZWS shows "Not Required" opposite the parameter

" Aging."

In other cases the parameters used in the pre-aging exposure of the qualification test program are shown, but there is no assessment of the adequacy of this expcsure or its interpretation in terms of qualified life.

The DOR Guidelines require that the Licensee:

o establish (numerically) the qualified life for all equipment items containing components susceptible to degradation due to heat and nuclear radiation o'

implement programs to review detailed surveillance and maintenance records to assure that equipment that exhibits age-related degrsdation is identified and replaced (or mcdified) as necessary.

Qualified life is the maximum time period of normal service, under specified conditions, for which it can be demenstrated that, at the end of the period, the equipment is still able to perform its specified safety function (s) for applicable design basis events. The qualified life may be contingent on implementation of a specified maintenance pregram. It is acceptable for - the qualified lif e of acme subcomponents of an equipment item to be less than the qualified life of the item itself, provided a program for

eplacemer.t of such components at intervals not exceeding their qualified lifetimes is specified and fulfilled. The qualified lif e of an equipment item may be changed during its installed lif e when justified by new information that permits a reanalysis of the qualification program.

Establishing the qualified life for equipment is a technically challenging task because of the paucity of information concerning degradation of materials and components under long-term exposure to the environmental service conditions in a nuclear power generating station. As is discussed more fully in Reference 36, with the possible exception of certain simple materials, there is no rigorous basis for estaclishing qualified lifetimes " e perieds approaching an installed lifetime of 43 years. Furtnermcre, additi:nal information regarding possible long-term synergistic effects of temperature, humidity, nuclear radiations, etc., is extremely limited.

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l TER-C5417-12 FR0 believes it is. fundamentally unsound to specify that the qualified life shall be 40 years (or any given value) for every safety-related equipment item in the plant, and then to attemot to prove that this " requirement" is met.

The Guidelines do not require that the qualified life be shown to be 40 1

l

_ years (or any other value). Rather, they require that each Licensee provide i.

evidence that the saf ety functions of the equipment in the plant can be 1

I performed adequately at all times. A conservative qualified life value should I

be established for each equipment item, and surveillance testing (necessary to monitor performance and identify degradation) should be performed to determine the need for maintenance or replacement. In this way, the qualified lif e value of an equipment item can be extended as new information is gained.

l The Licensee.should review the qualified life values and the present installed life of the equipment in accordance with the DOR Guidelines to determine a replacement schedule for each equipment item (or subcomponents thereof). These schedulos may te revised as new information becemes available.

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TER-C5 417-12 4.2 NRC Category I EQUIPMENT THAT SATISFIES THE GENERAL REQUIREMENTS CF THE DCR GUIDELINES AND IE BULLETIN 79-018 This category includes equipment items for which the System Component Evaluation Work Sheets are judged to be in compliance with IE Bulletin 79-01B,

- its-supplements, and the general requirements of the ' DOR Guidelines.

For these equipment items, the Licensee's System Component Evaluation Work Sheets indicate that the requirements of IE Bulletin 79-013 have been satisfied, assuming that the Licensee's analyses of qualification documentation are

- complete and correct.

For Quad Cities Nuclear Power Station Unit 1, no equipment is assigned to this category.

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1 TER-C5 417-12 4.3 NRC Category II EQUIPMENT THAT THE LICENSEE WILL MODITY OR RELOCATE This category includes equipment items that the Licensee has stated d

will be modified or relocated in order to comply with the DCR Guidelines requirements.

4.3.1 Equipment Item No. 99 480 V Motor Control Center Located in the Reactor Building General Electric Hodel 7700 Licensee reference not cited)

The Licensee maxes the following statements and commitments:

This equipment is suc]ected to harsh radiation only, and will be relocated and/or shielded to reduce the radiation exposure to a non-harsh level. Although qualification data is not availaole, continued operation is justified for the following reasons:

Radiation doses were calculated using conservative non-mechanistic l

a.

models. Meenanistic release models would result in radiation releases which occur several hours af ter the postulated accident.

Actual doses would therefore be less than those calculated using such censervative assumptions.

b.

Dese to this equipment is caused by only one loop of a redundant piping system. Operator actions taken to shut down redundant systems will further reduce exposure to this equipment.

i Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of tne SCR Guidelines are not satisfied. However, the Licensee stated that the equipment will be modified or relocated in order to achieve qualification.

1 4.3.2 Equipment Item No.108 DC Distribution Panel Located in the Reactor Building Cutler Hammer, Model Not Stated

(

l (Licensee ref erence not cited)

The Licensee stated:

This equipment is subjected to harsh radiatien only, and will be l

relocated and/or shielded to reduce the radiation exposure to a non-harsh level. Although qualification data is not available, continued station operation is justified for tne following reasons:

O 4-11 JUA Franklin Research Center a > on er w Fr,mma m oam

TER-C5 417-12 l

a.

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several. hours af ter the postulated accident.

Actual doses would therefore be less than those calculated using such

' conservative assumptions.

b.

Oose to this equipment is caused by only one loop of a redundant piping system. Operator action taxen to shut down redundant systems will further reduce exposure to this equipment.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of the DOR Guidelines are not satisfied. However, the Licensee stated that the equipment *will be shielded or relocated in order to

. achieve qualification.

4.3.3 Equipment Item No.139 Local Centrol Panels Located in the Reactor Building Harlo, Model DWG D12971 SH.30 (Licensee reference not cited)

The Licensee makes the fo11 ewing statements and commitments:

This equipment is subjected to harsh radiation only, and will be reevaluated and/or shielded to reduce the radiation exposure to a non-harsh level. Althougn qualification data is not availacle, continued statien operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases that occur several hours af ter the postulated accident. During this time, action will ce taken to shut down redundant systems beyond tcose needed for coolant inj ection. This would result in radiation exposures to only one of two redundant equipment trains. Also, actual doses would be less than those calculated using such conservative assumptions.

- Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down redundant system could be activated.

Review of the Licensee's System Component Evaluation Work Sheet indicates

)

that the requirements.cf the DCR Guidelines are not satisfied. However, the Licensee stated that the equipment will be shielded or relocated in order to acnieve qualification.

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l TER-C5417-12 4.4 NRC Category II' EQUIPMENT THAT THE LICENSEE BELIF/ES TO BE EXEMPT FROM QUALIFICATION This category includes equipment items that the Licensee believes to be exempt from qualification on the basis that (1) the equipment does not previde a safety function (i.e., should not have been included in the master list of safety-related equipment submitted by the Licensee), or (2) the specific safety-related function of the equipment can be accomplished by some other designated equipment that is fully qualified.

For Quad Cities Nuclear Power Station Unit 1, no equipment is assigned to tnis category.

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EQUIPMENT.THAT. HAS QUALIFICATICN TESTING SCHEDULED BUT NCTF COMPLETED This category includes equipment items that the Licensee has deter:nined to be de'ficient er inadequate with respect to qualification. However, the Licensee has stated that the equipment item is scheduled to be tested by a designated date.

For Quad Cities Nuclear Power Station Unit 1, no equipment is assigned to this category.

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9 TE R-C5 417-12 4.6 NRC Catecory V

- EQUIPMENT THAT DOES NJf SATISFY ONE OR MORE OF THE GENERAL REQUIREMEN*S-

'OF THE DOR GUIDELINES AND IE BULLETIN 79-013 This category includes equipment items judged to be deficient or inacequate with respect to the general reqcirements of the DCR Guidelines and IE Bulletin 79-01B based on a review of the Licensee's System Component Evaluation Work Sheets.

4.6.1 ' Equipment Item No.1 Temperature Switches Located in'the RWCU Room Manuf acturer and Model Not Stated (Licensee reference not cited)

The Licensee notes that, where these temperature switches are used for leak detection in the RWCU room, conditions are normally non-harsh.

Immediately following a leax, cne temperature will increase. As soon as the leak occurs, the switches will function, initiating system isolation within i

i minute.

Review of the Licensee's System Component Evaluation Work Sheet indicates

.that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not refe:enced qualification documentation for tnis item.

4.6.2 Equipment Item No. 2 Electric Motors Driving Pumps Located in the Corner Rooms General Electric Models 5K6338xC23A and 5K6336XC193 (Licensee ref erence not cited)

The Licensee makes the following statements and commitments:

A contract will be issued for service to qualify this equipment by analysis and/or testing, failing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualifica-tion data is not available, continued station operation is justified for i

the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases j

which occur several hours af ter the postulated accident. During this time, action will be taken to snut down recundant systems beyond those needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also' actual doses would be less than those calculated using such conservative assumotions.

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i TER-C5417-12 Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down_ redundant system could be activated.

During the time available af ter stabill:ation of core cooling, additional j

coolant injection paths could be established, if necessary, to assure

-long-term cooling..

1 Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Sulletin 79-013 are not satisfied. The Licensee j

has not refer 9nced qualification documentation for this item.

4.6.3 Equipment Item No.10 j

Pressure Switches Located in the NW and SW Corner Rocms Mercentrol Model OA-7043-804 (Licensee reference not cited) l The Licensee makes the following statements and commitments:

The equipment will be replaced with qualified equipment. Although qualificatien~ data is not available, centinued station cperatien is justified for the following reason:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release medels would result in radiatien releases I

wnich occur several hours after the postulated accident. During this time, action will be taken to shut down redundant systems ceyond those needed for coolant injection. This would result in radiation expcsures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down redundant system could be activated.

During the time available af ter stabili:ation of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

f Review of the Licensee's System Component Evaluation Werk Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.4 Iquipment Item No.13 Mctori:ed valve Actuator Located in the Drywell Limitorque Model SMB-1 with Reliance ac Motor (Licensee Ref erence 7)

The Licensee makes the fo11 ewing statements and commitments:

The equipment will te replaced with qualified equipment. Altncugh qualification data is not.availacle, continued stacien operation is l

justified for the following reason:

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4 TE R-C5 417-12 This valve is 1 =ated inside drywell and is normally open. Following a postulated accident, it would remain open to allow steam flow to the HCPI turbine. Valve operation would only be required to isolate the HPCI steam line. Three additional valves are located on this steam line outside drywell to isolate the steam line. Since the harsh environment inside drywell is associated with an accident wnigh would not affect environments or HPCI steam line pipe integrity outside drywell, the three outside drywell valves would be capable of isolating the steam line.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has referenced a test report indicating that none of the required environ-mental service parameters are enveloped. _Also, the Licensee considers that an evaluation of aging degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes this is not in conformance with the Guidelines requirements.

4.6.5 Equipment Itam No. 14 Motorized Valve Actuator Located in the Torus Area Limitorque Model SMS-1 with Peerless de Motor (Licensee ref arence not cited) i Review of the Licensee's System Component Evaluation Work Sheet indicates l

that the requirements of-IE Bulletin 79-013 are not satisfied. The Licensee has referenced a test report indicating that the required environmental l

service parameters were not enveloped with respect to the temperature and j

pressure exposures. It is noted that the nuclear radiation dose cited on the data sheet (10 krd) is not consistent with the value cited for this location in Appendix A.

Also, the Licensee considers that an evaluation of sging degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes this is not in conformarre with the Guidelines requirements.

P 4.6.6 Equipment Item No. 22 Temperature Switches Located in the HPCI Room United Electric Controls Model 883 (Licensee ref erence not cited)

The Licensee states that these temperature switches detect an HPCI steam line break and, in the event of a leak, these switches will function and isolate the HPCI steam line. The Lacensee concludes that, since the L >.

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temperature associated with this event is within the range of routine calibration, additional qualification ' data is not required.

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Review of the Licensee's System Component Evaluation Work Sheet indicates

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that the requirements of IE Bulletin 79-013 are not. satisfied. The Licensee

~

1 has not referenced qualification documentation for this item.

4.6.7 Equipment Item No. 36 Solenoid valve Located Inside 'Drywell Allied Controis-Gould Models 320X-39 and 320X-30 (Licensee reference not cited)

The Licensee makes the fo11cwing statements and commitments:

This equipment will be replaced with qualified equipment. Althcugh qualification data is not available, continued station operation is justified fer the fo11cwing reascns:

a.

These components are designed as redundant pairs, each separated from the other with only'one subjected to a harsh environment.

c.

These components _ complete eneir function in a very score period of time and would not experience significant effects of increased environmental conditions in this short time period.

c.

These components undergo periodic funccional testing to verify operabilit/. This testing would identify age related degradatien.

d.

These components or identical compenents remain functional during the June 5, 1970 depressurization incident at Dresden Unit 2.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.8 Equipment Item Nos. 37 and 38 Safety and Electromagnet Relief Valves and Solenoids Located Insi,de the Drywell 37: Dresser Industries Model C5450-5 332-Dresser Industries Medel 1325VX (Licensee Reference 15)

The Licensee makes the fo11cwing statements:

The numcer cf actuations which this compcnent was sugjected to during the test is censideracly larger than the numcer Of actuations during II days

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Although this test report did not utilize saturated atmosphere for testing, this component did operate through the saturated atmosphere of ene June 5, 19~0 depressurization incident at Dresden 0, and is therefore considered qualified.

The electrical components associated with this relief valve are enclosed in a metal enclosure which opens from the bottom only. Spray therefore could not af f ect operation of thir equipment.

Review of the Licensee's System Com ;nent Evaluation Work Sheet indicates e

I that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to spray, nuclear radiation dose, and test duration. Also, the Licensee considers that an evaluation of aging degradation is not required for this equipment. As note; in Section 4.1.3, FRC believes this is not in conformance with the Guidelines requirements.

4.6.9 ' Equipment Item No. 58 Motorized Valve Actuator Located in the Steam Tunnel

'Limitorque Model SMS-00 with Peerless de Motor (Licensee reference not cited)

The Licensee makes the following statements and commitments:

Additional vendor information is being sought to resolve outstanding environmental qualification items. Although qualification data is not available,' continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative non-mechanistic a.

models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident.

Actual doses would therefore be less than those calculated using such conservative assumptions.

b.

Other equipment similar in design to this equipment has successfully been qualified for environments in excess of the calculated l

requirement for this equipment.

l Review of the Licensee's System Component Evaluation Work Sheet indicates i

~

The Licensee that the requirements of IE Bulletin 79-01B are not satisfied.

i has not referenced qualification documentation for this item.

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TE R-C5 417-12 4.6.10. Equipment Item No. 43

-Pressure Switch Located in the EE Corner Room

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Static-C-Ring Model 12NN-KK215-VX (Licensee reference not cited)-

' The Licensee makes the following statements and commitments:

2

.This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is

. justified for the following reasons:

. Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiatien releases which occur several hours af ter the postulated accident. During this

. time, action will be taken to shut down redundant systems ceyend those needed for coolant injection. Tnis would result in radiation exposures to only one of two redundant equipment trains. Also actual deses would be less than.those calculated using such_ conservative assumptions.

Finally, should the operating equipment suffer degradation due to radiation. exposure, the shut down redundant system could be activated.

During the time available after stabilization of core cooling, additional coolant injection paths could be estactished, if necessary, co assure long-term cooling.-

Review of the Licensee's System Ccmponent Evalaation WecX 3heet indicatas that.the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item, 4.6.11 Equipment Item No. 56 Differential Pressure Indicating.Swit:hes Located in the NE and SE Corner Rocms Barton Model 289 (Licensee. reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mecnanistic models. Mechanistic release models would result in radiation releases which eccur several hours af ter the postulated accident. Curing enia time, action will be taken to shut dcwn redundant systems beycnd those -

needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual deses would

=e less than those calculated using such conservative assumptiens.

Finally, should the operating equipment suf fer degradation due to A

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. radiation exposure, the shut down redundant system could be activated.

During the time available af ter stabilization of core cooling.

Additional coclant injection paths could be established, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.12 Equipment Item No. 60 Dif ferential Pressure Switches Located in the NE Corner Room Barton, Model Not Stated (Licensee reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be replaced with qualified equipment. Altnough qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to radiation exposure, the shut down redundant system could be activated.

During the time available after stabilization of core cooling.

Additional coolant injection paths could be established, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.13 Equipment Item No.141 Temperature Element Located Inside the Torus Pall Trinity Micro 14-T-2H (Licensee reference not cited)

The Licensee makes the following statements and commitments:

A contract will be issued for services to qualify tn.is equipment by analysis and/or testing, f ailing which.the appropriate equipment or parts A, y Franklin Research Center t

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A TER-C5417-12 thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is

. justified for the following reasons:

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. Actual doses would therefore be less than those calculated using such conservative assumptions.

Other equipment similar in design to this equipment has successfully been qualified for environments in excess of the calculated requirement for this equipment.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Sulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.14 Equipment Iten No. 72 Electric Motors Driving Fans Lccated in the Corner Rocms General Electric.Models SK213AK2476 and 5K184AL2151 (Licensee reference not cited)

This equipment will be replaced with qualified equipment. Althougn qualification data is not available, continued station operation is justified for the following reasons:

Radiation deses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases that occur several hours af ter the postulated accident. During this time, action will be taken to shutdown redundant systems beycnd those needed for coolant inj ec tion. _This would result in radiation exposures to only one of two redundant equipment trains. Also, actual doses would be less than those calculated using such conservative assumptions.

' Finally, should the operating equipment suffer degradation due to radiation exposure, the shut down redundant system could be activated.

During the time available af ter stabilisation of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Li:ensee 1

has not referenced qualification documentation for this item.

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TER-C5 417-12 4.6.15 Equipment Item No. 81 Motorised Valve Actuator Located in the RWCU Room Limitorque Model SMB wit Peerless de Motor (Licensee reference not cited)

The Licensee makes the following statements and commitments:

Additional vendor information is being sought to resolve outstanding environmental qualification items. Although qualification data is not I

available, continued station operation is justified for th following reasons:

a.

These components are designed as redundant pairs, each separated from the other with only one sucjected to a harsh environment.

b.

These components complete their function in a very short period of time and would not experience significant ef fects of increased -

environmental conditions in this short time period, c.

These componenes undergo periodic functional testing to verify operability this testing would identify age related degradation.

Review of the Licensee's System Tempenent Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are net satisfied. The Licensee has not referenced qualification docunsntation for this item.

4.6.16 Equipment Item No. 69 l

Pressure Switches Located in the Reactor Building Static-O-Ring Model 12N-AAS-PP (Licensee reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

a.

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident.

Actual doses would therefore be less than those calculated using such

' conservative assumptions, t.

Dese to this equipment is caused by only one loop of a redundant piping system. Operator action taken to shut down redundant systems will further reduce exposure to this equipment.

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TE R-C5 417-12 Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee i

has not referenced qualification documentation for this item.

4.6.17 Equipment Item No. 90 Level Indicating Switches Located in the Reactor Building Yarway Models 4418C and 4419CE (Licensee reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be replaced with qualified' equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which eccur several hours af ter the postulated accident. During unis time, action will be taken to shut down redundant systems beyond those needed for coolant injection. This would result in radiation expcsures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions pinally, should the operating equipment suffer degradation due to radiation exposure, the shutdown redundant system could be activated.

During the time available af ter stabili:stion of core cooling.

Additional coolant injection paths could be established if necessary to assure long-term cooling.

P Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee j

has not referenced qualification documentation for this item.

4.'6.18 Equipment Item No. 7 Pressure Transmitters Located in the NW and SW Corner Rooms j

General Electric Models GE/MAC 551, 4532K11001 (Licensee Reference 21)

The Licensee makes the following statements and commitments:

A centract will be issued for service to qualify.this equipment by analysis and/or testing, f ailing vnich the apprcpriate equipment Or parts thereof will be replaced with qualified components. Although qualification data is not availaole, continued statien operation is justified for the fo11cwing reasont

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TE R-C5 417-12 Radiation doses were caiculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also acutal doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to.

radiation exposure, the shut down redundant system could be activated.

During the time available after stabilization of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to nuclear radiation dose and test duration. Also, the Licensee considers that an evaluation of aging l

degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes this is not in conformance with the Ouidelines requirements.

4.6.19' Equipment tem No. S Flow Transmitters Located in the NW and SW Corner Rooms l

General Electric Type 553, 4532K43001 (Licensee ref erence not cited)

The Licensee makes the following statements and commitments:

A centract will be issued for service to qualify this equipment by l

analysis and/or testing, f ailing which the appropriate equipment or parts

' thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is i

i justified for the following reasons:

l Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. During this time, action will be taxen to shut down redundant systems beyond those needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down redundant system could be activated.

During tne time available after stabilization of core cooling, additional coolant injection paths could be establisned, if necessary, to assure long-term cooling.

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'has not referenced qualification documentation for this item.

i 4.6.20 Equipment Item No. 9 Flow Switches Located in the NW and SW Corner Rocm3 Barton Model 289 i

1 (Licensee Reference 22) 4 The Licensee makes the following statements and commitments:

1 A cont:act will be issued for service to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment ce parts thereof will be replaced with qualified ecmponents. Althougn qualification data is not available, continued statien operation is f

justified for the following reason:

Radiatien doses were calculated using conservative, ncn-mechanistic models. Mechanistic release models would result in radiation releases which eccur several hours af ter the pestulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for. coolant injection. This would :esult in :sdiatien exposures to only one of two redundant equipment trains. Also actual doses wculd be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf f er decradation due to radiation exposure, the shut down' redundant system cculd be activated.

During the time available after staoili:ation of core eccling, additional ecolant injection paths could ce established, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evaluation Werk Sheet indicates that the requirements.of IE Bulletin 79-OLB are not satisfied. The Licensee has :sf erenced a test report indicating that the required environmental service parameters were not enveloped with respect to nuclear radiation dose.

Also, the Licensee considers that an evaluation of aging degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes this is not in conf:rmance with the Guidelines requirements.

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TER-05417-12 4.6.21 Equipment Item No. 54 Flow Transmitters Located in the NE and SE Corner Rooms

' General' Electric Model GE/MAC 553 (Licensee reference not cited)

The Licensee makes the fc11owing statements and commitments:

A contract will be issued for services to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reason:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant inj ection. This would result in radiation exposures to only.one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to j

radiation exposure, the shut down redundant system could be activated.

During the time available af ter stacili:ation of core cooling, additional l

coolant injection patns could be estaclished, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evaluation Work Sheet indicates j

(

that the requirements of II Bulletin 79-013 are not satisfied. The Licensee 1

l has not referenced qualification documentation for this item.

4.6.22 Equipment Item No. 57 Pressure Switches Located in the NE and SE Corner Rooms Mercoid Model GN-L-3 (Licensee ref erence not cited)

The Licensee makes the following statement and commitments:

A contract will be issued for services to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reason:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases wnich occur several hours af ter the postulated accident. During this time, action will be taken to shut down redundant sy, stems beyond those needed for coolant injection. This would result in radiation exposures

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TER-C5 417-12 to only.one of two. redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to-radiation exposure, the shut down redundant system could be activated.

During the time available af ter stabilization of core cooling, additional coolant' injection paths could be established, if necessary, to assure long-term ecoling.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirer

IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.23 Equipment Item No. 3 Motorized Valve Actuators Located in the NW and SW :'orner Rooms Limitorque Model SMB-0-25 with Peerless ac Motor (Licensee Reference 20)

Review of the Licensee's System Component Evaluatien Work Sheet indicates that a test report is referenced which envelops the environmental service parameters. However, the Licensee has not complied with the Guidelines requirements concerning the evaluation of aging degradation and determination of qualified life (see Section 4.1.3).

4.6.24 Equipment Item Nos. 4 and 49 Meterized Valve Actuators Located in the Reactor Suilding Limitorque Model SMB-0-15 with Peerless ac Motors (Licensee Reference 20)

}

Review of the Licensee's System Component Evaluation Work Sheet indicates that a test report is referenced which enveleps the environmental service parameters. However, the Licensee has not complied with the Guidelines

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requirements concerning the evaluation of aging degradation and determination of qualified lif e (see section 4.1.3).

l 1

l 4.6.25 Equipment Item No. 5 Motori:ed valve Actuators Lccated in the Reacter Building Limi:orque Medel 5MS-2-40 with Reliance ac Motor (Licensee Reference 7)

- Review of the Licensee's System Component Evaluation Wors Sheet indicates that a test report is referenced wnich envelops the environmental service d-h-4-23

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TER-C5417-12 parameters. However, the Licensee has not complied with the Guidelines requirements concerning the evaluation of aging degradation and determination of qualified life (see Section 4.1.3).

4.6.26 Equipment Item No. 6 Motorized Valve Actuators Located in the Torus Area Limitorque Model SMB-000 with Reliance ac Motor (Licensee Reference 7)

The Licensee makes the following statements and commitments:

Additional vender information is being sought to resolve outstanding environment qualification items. Although qualification data is not availaole for radiation, continued station cperation is justified for the following reason:

This valve opens on low flow to provide a minimum flow line. Should the valve fall in the open position, coolant injection would be reduced but would still exist. Additionally radiation deses were calculated using

. conservative, non-mechanistic models. Mechanistic release models would result in radiation releases whiet occur several hours after the postulated accident. During this time, action will be taken tt shut dcwn redundant systems beyond enose needed for cociant injection. This would result in radiation exposures to only of two redundant equipment trains.

Also actual doses would be less than those calculated using such l

conservative assumptions. Finally, should the operating equipment suffer

. degradation due to radiation exposure, the shut down redundant system could be activated. During the time available after stacilization of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

Review of the Licensee's System Component Evalueon Work Sheet indicates that the requirements of IE Bulletin 79-013 are not.

1sfied. The Licensee has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to nuclear radiatlon dese.

Also, the Licensee considers that an evaluation of aging degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes this is 1

not in conformance with the Guidelines requirements.

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I TER-C5417-12 4.6.27 Equipment Item No. 39 l

Motorized Valve Actuator Located Inside the Drywell Limitorque, Model Not 5tated, with Peerless ac Motor j

(Licensee References 20 and 24) l The Licensee makes the following statements and commitments:

The test peccedure required saturated atmosphere. Additional vendor information is being sought to resolve outstanding environmental qualification items, but humidity was not measured during the test. The test used saturated steam for temperature. Although qualification data is not available, continued station operation is justified for the following reasons:

These compenents are designed as redundant pairs, each separated frem a.

the other with only one subjected to a harsh environment.

b.

These components complete their function in a very short peried of i

time and would not experience siginficant eff ects of increased environmental conditions in this short time pericd.

c.

These components undergo periodic functional testing to verify operability. This testing would identify age related degradation.

d.

These components or identical ecmpenents ramained functional furing tne June 5, 1970 sepressurization incident at Dresden Unit 2.

Review of the Licens1e's System Ccmponent Evaluation Work Sheet indicates that a test report is referenced which envelops the environmental service parameters. However, the Licensee has not complied with the Guidelines requirements concerning the evaluation of aging degradation and determination of qualified life (see Section 4.1.3).

4.6.28 Equipment Item No. 42 Temperature Switches Located in the Steam Tunnel Fenwal Model 17002-40 (Licensee reference not cited)

The Licensee notes that these sensors are used to detect a main steam line break in the steam tunnel and complete their function within 1 minute.

The Licensee also notes that periedic calibratien is sufficient to demenstrate equipment capaci11ty to function under accident conditions.

Review of the Licensee's System Compenent Ivaluation Work Sheet indicates inat the requirements of II Sul.otin 79-013 are not satisfied. The Licensee has not referenced qualificatien documentation for this item.

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TER-CS 417-12 4.6.29 Equipment Item No. 44 Motorized Valve Actuators Located in the NE and SE Corner Rooms Limitorque Model SMB with Peerless ac Motors (Licensee Reference 20)

Review of the Licensee's System Component Evaluation Work Sheet indicates that a test report is referenced which envelops the environmental service parameters. However, the Licensee has not complied with the Guidelines raquirements concerning the evaluation of aging degradation and determination of qualified lif e (see Section 4.1.3).

4.6.30 Equipment Item No. 45 Motorized Valve Actuators Located in the NE and SE Corner Rooms Limitorque Model SMB-2-60, Motor Not Identified (Licensee ref erence not cited)

The Licensee states the following with regard to qualification for nuclear radiation dose Either Reliance or Peerless ac motors are used in this station. Tne Reliance ac motor is qualified for 2.0 E07 rads while Peerless ac motors

,are qualified fer 2.0 EOS. The lower number is used as the werst case.

Review of the Licensee's System Component Evaluation Work Sheet indicates that tne requirements of IE Bulletin 79-OlB are not satisfied. Tne Licensee has not referenced a test report or other evidence of qualification. The required environmental service parameters were not enveloped with respect to nuclear radiation.

4.6.31 Equipment Item No. 46 Motorized Valve Actuators Located in the Torus Area Limitorque Models SMB-000-5, SMB-3-100, SMB-0-10, and SMB-4T-150 (Licensee Reference 20)

Review of tne Licensee's System Component Evaluation Work Sheet indicates that a test report is referenced which envelops the environmental service parameters. However, the Licensee has not complied with the Guidelines

(

requirements concerning the evaluation of aging degradation and determination-of qualified lif e (see Section 4.1.3).

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- t 4.6.32 Equipment Item No. 47 Motorized Valve Actuators Located in the NE and SE Corner Rooms Limitorque Models SMB-2-40,

-0, and -1

. (Licensee Reference 7) l Review of the Licensee's System Component Evaluation Work Sheet indicates that a test report.is' referenced which envelops the environmental service parameters. However, the Licensee has. not complied with the Guidelines requirements concerning the evaluation of aging degradation and determination of qualified life (see Section 4.1.3).

i 4.6.33 Equipment Item No. 50 Motori:ed Valve Actuators Located in the Torus Area Limitorque Models SMB-5T-130 and SMB-2-60 with Reliance ac Motors (Licensee Reference 7)

L The Licensee makes the following statements and commitments:

Additional vendor information is being sought to resolve outstanding environmental qualification items. Although qualification data is not available, continued station operation is justified for the following reascns:

a.

Existing qualification data is within a f actor of 2 of the calculated radiation dese.

b.

Radiation doses were calculated using conservative non-meenanistic I

models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident.

Actual doses wculd therefore be less than those calculated using suen conservative assumptions.

c.

Other equipment similar in design to this equipment has successfully been qualified for environments in excess of the calculated

)

requirement for. this equipment.

- Review of the Licensee's System Component Evaluation ' dock Sheet indicates that the recuirements of IE Bulletin 79-01B are not satisfied. The Licencee has referenced a test report indicating that the required environmental service parsmeters were not enveloped with respect to nuclear radiation dese.

Also, the Licensee considers that an evaluation of aging degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes enis is not in conformance with the Guidelines requirements.

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TER-C5417-12 4.6.34 Equipment Item No. 52 Motori:ed Valve Actuators Located Inside the Drywell Limitorque Models SMB-3 and SMS with Reliance ac Motors (Licensee ceference not cited)

The Licensee makes the following statements and commitments:

Additional vendor information as being sought to resolve outstanding environmental qualification itena. Although qualification data is not I

available, con *'

ed' station operasion is justified for the following reasons:

a.

These componenus or similar items have been partially tested for' environmental conditions.

b.

These components remained functional during the June 5, 1970 depressuri:ation incident at Dresden Unit 2.

This incident resulted in harsh environmental conditions.

Review of the Licensee's System Component Evaluation Work Sheet indicates tnat the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.35 Ecuipment tem No. 53 Pressure Transmitters Located in the BTE and SE Corner Rooms General Electric Model GE/MAC 551 (Licensee reference not cited)

The Licensee makes the following statements and' commitments:

A contract will be issued for services to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment or parts thereof will be replaced with qualified components. Althougn qualification data is not available, continued station operation is justified for the following reason:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. During this time, action will be taken to shut down redundant systems beyond these needed for-coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to radiation exposure, the shut down redundant system could be activated.

During the time available after stabili:ation of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

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.that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee 1

has not referenced qualification documentation for this item.

4.6.36 Equipment Item No. 30 -

Motorized Valve Actuators Located in the Drywell Limitorque SMB-1-40, SMB with Peerless ac Motor (Licensee References 20 and 24)

Review of the Licensee's System Component Evaluation Work Sheet indicates that a test report is referenced which envelops the environmental service parameters. Mcwever, the Licensee has not ecmplied with the Guidelines requirements concerning the evaluation of, aging degradation and determination of qualified life (see Section 4.1.3).

4.6.37 Equipment Item No. 83 j

Motorized Valve Actuators Located in the Torus Area and Within the D rywell Limitorque Model SMB-000-5 with Peerless ac Motor (Licensee References 20 and 24)

Review of the Licensee's System Component Evaluation Work Sheet indicates that a test report is referenced which envelops the environmental service parameters. Mcwever, the Licensee has not complied with the Guidelines requirements concerning the evaluation of aging degradation and determination of qualified life (see Section 4.1.3).

4.6.38 Equipment Item No. 113

' Temperature Switches Located in the NW Corner Room Fenwal Model 17002-40 (Licensee Reference 27) 1 l

The Licensee stated:

j This temperature switch is used to detect an ROIC steam line tress. As soon as a brea4 cccurs, this switch will function isolaring the RCIC steam line, by detecting high temperature. This would accur in less than one minute. One minute was conservatively assumed. Periodic calibracien is sufficient to demonstrate ecmponent capability to f ur.ction under accident envircnments1 tempersture ccnditions.

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I TER-C5417-12 Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to steam exposure. Also, the Licensee considers that an evaluation of aging degradation is not required for this equipment. As noted in Section 4.1.3, FRC believes this is not in conformance with the Guidelites requirements.

4.6.39 Equipment Item No. 109 Motori:ed valve Actuators Located Inside the Drywell Limit 0rque Models SMB-2 and SMS-000 (Licensee reference not cited)

The Licensee makes the following statements and commitments:

Additional vendor information is being sought to resolve outstanding environmental qualification items. Although qualification data is not available, continued station operation is justified for the feliceing reasons:

a.

These components or simila: items have been partially tested Ocr environmental conditions.

i b.

These components remained functional during the June 5, 1970 depressuri:ation incident at Dresden Unit 2.

This incident resulted in harsh environmental conditions, j

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee l

has not referenced qualification documentation for this item.

l l

l 4.6.40 Equipment Item No. 110 Motor Operated Valves Located in the Torus Area Limitorque Model SMB-2-40 with Reliance ac Motor (Licensee Reference 7)

Review of the Licensee's System Component Evaluation Work Sheet indicates tnat a test report is ref erenced which envelops the environmental service j

parameters. However, the Licensee has not complied with the Guidelines requirements concerning tne evaluation of aging degradation and determination of qualified life (see Section 4.1.3).

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TER-C5 417 l 4.6.41 Equipment Item No.121 Electric Cable Located Inside the Drywell j

Simplex, Rubber Insulation /PVC Jacket (Licensee reference not cited) i The Licensee makes the following statements and commitments:

A contract will be. issued for services to qualify enis equipment by l

analysis and/or testing, failing which the appropriate equipment or parts thereof will be replaced with qualified cemponents. Although qualification data is not available,' continued station operation is justified for the following reasons:

a.

These components or similar items have been partially tested for environmental conditions.

b.

These components remained functional during the June 3, 1970 depressuri:ation incident at Dresden Unit 2.

This incident resulted in harsh environmental conditions.

Review of the Licenses's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.42 Equipment Item No. 126 Electric Cable Located outside the Drywell General Electric, Butyl Rubber Insulation /PVC Jackett Cross-Linked Polyethylene Insulation / Neoprene Jackett Rubber Insulation /Hypalon Jacket (Licensee reference not cited)

The Licensee makes the fo11cwing statements and commitments:

A contract will be issued for services to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reasons:

a.

Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, terus ecmpartment (near postulated HPCI break only), and RWCU recms contain equipment which must function in 1 minute or less. Once equipment functions are completed, there would be no furtter active function required. In all cases except the torus ecmpartment, the only cables entering the potential harsh environment area would terminate in that area. In the esse of the torus ccmpartment, other cabling could be in the vicinity of tne H7CI line fa

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O TER-C5417-12 break; however, the torus compartment is sn large that the harsh environment would dissipate almost instantly with valve closure.

Radiation is not concurrent with other harsh conditions.

b.

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident.

Actual doses would be less than those calculated using.such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

Review of the Licensee's System Component Evaluation Work Sheet indicates that;the requirements of II Bulletin 79-01B are not satisfied. The Licensee has net referenced qualification documentation for this item.

4.6.43 Equipment Item No.127 Cable Located within the Drywell General Electric, P 1yethylene Insulation /pv0 Jacket (Licensee reference not cited)

The Licensee makes the following statements and commitments:

A contract will be issued for services to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not availacle, continued station operation is

$ustified for the following reasons:

These components or similar items have been partially tested for a.

environmental conditions.

b.

These components remained functional during the June 5,1970 depressurization incident at Dresden Unit 2.

This incident resulted in harsh environmental conditions.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of II Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

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TE R-C5 417-12 4.6.44 Equipment Item No. 128 Electric Cable, Lccation Not Stated Simplex, Butyl Rubber Insulation /FVC Jacket (Licensee reference not cited)

The Licensee makes the following statements and commitments:

A contract will'b'e issued for services to qualify this equipment by analysis 'and/or testing, failing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reasons:

a.

Of the plant areas.which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near postulated HPCI break only), and

.RWCU rooms contain equipment which must function in 1 minute or less..once equipment functions are completed, there would be no further active function required. In all cases except the torus compartment, the only cables entering the potential harsh environment area would terminate in that area. In the case of the torus compa r tme nt, other cabling could be in the vicinity of the HPCI line break; however, the torus compartment is so large that the harsh environment would dissipate almost instantly with valve closure.

Radiation is not concurrent with other harsh conditions, b.

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models wculd result in radiation releases which occur several hours af ter the postulated accident.

Actual doses would be less than those calculated using such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, althougn some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilised and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of II Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

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TER-C5417-12 4.6.45 Equipment Item No. 129 Electric Cable Located outside Drywell Simplex, Anhydrex XX Plastex Insulation and Jacket (Licensee reference not cited)

The Licensee makes the following statements and commitments:

A contract will be issued. for services to qualify this equipment by analysis and/or testing, failing which the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reasons:

a.

Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near postulated HPCI break only), and

. RWCU rooms contain equipment which must function in 1 minute or-less. Once equipment functions are completed, there would be no further active function required. In all cases except the torus compartment, the only cables entering the potential harsh environment area would terminate in that area. In the case cf the terus compartment, other cabling could be in the vicinity of the HPCI line breax; however, the torus compartment is so large that the harsh environment would dissipate almost instantly with valve closure.

Radiatien ir not concurrent with other harsh conditions, b.

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the pastulated accident.

Actual doses would be less than those calculated using such conservative assumptions. In addition, harsh radiation is not-l concurrent with pressure, temperature, and humidity: therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utill:ed for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not ~ referenced qualification documentation for this item.

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4 TER-C5 417-12 4.6.46 Equipment Item No, 120 Electric Cable Located outside the Drywell Simplex, Poly Nylon Insulated Shield and Plaster Jacket

- (Licensee reference not cited)

The Licensee makes the following statements and commitments:

A contract will be issued for services to quality this equipment by analysis and/or testing, failing which the appropriate equipment ce parts thereof will be replaced with' qualified components. Although qualification data is not available, continued station operation is justified for the following reasons:

s.

Of tne plant areas which could experience harsh pressure, ctemperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near gostulated RPCI break only), and RWCU rooms contain equipment which r e-

' '-tion in 1 minute or less. Cnce equipment functions are campleted, there would be no further active function required. In all cases except the torus compartment, the-only cables entering the potential harsh environment area would terminate in that area.

In the case of the torus compa r tmen t, other cabling could be in the vicinity of the EPCI line breaks however, the torus compartment is so large that the harsh environment would dissipate almost instantly witn valve closure.

Radiation is not concurrent with other harsh conditions.

b.

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours af ter. the postulated accident.

Actual doses would be less than those calculated using such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

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t TER-C5417-12 4.6.47 Equipment Item No. 132 Electric Air Heater Located in the Reactor Building E. L. Wiegland, Model Not Stated (Licensee reference not cited) _

The Licensee makes the f=11owing statements and commitments.

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours'after the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to radiation exposure, the shut down redundant system could be activated.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

4.6.46 Equipment Item No.13 4 Electric Motor Driving Exhaust Fan Located in the Reactor Building New York Blower Model E4966 (Licensee reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be replaced with qualified equipment. Althougn qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using eenservative, non-mechanistic models. Mechanistic releas models would result in radiation releases which ' occur several hours af ter the postulated accident. During this l

time, action will be taken to shut down redundant systems beyond those l

needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down redundant system could be activated.

Review of the Licensee's System Component Evaluation _ Work Sheet indi:ates tnat the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

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TE R-C5417-12 4.6.49 Equipment Item No.135 Flow Transmitter Located in the. Reactor Building Leeds & Northrup Model 1912-3-21-0-0000-0300-0300 (Licensee. reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be ' replaced with qualified equipment. Although qualification data. is not available, continued station operation is justified for the following reasons:

- Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic releas models would result in radiation releases which occur 'several hours-af ter the postulated accident. During this-time, action will be taken to shut down redundant systems beyond those needed for coolant injection. This. would' result in radiation exposures co only one;of two' redundant equipment. trains. Also actual doses would

, be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, the shutdown redundant system could be activated.

~ '

Review of the Licensee's System Component Evaluation Worx Sheet indicates that. the requirements of IE Bulletin 79-013 are not' satisfied. The Licensee has not referenced qualification documentation for' this item.

4.6.50 Equipment Item No.136 Ficw Transmitter Located in the Reactor Building Foxboro Model 15A (Licensee reference not' eited)

The Licensee makes _,the following statements and commitments:

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses' were calculated using conservative, non-mechanistic models.. Mechanistic release models would result in radiation releases which occur several hours af ter. the postulated ' accident. During this time, action will be taken to shutdown redundant systems beyond those needed for ' coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses wculd be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down redundant system could ce activated.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

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O TER-C5417-12 4.6.51 Equipment Item No.137f

. Flow Switches Located in the Reactor Building Mercoid Models DA-533-3 and DA-533-2R1 (Licensee reference not cited)

.The Licensee makes tne following statements and commitments:

This equipment will-be replaced with qualified equipment. Although qualification data is not available, continued. station operation is justified for the.following reason Radiation doses were calculated using conservative, non-mechanistic models. -Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. During this

' time,-action will be taken to shut down redundant systems beyond those z needed for coolant injection. This would result in radiation exposures-to only one of two redundant equipment trains., Also actual doses would

. be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, tne shut down redundant system could be activated.

Review of the Licensee's System Component Evaluation Work Sheet indicates-that_the requirements of IE Bulletin 79-013 are not satisfied. The Licensee P

has not' referenced qualification documentation for this item.

4.6.52 Equipment Item No. 138 Temperature Switch Located in the Reactor Building Chremalox, Model Not Stated

'(Licensee reference not cited)

The Licensee makes.the following statements and commitments:

i This equipment will be replaced with qualified equipment. Although qualification data is not available,. continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases

. which occur several hours'after.the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant injection. This would result in radiaiton exposures to only one of two redundant equipment trains. Also, actual doses would be less than those calculated using such conservative assumptions.

- Finally, should the operating equipment suf fer degradation due to radiationL exposure, the ' shutdown redundant system could be activated.

Review of the Licensee's System Component Evaluation, Work Sheet indicates that.the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for this item.

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TER-C5417-12 4.6.53 Equipment Item No.140

. Solenoid Valve Located in the Reacter Building

' versa /ASCO Model VWS-23029320A23 (Licensee reference not cited)

The Licensee makes the following statements and commitments:

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative non-mechanistic i

models. Mechanistic release models would result in radiation releases that occur several hours af ter the postulated accident. During this

~

time, action will be taken to shut down redundant systems beycnd those needed.for coolant injection. This would result in radiation exposures to only 'one'of two redundant equipment trains. Also, actual deses would be less than those calculated using such conservative assumptions.

Finally, should the operating equipment suf fer degradation due to radiation exposure, the shut down redundant system ceuld be activated.

Review of the Licensee's System Component. Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation for enis item.

4.6.54 Equipment Item No. 131 Position Switch Located Inside the Drywell NAMCO Model EA-08011100 (Licensee reference not cited)

The Licensee makes the following statements and commitments:

This switch was inaccessible for inspection. The manufacturer and model number will be established during the next outage permitting entry to the drywell. If the component is not ' qualified, a replacement part with qualification data will be purchased and installed during the first outage after received on site.

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not ref erenced qualification documentatien for this item.

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1 TER-T5417-12 4.6.35 Equipment Item No. 123 Electrical Penetrations Located in the Drywell GE-NEBS, Model Not Stated (Licensee reference not cited)

The Licensee maxes tne f:llcwing statements and commitments:

- Additional vendor information is being sought to resolve outstanding environmental qualification items. Although qualification data is not available, continued station operation is justified for the following reasons:

a.

These components or similar items have been partially tested for environmental cenditions.

b.

These components remained functional du:ing the June 5, 1970 depressurization incident at Dresden Unit 2.

This incident resulted in harsh environmental conditions.

Review of the Licensee 's System Component Evaluation Work Sheet indicates tnat tne requirements of II Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

- 4.6.56 Equipment Item Nc. 130 Terminal Blocks Located in the Drywell Allen Bradley, Model Nct Stated (Licensee reference not cited)

The Licensee makes the following' statements and commitments:

This equipment will be replaced by qualified equipment. Althougn qualification data is not available, continued station operation is justified for the following reasons:

Tnese components or similar items have been partially tested for a.

environmental conditions.

l b.

These componen,ts remained functional during the June 5, 1970 depressurization incident at Dresden Unit 2.

This incident resulted l.

in harsh environmental conditions.

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Review of.the Licensee's System Compcnent Evaluation Xcrx Sheet indicates l

that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

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TER-C5417-12 4.6.57 Equipment Item No.119 Electric Cable Located outside the Drywell General Electric vulkene No. SI 57275 (Licensee reference not cited)

The Licensee makes the following statements and commitments:

A contract will be issued for services to qualify this equipment by analysis and/or testing, f ailing which the appropriate equipment or parts thereof will be_ replaced with qualified ccmponents. Although qualific-ation data is not-available, continued station operation is justified for the following reasons:

of the plant areas which could experience harsh pressure, a.

-temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus ccmpartment (near postulated HPCI break only), and RWCU recms centain equipment wnien must function in 1 minute or

.less.

Once equipment functions are ecmpleted, there would be no further active function required. In all cases except the torus ccmpartment, the only cacles entering the potential harsh environment-area would terminate in that area. In the caae of the torus compartment, other cabling could be in the vicinity of the HPC line break; however, the torus compartment is so large tha t the haran environment would dissipate alscst instantly with valve closure.

Radiation is not concurrent wien otner naran conditions.

b.

Radiation deses were calculated using conservative ncn-mechanistic medels.. Mechanistic release models would result in radiation releases which occur several hours af ter the pcstulated accident.

Actual doses would be less than these calculated using such consetvative assumptiens. In addition, harsh radiation is not cencurrent with pressure, temperature, and humidity; therefore, although seme material decradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, scst of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

Review of the Licensee's. System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation for this item.

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TEE-C5417-12 4.6.58 Equipment Item he. 111 Scienoid Valves Located in the Torus Area Versa Models VPS-2502 and VGS-4522/VGS-4422

-(Licensee reference not cited)

The Licensee states:

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident. Actual doses would therefore be less than those calculated using sucn conservative assumptions. An alternate flow path is available to relieve torus vacuum in the event these components should fail.

Review of the Licensee's System Ccmponent Evaluation Work Sheet indicates tha t the requirements cf :E Bulletin 79-013 are not satisfied. Tne Licensee has not referenced qualification documentation for this item.

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TER-C5417-12 4.7-NRC Category VI EQUIPHENT FOR WHICH QUALIFICATION IS CEFERRED This category includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittals; however, the 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.19 Differentia 1' Pressure Indicating Switches Located in the Reactor Building Barton Model'288 (Licensee, reference not cited)

Review'of the Licensee's System Cemponent Ivaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that.it performs its safetyf function. Therefore, qualificati:n review can be deferred in accordance with criteria presented in Section 2.2.3.

~

4.7.2 Equipment Item No. 24 Pressure Switch Located in the Reactor Building 3arksdale Model 32T-A12SS (Licensee reference not cited)

Review of the Licensee's System Ccmponent Evaluation Work Sheet indicates tha t this equipment is located in a nenharsh area prior to and during the time tha t it performs its safety function. Therefore, qualificatien review can be

' deferred in' accordance with criteria presented in Section 2.2.3.

4.7.3. Equipment Item No. 68 Pressure Switch Located in the Reactor Building Static-O-Ring Model 12N-AAS-PP (Licensee reference not cited)

. Review of the Licensee's System Ccmponent Evaluation Worn Sheet indicates that this equipment is located in a nenharsh area prior'to and during the time that it performs its safety functien. Therefore, qualification review can be deferred in acccedance with criteria presented'in Section 2.0.3.

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e TER-C5417-12 4.7.4 Equipment Item No. 142 Damper Located in the KVAC Equipment Room Manufacturer and Model Not Stated (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.5 Equipment Item No. 76 Level Switenes Located in Diesel Room Magnetrol Model A-103F-EP/VP (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates tnat this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualificatien review can.be deferred in accordance with criteria presented in Section 2.2.3.

4.7.6 Equipment Item No. 74 l-Electric Motor Driving Fan Located in the Diesel Room i

Manufacturer and Model Not Stated (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant l

l location is 120*F and.regards this as a nonharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

-However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii)

. the duration of the temperature excursion above 104'F is so short that the elevated ambient temperature cannot af fect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

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TER-C5417-12 4.7.7 - Equipment Item No. 75 Electric Motor Driving Pump Located in the Diesel Rocm General Electric Model SK182BL315, Type K (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*? and regards this as a nenharsh cendition; the r e for e,

, qualification review can be deferred in accordance with criteria presented in Section 2.2.3..However, as noted in Section 4.1.2, FRC considers that this approach does not conform _to tne requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*? is so short that the

-elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification dccumentation.

4.7.8 Equipment Item No. 77 Solencid Valve Located in the Diesel Room ASCO Model 3211239 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section'2.2.3.

However, as noted in Secticn 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot af fect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

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TER-C5417-12 4.7.9 Equipment Item No. 94 Diesel Auxiliary Control Panel Located in the Diesel Room Ideal Electric and Manufacturing Model S.O. No. 267777 (Licensee reference not cited)

The Licensee states:

FSAR Section 10.10 and Special Report No.12, Rev.1, February 1975.

Qualification for the environment due to a feedwater line break is not required since three diesels are available to provide emergency ac power.. FSAR Section 8.2.3.1 describes the system arrangement for the standby ac power system. As a minimum, one diesel generator can be made available to provide emergency power to the af fected unit assuming the HELB causes f ailure of the adjacent diesel and a single active f ailure of a second diesel unit.

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh conditions therefore, qualification review can be deferred in accordance with criteria presented in Section 1.2.3.

However, as noted in Section 4.1.2, FRC considers that this appecach does not conform tc the requirements of the Guidelines unless fi) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so sheet that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.10 Equipment Item No. 95 Excitation Cabinets Located in the Diesel Room Electromotive Div. of GM Model 9474 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the l

equipment has been designed to operate in this ambient temperature, or (ii) ine duration of the temperature excursion above 104*F is so short that the elevated ameient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

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TER-C5 417-12 4.7.11 Iquipment Item No. 96 Diesel Generator Located in the Diesel Recm Electremotive Div. of GM, Model Not Stated (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh conditicn; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC censiders that this approach dces not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*? is so short that tne elevated ambient temperature cannot affect the equipment 's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.12 Equipment Item No. 100

' Ingine Centrol Panel Located in the Diesel Rocm Electromotive Div. of GM, Model Not Stated (Licensee reference net cited)

The Licensee states:

FSAR Section 10.10 and Special Report No.12, Rev.1, February 1975.

Qualification for the environment due to a feedwater line crea4 is not required since ' three diesels are available to provide emergency ac power. FSAR Section 3.2.3.1 describes the system arrangement for the standby ac pcwer. system. As a minimum, one diesel generater can be made available to provide emergency power to the affected unit assuming the EELB causes f ailure of the adjacent diesel and a single active f ailure of a secend diesel unit.

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh cendition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC censiders that this approach does not conferm to the require =ents of the Guidelines unless (;; the equipment has been designed to operate in tnis amcient temperature, er tii) the duratien of the temperature excursion aceve 104'F is se short that the elevated amotent temperature cannot affect the equipment's operatien. The 4 **

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Licensee has not provided any information to show that either condition is i

satisfied and has provided no qualification documentation.

4.7.13 Equipment Item No. 102

'D/G Secendary Control Panel Located in the Diesel Room Ideal Electric 5.0. No. 267777 (Licensee reference not cited)

The Licensee states:

FSAR Section 10.10 and special Report No.12, Rev.1, February 1975.

Qualification for the environment due to a feedwater line break is not

~

required since three diesels are available to provide emergency ac power. FSAR Section 8.2.3.1 describes the system arrangement for the standby ac power system. As 'a minimum, one diesel generator can be made available to provide emergency power to the affected unit assuming the HELB. causes 'f ailure of the adjacent diesel and a single active f ailure of a second' diesel unit.

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards thir is a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has oeen designed to cperate in this ambient temperature, or (ii) the duration of the temperature excursion above 104'F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee.has not provided any information to show that either condition is I

satisfied and has provided no qualification documentation.

4.7.14 Equipment Item No.103 D/G Neutral Grounding Panel -Located in the Diesel Room l

General Electric Model 208419-68P, #KVA-5 (Licensee reference not cited)

The - Licensee states:

t l

FSAR Section 10.10 and Special Report No.12, Rev.1, February 1975.

l Qualification for the environment due to a feedwater line break is not required since three diesels are available to provide emergency ac l

power.

FSAR Section 8.2.3.1 describes the system arrangement for the standby ac power system. As a minimum, one diesel, generator can be made l

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TER-C5417-12 available to provide emergency power to the af fected unit assuming the HELB causes failure of the adjacent diesel and a single active

allure of a second diesel unit.

-The Licensee indicates that the maximum-temperature in this plant location is 120*F and regards this as a nonharsh condition; therefore,

. qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2,.FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short tha t the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is

-satisfied and has provided no qualification documentation.

4.7.15 ~. Equipment It em - No. 10 4 3attery Chargers Lccated in the Battery Charger Room Gould Mcdels GRF240T100X, GRF120T100X, and GRF24S25F30X (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh conditions therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Ouidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short tha t the elevated ambient temperature cannot af fect the equipment 's operation. The Licensee has not provided any information to show that either condition is satisfied and'has-provided no' qualification documentation.

4.7.16 Equipment Item No.105 250 7 de Motor control Center Located in the 3attery Oharger Recm Cutler Hammer Medel 5002H3473 (Licensee Reference 25)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards tnis as a nonnarsh conditioni enerefore,

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8 TER-C5417-12 qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this amoient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.17 Equipment Item No. 106 Batteries Located in the Battery Charger Room Gould Models FPS-25, FPR-13, and CPP-9 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC censiders that this approacn does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short enat the elevated amcient temperature cannot af fect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has previded no qualification documentation.

4.7.18 Equipment Item No. 107 de Distribution Panel Located in the Battery Charger Room Cutler Hammer, Model Not Stated (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh condition; the re f o r e,

i qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the (ii) equipment has been designed to operate in tnis amcient. temperature, or the duration of the temperature excursion abcVe 104*F is so short that tne 4-55 2 Frankjin Researen Center A QMason of The li ansen m r

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- Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

- 4.7.19-Equipment Item No. 11 l Step Valve Located in the HPCI Room Manuf acturer-Not Stated, Model 178250E02D4 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*? and regards this as'a nenharsh condition. Therefore, qualification review can be' deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in'Section 4.1.2, FRC considers that enas

. approach doe's not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*? is so short that the elevated ambient temperature cannot affect the equipmer.t's operation. The

. Licensee has not provided any informatien to shew that either cceditien is satisfied and has previded no qualification documentation.

?

4.7.20 Iquipment Item No. 12 Motorized valve Actuators - Located in the HPCI Room Limitorque Model SMB with Peerless de Motors (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant

. location is 120*F and regards this as a nenharsh condition; th e r e for e,

I

- qualification review can be deferred in accordance with criteria presented in Section 2. 2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or'tii) the duration of the temperature excursion above 104*F is so short tha t the elevated ambient temperature cannot affect the equipment's operatien.

The.

' Licensee has not provided any infermatien to shew that either cenditien is satisfied and has provided no qualificatien dccumentation.

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0 TER-C5417.2 4.7.21-Equipment Item No. 15 Motorized Valve Actuators Located in the EpCI Room Limitorque Model SMB with peerless de Motors (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120'F and regards this as a nonharsh condition. Tnerefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee' has not provided any information to show that either condition is satisfied and has previded no qualificatien documentation.

4.7.22 Equipment Item No. 16 Motori:ed Valve Actuators Located in the Steam Tunnel Limitorque Model. SMS witn peerless de Motor (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh conditions therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, TRC considers that this l

approach does not conferr to the requirements of the Guidelines unless (i) the I

equipment has been designed :c' operate in this ambient temperature, or (ii) the duration of the~ temperature excursion above 104*F is so short that tne elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.23 Equipment Item No. 17 Motori:ed valve Located in the HpC: Room Limitorque Model SMB with Reliance de Motor (Licensee reference not cited) l The Licensee indicates that the maximum temperature in this plant location is 120'F and regards this as a nonharsh condition; therefore, i

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TER-C5417-12 qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

Ecwever, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment.has been designed to operate in this amcient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operatien. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.24. Equipment Item No 13 Solenoid valves Lccated in the H7C2 ?ccm ASCO Model 330281F t-s s (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh conditiens.therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers tnat ents approach dees not conform to the requirements of the Guidelines unless (i) the equipment has been designed to cperate in 'this ambient temperature, or (11) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature.cannot affect the equipment's cperation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.25 Equipment Item No. 20 Flow Transmitter Located in the HPCI Room General Electric Model GE/MAC 553, 4532K13001 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*? and regards this as a nonharsh condition. Therefore, qualification review can ce deferred in accordance with criteria presented in Section 2.2.3..

Mcwever, as noted in Section 4.1.2, FRC considers that thia appecaen does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this amcient t,emperature, er 1:1) 4-58

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tne duration of the temperature excursion above 104'T is se short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has.provided no qualificatien documentation.

4.7.26 Equipment Item No. 21 pressure Transmitter Located in the HPCI Room General Electric Model 4532K11001 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh condition; therefore, qualification review can be deferred !, accordance with criteria presented in Section 2.2.3.

Hewever, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duratien of the temperature excursion above 104'T is so shcrt that the elevated ambient temperature cannet affect the equipment's operation. The Licensee has not provided any information to shew that either condition is satisfied and has provided no qualification documentation.

4.7.27 Equipment Item No. 23 Pressure Transmitter Located in the HpCI Room i

General Electric Models GE/MAC 551, 50-551032CAAY1 l

4 l

(Licensee reference not cited) i l

The Licensee indicates that the maximum temperature in this plant l

l

. location is 120*F and regards this as a nonharsh condition; therefore, l

qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration cf the temperature excursion abcve 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has net provided any information to show that either condition is satisfied, and has provided no qualification documentati,en.

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TER-C5417-12 4.7.28 Equipment Item No. 25 Electric Motor Driving Turbine Gland Seal Condensate Drain Pump Located.in the HPCI Rocm General Electric Model 58225A3525 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to cperate in this amcient temperature, or (ii) the duration of the temperature excursion acove 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any infccmstien to shew that either conditien is satisfied and has provided no qualification documentation.

4.7.29 Equipment Item No. 26 Electric Motor Driving Gland Steam Exhaust Fan Lccated in the HPCI Rccm General Electric Model 5BC74AB2193 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh conditien; therefore, qualification esview can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC censiders that this approaca does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) l the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has previded no qualificatien dccumentation.

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TER-C5417-12

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4.7.30 Equipment Item No. 27 Motor Speed Changer Located in the HPC: Room General Electric Model GE5BC26AC389 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh conditions therefore, qualification review can be deferred in ace-rdance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short tnat the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.31 Equipment Item No. 28 Motor Gear Unit Located in ene HPC: Room General Electric Model SC014019Alll6:0 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh conditiens therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (i) the i

equipment has oeen designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion aeove 104*F is so short that the elevated ambient temperature cannot af fect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.32 Equipment : tem No. 29 Electric Motor Criving 011 Pump Located in the HPCI Room General Electric Models SCO218E252 and SCD326E758 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120'T and regards this as a nonharsh condition; therefore, 4-61 d'. Frankhn Research C. enter l

4cm on.< w % nm.

1 l

l l

TER-C5417-12 qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (11) the duration of the temperature excursion abcve 104*F is se sheet tha t the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.33 Equipment Item No. 30 HPC: Meter Centrol Signal Converter Lccated in the HPC ?.ccm General Electric Medel 3575130C108 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nonharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

Scwever, as noted in Secticn 4.1.2, FRC censiders that th is approach dcas not conform to the requirements of the Guidelines unless (i) the equipment has been designed to cperate in this ambient temperature, or (ii)

^

the duration of the temperature excursion aceve 104*F is so short tha t the elevated amoient temperature cannot affect the equipment's cperatien. The Licensee has not provided any informatien to show that either condition is satisfied and has provided no qualificatien documentation.

4.7.34 Equipment Item No. 31 Level Switch Lceated in the RPCI Rcom Meceoid Model 123-2 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant lccation is 120*F and regards this as a nenharsh condition; therefere, cualification review can be deferred in accordance with criteria presented in 3ection 2.0.3.

Ecwever, as acted in Section 4.1.2, FRC censiders that this approacn does net conform to the requirements of the Guidelines unless (1) the equipment has been designed to cperate in this amcient temperature, er (ii) the duration of the temperature excursion abcVe 104*F is so short tha t the 4-62

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s TER-C5417-12 l

elevated ambient temperature cannot affect tne equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.35 Equipment Item No. 32 Level Switch Located in the Torus Area Magnetrol Model 291 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time tha t it performs its safety function. Therefore, qualification review can be de =rred in accordance with criteria presented'in Section 2.2.3.

8 4.7.36 Equipment Item No. 33 Flow Switch Located in the HPO: Room.

Barton Model 289 (Licensee reference not cited)

The Licensee indicates that the maximum temperatu:e in this plant location is 120'T and regards this as a nonharsh condition; therefere, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that etis l

l approach does not conform to the requirements of the Guidelines unless (i) tne '

equipment has been designed to operate in this ambient temperature, or (ii)

I the duration of the temperature excursion above 104*F is se short that the elevated ambient temperature cannot affect the equ,ipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.37 Equipment Item No. 34 Pressure Switch Located in,the HPC: Room Static-O-Ring Model 6NN-AA2,1-VP.R (Licensee reference not cited) i The Licensee indicates that the maximum temperature in this plant location is A20*F and regards this as a nonharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in i

Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this M2 4-63 Jeu Franklin Research Center A Dame.an af the heren enssam

. 9 TER-C5417-12 approach does not conform to. the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient. temperature, or (ii) the duration of the temperature excursion above 104*F is so 'short tha t the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided an'y information to show that either situation applies and has provided no qualification documentatien.

l 4.7.38 Equipment Item No. 35 Pressure Switches Located in the HPCI Rocm

.Barksdale D2H-M150SS (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh conditient therefore, qualification' review can be deferred. in acccedance with criteria presented in Secticn 2.2.3.

Hcwever, as noted in Section 4.1.2, FRC considers that this

. approach does not conform to the requirements of the Guidelines unless (1) the ecuipment has been designed to operate in this amoient temperature, or (ii) the duration of the temperature excursion accve 104*F is. so shcrt tha t the elevated ambient temperature cannot affect the equipment's operatien. The Licensee has not provided any information to show that either 'cendition is satisfied and has previded no qualification documentation.

4.7.39 Equipment Item No. 40

' Motor Operated valve Located in the Steam Tunnel Limitorque Model SMB-00-7.5 with Peerless de Motor (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC censiders that this appecach does not conform to the requirements' of the Guidelines unless fi) ne equipment has been designed to cperate in this ametent temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's cperatien. The W-h---

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' 4.7.40 Equipment : tem Mc. 41 Differential Pressure Indicating Switches-Located in the Reactor Building Barton Model 278 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time tnat it. performs'its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.i.41' Equipment Item No. 48 Meteri:ed Valve Actuater Lecated in the SE Corner Room Limitorque, Model Not Stated (Licensee reference not cited)

Review cf the Licensee's System 2cmponent Evaluation Work Sheet indicates that_this equipment is located in a nenharsh area prior to and during tne time

' tha t itl perf orms its saf ety function..Therefore, qualification review can be deferred in accordance wita criteria presented in Section 2.2.3.

4.7.42 Eq'aipment Item No. 51 Motorized Valve Actuator Located in the Torus Area Limitorque Model SMB with Peerless de Motor (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can ce I~

deferred in accordance with criteria presented in Section 2.2.3.

4.7.43 Equipment Item No. 55 Level Switches Lo:ated in the RER pump Room Magnetrol Model 249C-X-EP-SIMD4DC (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant lecstion is 120*F and regards this as a nonharsh condition; therefore, 1l-dA---

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qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section'4.1.2, FRC considers that this i

approach does not conform to the requirements of the Guidelines unless (i) the

~

equipment has been. designed to operate in this ambient temperature, or (11) the' duration of the temperature excursion above 104*F is so'short that the i

1 elevatedJambient temperature cannot' affect the equipment's operation. The

. Licensee has not provided any information to show that either condition is

= satisfied and has provided.no qualification documentation.

4'.7.44 ' Equipment Item No. 59' RHR Service Water Pump Motors Lccated -in the RHR pump Recm General: Electric Medel SKS21167A31 (Licensee reference not cited)

' The Licensee indicates.that the maximum temperature in this plan

. location is 120*F and'regards this as a nonharsa conditions enerefore, qualification review can.be deferred in accordance with criteria presented in

. Section 2.2.3.. However, as noted in Section - 4.1.2, FRC considers tha t this i

approach does not conform to the requirements of tne Guidelines unless (i).the equipment has been designed to operate in this amhient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the i

elevated ambient temperature cannot affect the equipment's operation. The Licensee has-not provided any information to show that either condition is satistled and has-provided no qualification dccumentation.

4.7.45 Equipment Item No. 61 Room Coolers Located.in the RHR Pump Rocm Manufacturer and Model Not Stated i

(Licensee reference not cited) 1 i

The Licensee indicates that the maximum temperature in this plant i

location is 120*F and regards this as a nonharsh condittent therefore, qualification review can be deferred in accordance with criteria presented in Sectten 2.2.3.

Ecwever, as ncted in Section 4.1.2, FRC considers that this apprcacn dees not conform to the requirements of the Guidelines unless (1) the equipment has been designed te cperate in this amoient temperature, or (ii) the duration Of the temperature excursien above 104*F is so snce: that the 4-46 E, -

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TER-C5417-12 elevated amhient temperature cannot affect the equipment's operation. Tne Licensee has not provided any information to show that either condition is

' satisfied and has provided no qualification documentation.

4.7.46 Equipment Item No. 6 2 Solenoid valves Located in the Torus Area ASCO Model HT8316B14' (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance. with criteria presented in Section 2.2.3.

4.7.47 Equipment Item No.143 Position Switches iccated in the RWCU Rocm Manufacturer and Model Not Stated (Licensee reference not cited)

Review of tne Licensee's System Component Evaluation Work Sheet indicates that this equipment is located.in a nonharsh area price te and during :3e time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.48 Equipment Item Nos. 63 and 64 Solenoid valves Located in the Reactor Building Versa Models 63:

VPS-2402, VGS-4422

-64:

VPS-2401/VPS-4422, VGS-4532/VPS-2402, VPS-2302 (Licensee reference not cited)

Review of the Licensee 's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be

' deferred in acecrdance with criteria presented in Section 2.2.3.

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TER-C5417-12 4.7.49 Equipment Item No. 65 Solenoid Valves Located in the Reactor Building ASCO Models 8302026F, HT8316B14, HTS 31614 (Licensee reference not cited)

Review of the Licensee's System Component Evaluaticn Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.50 Equipment Item No. 66 Motorized Valve Actuator Located in the SE and NW Corner Rooms Limitorque, Mcdel Not Stated (Licensee reference net cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates enat this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.51 Equipment Item No. 70 Pcsition Switch Located in the Keacter Building and Terus Area NAMCO Medel Mark I: 01:00-G (Licensee reference not cited)

Review of the Licensee's System Ccmpenent Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time tha t it performs its safety function. Therefore, qualificatien review can be deferred in acccedance with criteria presented in Section 2.2.3.

4.7.52 Equipment em No. 67 Motor Ope., ted Valve Located in the Reactor Bailding Limitorque Model SMB-000 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that tnis equipment is located in a nenharsh area peter to and during tne ti e th a t it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

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TER-05417-12 4.7.53 Equipment Item No. 71 Electric Motor Driving Pumps Located in the RER Pump Room General Electric Model 5K365AK169 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant

ocation is 120'T and regards this as a nonharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Sect ion 2. 2. 3.

However, as noted in Section 4.1.2, FRC considers that this; approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.54 Equipment Item No. 73 Room Cooler Fan located in the HPCI Room

' Buf f ale Forge Model G1:3-HV, Type 15747 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120*F and regards this as a nenharsh condition; theref::e, qualification :eview can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to the requirements of the Guidelines unless (1) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.55 ' Equipment Item No. 78 Solenoid Ball valves Located in the Reactor Building General Pneumatic Model 608KW106 (Licensee reference not cited)

Review Of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time 4-69 acu Franklin Researc.h Ce.nter At==enatth r,

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1 4.7.56 Equipment Item No. 79 Squib Shear Valves Located in the Reactor Building Pyredyne, Model Not Stated t

(Licensee reference not cited)

Review of the Licensee's. System Component Evaluation Work Sheet indicates that this equipment is locat;ed in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be l

deferred in accordance with criteria presented in Section 2.2.3.

4.7.57 Equipment Item No. 82 Solenoid Valves Located in the Torus Area ASCO Mcdel HT931614 (Licensee reference not cited) l Review of the Licensee's System Ccmponent Evaluation Work Sheet indicates that this equipment is lecated in a nenharsh area prior'to and during the time that it performs its safety function. Therefore, qualification review =an be deferred in accordance with criteria presented in Section 2.2.3.

4.7.58 Equipment Item No. 84 Sob.cid valves Located in the Reactor Building ASCO Models BVA-90-405-2A, HVA-96-082A, WPBLX831636, and HVA-96-081A (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates l

that this equipment is located in a nonharsh area prior to and during tne time that'it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.59 Equipment Item te. 85 Level switches Lccated in the Reacter Building Magnetrol Medel 402 (Licensee reference not cited)

Review of the Licensee's System Ccmpenent Evaluation Work Sheet indicates that this equipment is 1ccated in a nenharsh area prior to and during the t*.me M2 4-70 an FranMn Re.se,ren Center

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that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.60. Equipment tem Nc. 86 Sciencid Valve Located in the Reactor Building

\\

ASCO, Model Not Stated (Licensee reference not cited)

Review of the Licensee 's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time

.that it performs its safety function. Therefore, qualification review can be-deferred in accordance with criteria presented in Section 2.2.3.

4.7.61 Equipment Item No. 87 Solenoid. valve Located in the Reactor Building ASCC Model SN-681055 (Licensee reference not cited)

Review of the Licensee's System = Component Evaluation Work Sheet indicates

-that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.62 Equipment Item No. 86 Pressure Switches Located in the Reactor Building Barnsdale Models 22T-M12SS ' and B2T-A12SS (Licensee reference not cited) o

\\

Review of the Licensee's System Component Evaluation Work Sheet indicates i

that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.63 Equipment : tem No. 89 Level :ndicating Switenes Located in the Reactor Building Yarway Models 4418C and 4418CE (Licensee reference not cited)

Review of the ' Licensee 's System Ccmponent Evaluation Work Sheet indicates tnat this equipment is' located in a nonharsh area prior to and during the time "7fEl 4 71 l

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TER-C5417-12 that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in'Section 2.2.3.

4.7.64' Equipment Item No. 91 Differential Pressure Indicating Switches Located in the Reactor Building and NE/SE Corner Recms Barton Model 288-(Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs 'its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

l 4.7.65. Equipment Item No. ' 9 2

)

Radiation.2etector Located in the Turbine Building General Electric Model DWG 194X927GI (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant iccatien is 120'T and regards this as a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in

.Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approach does not conform to.the requirements of the Guidelines unless (i) the

equipment has been designed to operate in this amoient temperature, er (ii) the duration of the temperature excursien abcVe 104*? is so sheet that the elevated ambient temperature cannot af fect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no-qualification documentation.

4 4.7.66 Equipment Item No. 93 Solenoid valves Located in the Reactor Building Versa /Barksdale Models VPS-2402 and VGS-4422//D13.4150SS (Licensee reference not cited)

The Licensee indicates that the maximum temperature in tais plant location is 120'F and regards this as a nenharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in

.Section 2.2.3.

Mcwever, as neced in Section 4.1.2, TRC pensiders that this j

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TER-C5417-12 approach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104'F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.67 Equipment Item No. 97 Switchgear Located in the Reactor Building General Electric Models AME 4.76-250 and AKD-5 (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant location is 120'F and regards this as a nonharsh condition; therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this approaca does net conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that th e elevated amtient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.68 Equipment Item No. 98 480 V Motor Control Center Located in the Reactor Building General Electric Model 7700 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time t

t l

that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

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4.7.69 Equipment Item No. 101 4 kV Non-segregrated Bus Located in the Turbine Building Manufacturer and Model Not Stated (Licensee reference not cited)

The Licensee states:

TSAR Section 10.10 and Special Report No. 12. Rev. 1, Feb. 1975.

Qualification for the environment due to a.feedwater line break is not required since three diesels are available to provide emergency ac power. FSAR Section 8.2.3.1 describes the system arrangement for the standby ac power system. As a minimum, one diesel generator can be made available to provide emergency power to the affected unit assuming the HELB causes failure of the adjacent diesel and a single active failure of a second diesel unit.

The Licensee indicates that the maximum temperature in this plant location is 120'F and regards this as a nenharsh conditions therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

Ecwever, as noted in section 4.1.2, FRC considers that this j

appecach does not conform to the requirements of the Guidelines unless (i) the equipment has heen fesigned to cperste in this ambient temperature, or (ii) the duration of the temperature excursien abcve 104*F is so short that the elevated amoient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either conditien is j

satisfied and has provided no qualification documentation.

4.7.70 Equipment Item No. 112 Differential Pressure Indicating Switches Located in the NW Corner Rocm Barton Model 288 (Licensee reference 26)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

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TER-CS417-12 4.7.71 Equipment Item No. 114 Pressure Switches Located in the NW Corner Room Barksdale Model B2T-Al2SS (Licensee Reference 28)

The Licensee states:

This pressure switch is used to detect an RCIC steam line break. As soon as a break occurs, this switch will function, isolating the R2IC steam line. This would occur in less than one minute.

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with c:iteria presented in Section 2.2.3.

4.7.72 Equipment Item No. 117 Position Switch Located in the RWCU Room NAMCO Model Mark II D1200G (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Werk Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification :eview can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.73 Equipment Item No. 122 Solenoid valves Located in the NW Corner Room

'ASCO Model 830281F (Licensee reference not cited) r Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.74 Equipment Item No. 133 Motorized Damper Actuators Located in the Reactor Building Limitorque Model SMB (Licensee reference not cited)

Review cf the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time 4-75 dJ Franklin Research Center A Denensa el The Feensen utsensee

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TER-C5417-12 that.it performs its safety function.' Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.75 Equipment Item No. 145 120 V ac Reactor Protection Bus Lccated in the Electrical Equipment Room General Electric Type NAB, Style 2A, Plant E (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it' performs its safety function. Therefore, qualificatien review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.76 Equipment Item No. 146 120/240 V ac Bus Located in the Electrical Equipment Recm Cutler Hammer Medel 6C?S55505 (Licensee reference not cited)

. Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

s 4.7.77 ' Equipment Item No. 147 120/240 V ac Bus MMG Set Located in the Electrical Equipment Room General Electric Medel 5L54404A22Y30 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

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4 TER-C5417-12 l

4.7.78 ; Equipment Item Nc. 116 Electric Motor Driving Supply Air Fan Located Above the Control Room-Trane Co. Model 30 No. KALF575A (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.79 Equipment Item No. 115 Electrical Motor Driving Return Air Fan Located Above the Control Room Joy Mfg. Model 38-21-1750 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safe:y function. Therefore, qualification review can be deferred in accc: dance with criteria presented in Section 2.2.3.

4.7.80 Equipment Item No. 118 l

Solenoid Valves Located in the EVAC Equipment Room Manufacturer and Model Not Stated (Licensee reference not cited) l Review of the Licensee's System Component Evaluation Work Sheet indicates l

hat this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.81 Equipment Item No. 124 Water Chillers Located in the EVAC Equipment Room T:ane Co. Model 3E5H80 (Licensee reference not cited)

Review cf the Licensee's System Component Evaluation Work Sheet indicates that this equipment is located in a nonharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented;in Section 2.2.3.

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4.7.82 Equipment Item No. 125 Electric Motor Driving chilled Water Pump Located in the HVAC Room Ingersoll-Rand Model 0469-4154 (Licensee reference not-cited)

Review of the. Licensee's System Component Evaluatiori Work Sheet indicates that this equipment is located in a nenharsh area prior to and during the time that it performs its safety function. Therefore, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

4.7.33 Equipment Item No. 144 Level Switches Located in the Turbine Building Magnetrol Model 291-SP (Licensee Reference 23)

The Licensee indicates that the maximum tempersture in this plant

- location is 120*7 and regards this as a nenharsh conditions therefore, qua'.ification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers that this appJoach does not conform to the requirements of the Guidelines unless (i) the equipment has been designed to operate in this ambient temperature, or (ii) the duration of the temperature excursion above 104*F is so short that the

- elevated ameient temperature cannot affect the equipment's cperation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

4.7.84 Equipment Item No. 148 250 dc Motor Control Center Located in the Reactor Building Cutler Hammer Model'6002H347B (Licensee reference not cited)

The Licensee indicates that the maximum temperature in this plant locatien is 120*? and regards this as a nenharsh eenditions therefere, qualification review can be deferred in accordance with criteria presented in Section 2.2.3.

However, as noted in Section 4.1.2, FRC considers tnat this approach does not confor:n to the requirements ot' the Guidelines unless (i) the equipment has been designed to cperate in this smoien+. temperature, er (ii)

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the duration of the temperature excursion above 104*F is so short that the elevated ambient temperature cannot affect the equipment's operation. The Licensee has not provided any information to show that either condition is satisfied and has provided no qualification documentation.

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TER-C5417-12 4.8 GUMMAM CF THE EVALUATICN The following tabulations represent a summary of the results of the i

equipment environmental qualification evaluation conducted by FRC in accordance with the methodology presented in Section 3.

Table 4-1 shows the number of equipment items assigned to each NRC j

qualification catetery as - a result of the evaluation.

Table 4-2 consists of Equipment Environmental cualification Summary Forms for each equipment item, identifying compliance with the qualification requirements defined in Section 3.

The following designations are used:

X=

A deficiency with respect to compliance with a Guidelines requirement. Deficiencies result in equipment items categoriesed as unqualified or qualificatien not established, j

i O=

Assignment to NBC qualification category.

R=

Replacement of the equipment by the Licensee is planned.

Either replacement of the equipment or qualificatico by analysis er

=

test is planned by the Licensee.

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TER-C5417-12 Table 4-1 NUMBER OF EQUIPMENT ITEMS IN EACE QUALIFICATION CATEGORY NRC Numcer of Cateoory Cateoory Definition Ecuipment Items I

Equipment That Satisties the General Requirements of the DOR Guidelines and IE Bulletin 79-OlB 0

II Equipment That the Licensee Will Modify or Relocate 3

III Equipment That the Licensee Selieves To Be Exempt from Qualification 0

IV Equipment That Has Qualifi-cation Testine Scheduled But Not Completed 0

V Equipment That Does Not satisfy One or More of the.

General Requirements of the DOR Guidelines and-IE Bulletin 79-OlB 60 VI Equipment for Which Qualification is Deferred 95 148

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SUMMARY

REVIEW ECUIPMENTITEM NUMGER I l 21314 l S l 6 l 7 i $ 19 liolili 2 l l3 l idi lS l i6147 ) zS l i91 l

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SUMMARY

REVIEW I

EOUIPMENT ITEM NUMSER 1201 ZI I O ! 2312412S l 2512' ! 2912913Cl 3.12213313412513613 ? l 381 lGUICEWNE RECulREMEN*S ICESIGNA*lCNS. X - OEFIC:ENCY. L - LIMf71NG 00N0f*:CN)

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PL. ANT N AME

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PRCTASK 3

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ES 75418

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~ EQUIPMENT! TEM NUMBER I 3914C 141142141144145146147148149130 !!! I S21*JI 46 51261 $7 i GUICELNE PECUlAEMENTS

CESIGNADCNS: X - OEFC:ENCY. L - LMfTNG OCNCITCN)

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SUMMARY

REVIEW l

EQUIPMENTITEM NUM8ER 156159 i 60 t Si l 6216 3164t E 516616716816917017i 17:173174t751*64 l lGul0 ERNE REOUIREMENTS (CESIGNATICNS. X-DEriCIENCY.L-UMITING CCNCITICN) l EVfCENCE CF CU AUFICATION lXi iXI I l l I ! l l lXl l IXl l 8

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4-s TER-C5417-12 j

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CUALFCATICM OCCMET N AC TAC.

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185 4416 '

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SUMMARY

REVIEW ECU;PMENT' TIM NUMegg 7'I ?S l'?l BCI SI ? 92 f 32I 848 W 56 i Bil 4 6 I 39i30191192 ! m14. M i l 1

QUICERNE *ECUIAEMENTS CES:GNA*CNS: X - OEFC:ENCY. L - LMIT'NG CCNCr"CN) 1 EVICENCE C8 0VALF'CATICN l l l }XIX! lX! l i l l l lXl 1 l ! I RELATICN8Mtp TC EST SPEC: MEN l l l l I 1 -- ! I lI i i l i i i l i i !

j I

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4 TER-C5417-12 Table 4-2 (con *.)

'i As FRCTASK

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LDD2OT sROJEOT UTIUTY 3

1 CZ00 EQUIPMENT ENVIRONMENTAL CUAUF1 CATION DCCXET NRCTAC OATE/ ENGINEER lEB-5018 l

30-134 42478 4 - II - 6. /

/*v-

SUMMARY

REVIEW l

ICUIPMENTITEM NUMBER 196 197 198199110Cl 1011103i031104810' l10$C 71108110911101111 11121 :1311'41 GUf0E::NE AEculREMEN*S iOESIGNATIONS, X - Ogr1C:ENCY. L - UMr* LNG CCNCITICNb lEV10ENCE CF CU AUFICA*1CN i i i IXi-1 i i t i iXiXeXiXt iX i

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TER-C5417-12 Table 4-2 (CCn t. )

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SUMMARY

REVIEW l

ECUIPMENT TTEM NUMSEM

' Ill S f il61117111811196120ll21112211231124112*l126 l12'!!291129113C113111321:331 lGulCEUNE PECulPEMENTS

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1 Table 4-2 (CCnt.)

rR ;Asg gga sLAN?NAME

- GI 4~.

4c0.,1 Sn Quad Cities 1 S

1..; Franklin Researen Center

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PACJEC; UTlWTY ECUIPMENT ENVIACNMENTAi.

CUAUFICATICN DCCKET NRC TAC DAT1/ ENGINEER LE5 79018 50-234 4:478

g. u f'I M

SUMMARY

REVIEW l

EcutPMENTITEM NUMBER ll3411351:36!'3?t!36!!39 )lddle i ll ed i43 t i44ti4 51146114? ii46 ii i GUIDEUNE AECUIREMENTS (CESIONA3ONS: X - CEf1CIENCY. L - UMITING CCN0mCN1

!!V10ENCE CF CU AUFICATICN l X IX IXIXIXIX IXIX !

t-1 I I l i i i i i l AELATICNSHi8 ?C TEST SPECIMEN l l i i l i l l I i I I I l I I I I I I

!AC:NG DEG AAOASCN EVALUATED i

! I lCU AUFtED U8E ESTA BUSWE0 l I ! I

I I I I I ! = we I I l I '

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I t i i i i i ICU AUFICATICN CATEGCRY C = CATEGCRY DESIGN ATICN I

l -SCEWS SATISFY OUICEUNES I I I l l l 1 l l l l l I i l i I l f I I II -CU AL. PENOiNG MC0tFICATICN I I I I ! IOi l I I i I l ! i 6 6 I I i !

Ill-EXEMPf amCM CUAL.

l l l t l t l l l l l l l } } }

t l l l l ly -CU AL. TEST SCHEDULED i i i l l l I l l l i i i i l i i i i 6 l v -sCEwS ec NOT $AT'SF QUICEUNE$l Q ! Q l Q ! Q l Q ! ]Q ! Q{ [ j !

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l TER-C5417-12 1

i 5.

CCNCLUSIONS The tabulations presented in:Secticn 4.9 represent a summary of the r

results of the equipment environmental qualification (EIQ) evaluation conducted by FRC in accordance with. the methodology presented in Section 3.

The evaluations 'are ' based on ' the. available qualification documentation J

provided by the Licensee, complemented in several cases by other relevant technical information.

"'he major deficiencies that have been identified are shewn in the Iquipment Invirenmental Oualificatien Summary Forms ' (Table 4-2).

The. review has shown that qualification documentation for many equipment items -

is inadequate er ncn-existent, and that additional infermatien is essential.

The OCR Guidelines require ene Licensee to have ongoi.ig pecgrams te.

review surveillance and maintainance records to assure that safety-related equipment that exhibits age-related degradation be identified and, if necessary, replaced. No evidence of such programs was included in :he Licensee's' submittal.

l l-f L

l A. -

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TER-C5417-12 6.

REFERENCES 1.

FSAR Section 10.10 2.

Becntel Radiatien Study-3.

FSAR Table 9.2.3 4

4.

FSAR Figures 5.2.15 and-5.2.16 5.

FSAR'Section 6.2.3.2 6.

Special' Report No.12, Rev.1, February 1975 7.

Limitorque 600461-B0003. qualification Test Report 3.

Limiterque 600426-20009 9.

F-C2232-01 10.

F-C3441 11.

OV-145C3006 qualificatien resign verification 12.-

FSAR Section 6.2.7.2 13.

FSAR Table 5.2.1 14.

FSAR Secticn 6.2.4.2.0 15.

PEP (42963 Tes,t cresser Felief Valve Actuater 16.

FSAR Secticn 6.5 17 FSAR Section ' 6.2. 3. 2 13.

Report Section 4.4 19.

Peper Section 4.3.6 20.

Report WCAP 7410-L, Test en Limiterque valve Meter Cperaters 21.

GE Test Report No.145C3006, qualification Oesign verification File 22.

GE Test Report No. OV-1453008, qualification Oesign verificaticn File 23.

GE Test Report No.159C4361 and Wyle Test Report No. 43235-1 24.

Report No. 338164 (F-C2485-01) Tests of Limitorque valve Cperator 25.

Report No. F-C3791, Franklin Institute Research Lacoratories 26.

GE Test Re por t No. OV-145C3009, Qualification resign verificatten File I*T 3arten Rep.

27. -GE Test Repcet No. OV-145C3004, qud ificatien Cesign verification File

~

6-1

.L:, Panklin Researen Center s um m v m.n m a

v-ee---v,.

.=e-,-w,-vw,-wen----

e v,- m

. ea-wrot-er,-

e me r -ge r,-,e-*-w-

mer

-,-ee3+--+t-+

,e+--,

- e - e n a av-e m-v * *,

.etw,vcc-e-y e-ve,+r-

=e-t - w--- te s m e

TER-C5417-12 i

i 48.

GE Test Report No. CV-145C3010, Qualification Design Verification and AETL Report 596-0398 29.

Letter from G. Lainas, NRC, to A. Schwencer, NRC, February 19, 1980.

Subject:

Electrical Equipment Environmental Qualification, including DCR Guidelines.

30.

Letter from N. C. Moseley, NRC, to B. H. Grier, J. P. O'Reilly, J.

G. Keppler, K. V. Seyfrit, R. H. Engelken, NRC, September 29, 1980.

Subjects-IE Supplement No. 2 to Bulletin 79-013, Environmental Qualification of Class 1E Equipment.

31.

Letter from N. C. Moseley, NRC, to B. H. Grier, J. P. O'Reilly, J.

G. Keppler, K. V. Seyfrit, R. H. Engelken, NRC, Cetober 24, 1980.

Subject:

IE Supplement No. 3 to Eu11stin 79-013, Environmental Qualification of Class 1E Equipment.

32.

U.S. NRC Memorandum and Crder (CLI-80-21) pursuant to the Petition for Emergency and Remedial Relief filed with the NRC on November 4, 1977 33.

Ccmmonwealth Edison Company, " Response to NRC IE Sulletin 79-01B Environmental Qualification of Class 1E Equipment for Quad Cities 1 and 2,*

Revision 1, November 1, 1980.

34.

NUREG-0588, " Interim Staff Position on Invironmental Qualification of Safety-Related Electrical Equipment," December 1979.

35.

Memorandum for V. D. Thomas, NRC, through D. W. Hayes, NRC, from J.

Hughes, NRC, Subjects Screening Review of Licensee Responses to IE Bulletin 79-013 and Summary of Inspections of Installed Systems at Quad Cities Unit 1 and 2 Facility - Docket No. 50-254; April 14, 1980.

36.

S. P. Carfagno and R. J. Gibsen, 'A Review of Equipment Aging Theory and Technology," Electric Power Research Institute Report NP-1558, i

September 1980.

l l

l I

d -h-0 ~,'

..:. Franni1n Researcn C. enter 4 d on a h. r a.a a,n na.

e

. ~

TER-C5417-12 APPENDIX A - ENVIRONMENTAL SERVICE CCNDITIONS The Licensee has previded detailed information (33] concerning environmental :enes and expected environmental service conditions in all locations within the plant. Figures A-1 and A-2 shew the inside-centainment profile envelopes provided by the Licensee. The plant's centainment spray system uses demineraliced. water rather than a chemical spray solution. This is considered in the Licensee's analysis.

The specific environmental service conditions corresponding te plant zones are shown 'in Tables A-1 through' A-3.

The Licensee states that, where envircemental cceditiens are maintained by HVAC equipment, the T/AC system ia previded with redundant ecmpenents and/cc a backup pcwer supply for reliaele operation.

Saf ety-related r/AC systems are provided fer the fc110 wing areast control rocm, cable spreading rocm, battery recm, computer recm, and a.

electrical equipment recm

.b, standby diesel generator rocm c.

HPCI recm d.

corner recms.

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TER-C5417-12 QW WW

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MAXIMilM Et1V i ltOt1M I:tITAI, COtlIII TI OtlS IHS It)E Tile DilYWHI.I.

FOI.I AMitlG TIIM POSTtil ATEll I.OCA/IIEI.It i

I Ite I a L i ve Cont.ainmenL Gamma Submeryence

~

^

Tengica at tin e Pressitre litim id i ty Spray _ _

lladiation

- El eva t iosi 2111 F 6.1 psia 100%

Ik:mi nera l i zed I

day-4.3x10 -rads 583'-0" water 3tl day-1.0xlo rads g

1 1 year-1.1x10 rads 4

e Y

S

?

FIGURE SUPPLIED C

BY THE LICENSEE i

i L

~

4 f

i Table A-2 b.

n YN /

H AX I Hilti ErlVi ttotattl{tlTAl. CollillTIOllS f(=

OtITS I DE Tile DitYtdI:!.I. FOI.I.OW I f1G Tllli

.J u POSTill.ATEI) 18 E1.11 ACC I DEtITS es d' E.

i[il s

Ha x imuin Ha x innum iteLative 3

h Preusnare Teinpe ra tu re -

Ilism id i ty Pipe lireak (psia)

(*P)

_(% )

2 An ca T. un compa n't nient IIPC I steam 27.0 242 100

( n eg itui of pos t u t at ed itCIC St eam

'l 1ine lis cat )

?

Co n e sps ay/itC e c room ItCIC utuam that evaluated - Equipment in tinis room not regiaired for itCIC steam Iine break i

^

Steam tunnel Main steam 27.0 242 100 Peedwater itCIC steam 1111 0 11 lie a t excliainiger and itWCtl Ih>L evaluated - Only two containment _ isolation lio l d i ng guimg

oom valves required to function.

Qualification wi1I meet conservatively assumed inside drywel1 i

conditions.

iii.sh-pi essum e lieater itain steam tiot evaluated - No equi miesit. which is required t

laay Feedwater to f t:inction is located in liais area.

laU in I

Turbine l>u l l d i eng Main steam th>L evaluated - No equipment which is required E el 615'-6" to function is located in this area.

O noith of Column G, i

leetween Columns 9 and 11

.il t41 I5 dild I6 flGURESUPPUED ELY YHEIJCENSEE i

b'f)'

,1,E it >

$s'9 T.atste A-2 (continued) la

m 50 Ea 4

Ha x i nnum Maxionum Relative Pressure Tennpe ra ture ilumi d i ty

_ psia)

(*F)

(t)

Aiea Pipe Break

(

ituac t or tee.1 pump Feedwater fla t evaluated - tio equipment which is required i

ioom to function is located in this room.

Tut taine t>uilding Feedwater 110t. evaluisted - tio equipment which is required

{

1 el 595'-0" t.o function is_ located in this area.

anea sonth of tin i t 1 pump room and nortin i

ut tin i t 2 gum.p room i

liiesel genetator room Feeduater flot evaluated - Qualification for the environ-ment due to a postulated feedwater line break is init required since three diesels are available to provide emergency ac power.

.-a El A,

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o j

FIGURE SUPPLIED h

BY THE LICENSEE 4

i

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YM{i DitYWEl.l. I'OI.I.(Ri t tlG Tile l'OSTill.ATED I.OCA I$

flAXIttt1M ItADI ATIOtt SotaltCES aa U

fi listegrat eil Dose f.evels ( rails )

U Asca Soti r ce

1 l'a y 30 Days 1 Year

!O 7

7 7

8,j Tin ins S t.

l.Sx10 3.2x10 3.9x10 6

ites iittia l lica l removal corrier rooms S t>

2.4x10 9.4x10 1.7x10 6

tii'C l inom MS 6.6x10 1.6x10 1.7x10

~

Come ugiray/itCIC rooms MS 6.6x10 1.6x10 1.7x10 S

S 6

st eam tunnel MS 3.1x10 8.5x10 1.6x10 6

6 It< ac t or 1.u i lili ng el 595'-0" Itw 2.Sx10 7.8x10 1.4x10 6

leeact..r liis i liling el 623'-0" CA

6. ti x 10 1.6x10

1. 6 x 10 '

6 it. act or lois i lili ng el 647'-6" CA

6. ti x 10 1.6x10 1.6x10 6

6 tec.ict or leis i lil i ng el 666'-6" CA 6.tix10 1.6x10 1.6x10 Sules uns ion [xiol 1 i < lit i el S I'

=

Itu a steact or water lteaClalr Siedm MS a

3 CA - Coint a i simenit airborne A

FIGURE SUPPUED E

9tf THE UCIWSEE

{

TER-C5417-12

' APPENDIX B LISTING OF SATETY-RELATED ELECTRICAL EQUIPMENT This appendix lists groupings of safety-related electrical equipment for

. Quad Cities. Nuclear Generating Station Unit 1.

Equipment item numbers in the list are used. in the Equipment Environmental Qualification Summary Forms and in the equipment _ qualification discussions in Sect' ion 4.

The list was generated from the Licensee's System Component Evaluation Work Sheets (SCEWS)

{

in Reference 3'3.

For each. item, the list identifies the manuf acturer and medel number, plant location, SCEws numcer, applicable qualification 7

references,' and TER section where the item is discussed.

n h

l I.

b 31 4..' Franklin Resesren Center A om a ~>ee-enan,m,

4 1

+,=-~r e

g

(

9er y r g=

g*t y

e e -v

= -e -

p-%'=~r,

n-w.<t'=ewy e y4-,*-c-*

r - ve,, v e c,- wt ewvvge-m,=eair=.,,+--w,*

9+ee.

een ree.<

, = e -- ew e nmwe i + = r as-nu

TER-C5417-12 1

EQUIPMENT TER ITEM ITEM SCIWS CUALIFICATICN SECTION NC.

DESCRIPT!CN LCCATION NO.

REFERENCES NC.

'l Temperature _ Switches.

RWCU' 1-6 None 4.6.1 Manufacturer and Room Model Net Stated 2

Electric Motor Corner 7-9 None 4.6.2 Oriving Pumps.

Rooms 190-193 General Electric SK6338XC23A

$K6336xC193' 3-Motorized valve NW and SW 10-12 20 4.6.23 Actuator Corner l

Limitorque/?eerless.

Ecoms ac Motors SMB-0-25.

4 Motorized Valve Reactor 13-14 20 4.6.24 Actuator Building Limitorque/ Peerless ac Mctors SMS-0-15 5

M.otorized valve Reactor 15-18,-

7 4.6.25 Act'2ator Building 142-143 Limitorque/ Reliance 1

ac Motors SMB-2-40, SMB l

6 Motori:ed Valve Torus 19-21 7

4.6.26 I

Actuator Area Limitorque/ Reliance ac Motors SMB-000 7

Pressure Transmitters NW and SW 22-24 21 4.6.19 General Electric Corner GE/Mac 551 Rocms j

4532K11001

)

3 F1:w Transmitters NW, sed SW 25-27 Sene 4.6.19 Cener s*. Electric 0:ener

?/pe $53 Roems 453 K-43001 9

Ficw Switches

!M and 3W 29-30 22 4.6.20 3ar-:n Corner 239 Rocms 8 32 a FranWin Researe.n.Ce.nter

% at v n 6

m 4

,r 3 - yy

+ -

ei,

.w

.o 4-,

9.~

,y.,

,,4 c

,,4.,,-.w.....

.,,r...,-r.

m

,,vr_

..,.ws,

.mw.,,,...,,,-w.

.,w..,+.~..v,.e.

F TER-C5417-12 ECUIPMENT TER

- I*EM ITEM SCIWS QUALIFICATICN SECTICN NO.

DESCRIPTION

- LCCA?!CN -

NO.

REFERENCES NO.

- 10' Pressure Switches NW and SW 31-34 Ncne 4.6.3 Mercentrol Corner CA-7043-804 Recms L

. 11~.

Step valve EPCI Recm 35 Ncne 4.7.19

- Manuf acturer - Net Stated 179250H02D4

' 12.

Motori:ed Valve HPCI Recm 36,43,44,46, Ncne 4.7.20 Actuator 52 Limiterque/ Peerless de Mctors SMB-2 SMS 3 SMS-4 SMB-000 0

uct ri:ed valve

rywell 37,38 7

4.6.4 Actuater Limiterque/Peliance ac McCor SMB-1 14 veteri:ed valve Mrus Area 39 Ncce 4.6.5 Actuator Limitorque/ Peerless de Meter SMS-1

- 15

.Meterized valve HPCI Recm 40,49,50,51 Ncne 4.7.21 Actuator Limiterque/ Peerless de Motor SMB-0 SMB-000 16 Meteri:ed valve Steam 41,42, Ncne 4.7.22 Actuator

?annel 466, 467 Limitorque/ Peerless de.MCCCr SMB-3-30 SMB-00' 5

3-3 4cen sesrens.n. C.u.ter F 2nklin Re en t

a v--

g.r--

v-p. wwy ev eree--rs-v y~ -w

,,e',yy

,-.++

-.=w--.-.a,<

c c.e+e-+..,-,-weev-

-w,-

=,

,r,-e---ww,t-.w>r..-,.,.r--,...-~=s-e,r.-,-ww-ew,--

v-ww-ww-%crrs

TER-C5417-12

' J ICUIPMENT TER ITEM ITEM SCZWS OUALIFICATICN SECTICN NO.

-DESCRIPTION LCCATICN NO.

REFEFINCES NC.

17 Motorized Valve HPCI Room 45 None 4.7.23 Actuator Limiterque/ Reliance de Motor 1

SMB-0 l

la Solenoid. Valve HPCI Recm 47-48, None 4.7.24 J

ASco 53-54 830281F

- 1 19

' Differential Pressure Reactor 55-56 None 4.7.1

' l Indicating Switch Building 3arten 288 20 Flew Transmitter HPC: Recm 57 Ncne 4.7.25 General Electric GE/Mac 553 4532K13001

. 21-Pressure Transmitter HPC: Rccm 38 Ncne 4. "'. 2 6 General Electric GE/Mac $51 4532K11001-22

_ Temperature Switches HPC: Recm 59-68 Ncne 4.6.6 United Electric Centrols 88B 2 3 '-

Pressure Transmitter HPC Recm 69 21 4.7.27 General Electric GE/Mac 551 50-551032CAAY1 24 Pressure Switches Reactor 70-72 None 4.7.2 Barksdale Building 32T-A12SS 25 Electrid Motor Oriving HPCI Rocm 73 None 4.7,08 W ecine Gland 3eal Cendensate Orsin Pump General Electric

$8225A3525 3-4 Frankjin Research Cen.ter

.. t.

D m.ea w w enon.n u e

w c-

,,p.,-

g

---wwe-y w

w

,~ewvy c w

-,-.---%,,,y,.-%r,,

,w--,w<,--er--eme-ewer +*-,+,.

,*e-,,,.r..ew.-,--*e-ww. wee,ee*

e,w.,-

TER-C5417-12 TER EQUIPHENT ITEM ITEM SCEWS CUALIFICATICN SECTICN

'NO.

DESCRIP* ION LOCATION NO.

REFERENCES NO.

26

' Electric Motor HPCI Recm 74 None 4.7.29 Cr;tving Gland Steam Exhaust Tan General Electric SBC74AB2193 27 Motor Speed Changer HPCI Room 75 None 4.7.30 General Electric j

GE5BC26ACJ89 23 Mcter Gear Unit MPCI Recm 76 Ncne 4.7.31 General Electric SC 14019A11620 29 Electric Mctors HPCI Recm 77,73 Ncne 4.7.3 Criving oil Pump General Electric

!CO218E252 5CD326E758 30 HPCI Meter Centrol HPCI Recm 79 Ncne 4.7.33 Signal Ccnverter General Electric

'357513TC103 31 Level Switch HPCI Rocm 90 Ncne 4.7.34 Mercoid 123-2 32-Level Switches Torus 35,36 None 4.7.35 Magnetrol Area 291 33 Flow Switch HPCI Room 87 None 4.7.36 i

Barton 199 34 Pressure Switch HPCI Rocm 38 Ncne 4.7.37 Static-0-Ring 6 mi-AA21

'v RR 35 Pressure Switenes HPCI Reem 39-90 Ncne 4.7.38 3ar<3 dale C2H-M150SS 3

'2

..." F.mnxlin Researc.h Center h a N < no -.

--,.=w-.<nr<,,,,.w-..,,,4

TER-C5417-12 EQUIPMENT TER ITEM ITEM SCEWS QUALIFICATICN SECTICN

- NO.

DESCRIPTICN

.LCCATICN MO.

REFERENCES NO.

36.

. Solenoid valves Crywell 91-96 Ncne 4.6.7 Allied controls-Gould 320X-39, 320X-30 37 Safety Relief Valve Drywell 97,98 15 4.6.3 and Solenoid Cresser Industries C5450 -

38 Electremagnetic Drywell 99-102 15 4.6.8 Relief Valves'and Solenoid valves Dresser Industries 1525VX 19 Motorized Valve Drywell 103-104 20,24 4.6.27 Actuater.

Limitorque/ Peerless ac McCor

.tdel Not Stated 40-Motori:ed Valve Steam 105,106 None 4.7.39 Aca;uater 3:nnel -

Limitorque/ Peerless de Meter SYB-00-7.5 41 Differential Reactor 107-116 None 4.7.40 Pressure Indicating Building Switches Barton 273 42 Temperature Switches Steam 117-126 None 4.6.28 Fenwal Tunnel 17002-40 43 Pressure Switch SE Cerner 235-237 Ncne 4.6.10 Static-C-Ring Fcom 12NN-KX213 'lX 44 Motori:ed Valve NE and SZ 127-129 20 4.6.29 F

Actuator Corner Limiterque/ Peerless Recms ac McCor SMS-0-13

-SMS-2-60 l

SMB-:-40 3

gg 3-6 J.;, FrankJin Research Center i

4da aw heAwwam.oue s

.,v_.,~....-

.,,. _., ~,... _...,... - _,, - _.,...- _. _.-

~-.-.-._.._.._..._.-_,..._....._...---__,.D

-. i TER-C5417-12 EOUIPMENT.

za ITEM ITIM SCEWS QUALIFICATICN SECTICN NO.

DESCRIPTION LOCATICN NO.

REFERENCES NO.

45 Motorized Valve

- NE and SE 130-132 None 4.6.30 Actuators.

Corner Limitorque/ Motor Rooms Not' Identified SMB-2-60 46

- Motorized Valve Torus Area 135-136, 20 4.6.31 Actuator 147-148,

. Limitorque/ Peerless 152-135 ac Motor SM3-dOO-5' SMS-4T-150 SMB-3-100 SMB-0-10 47 Motorized valve NE and SE 133-134, 7

4.6.32 Actuator Corner 137-138, Limitorque/ Reliance Rooms 194-197 ac Motor SMS-2-40 SM3-0 SMB-1 48 Motorized valve SE Corner 139 Ncne 4.7.41 Actuator Room Limitorque/ Peerless ac Motor Model Not Stated 49 Motorized valve Reactor 140-141 20 4.6.24 Actuator Building Limitorque/ Peerless ac Motors SMB-0-15 50 Motorized Valve Torus Area 144-146, 7

4.6.33 Actuator 149-151 Limitorque/ Reliance ac Motors SMB-5T-150 SM3-2-40

'5; Motorized valve

' Torus Area 156 Ncne 4.7.42 Actuator Limitorque/?eerless de Mctor a

SMB h

B-7 4>.n:in Resea.re.n Center

..; eran

.a a s. r e,

s v, - n -,

,re,-

r.v

--w.

s.

-a-r--,,w.,

a,n-.--rw-w-n ren---,w w,

-w,-en,-,w.,-,,--,,-r-,,,--,ne,-e--,n..n,,--+,--ens

1 TER-C5417-12 EQUIPMENT TER ITEM ITEM EC:'WS QUALIFICATICN SECTION NO.

DESCRIPTION _

LOCATION NC.

REFERENCES NO.

52 Motorized valve Drywell 161-162,

'None 4.6.34 Actuator 157-158 Limitorque/ Reliance ac Motor SMB-3

'SMB 53 Pressure Transmittets NE and SE 163-165, None 4.6.35 General Electric Corner 186-189

'GE/Mac 551 Recms 54 Flow Transmitters NE and SE 166-170 None 4.6.21 General Electric Corner GE/Mac 553 Rooms-55 Level Switches RHR 171-173 Ncne 4.7.43 I

Magnetrol Pumo Rooms

.249C-X-EP-SIE14DC 56 Differential Pressure NE and SE 174-176 None 4.6.11 Indicating Switches Corner Barten Recms 299 57 Pressure Switen NE and SE 177-182 Ncne 4.6.22' Mercoid Corner GN-L-3 Recms 58 Meteri:ed valve Steam 159,160 Ncne 4.6.9 Actuators Tunnel Limitorque/ Peerless de Motor SM&a00 59' RHA Service Water RER Service 183-185 None 4.7.44 Pump Motor

. Water General Electric Pump Room 3K821167A31 60 Differential Pressure NE 198-200 Ncne 4.6.12 r

Switches Corner 3arton

-Room Model Not Stated 61 Room C:oler PJtR 201-203 None 4.7.45 Manufacturer and Pump Recm Mcdel Not Stated l

3~0

.... Franxiin Research Cen.ter 4 :.a.aa e se r.a a w ma I

s

-.m TER-CS417-12 EQUIPMENT TER ITEM ITEM SCEWS QUALIFICATICN SECTION NO.

DESCRIPTICN LOCATICN NO.

REFERENCES 11 0.

f

- 62 Solenoid' Valves Torus Area' 205-206, None 4.7.46 j

ASCO 208,226 HT9316B14 63 Solenoid Valves Torus Area 207,209, None 4.7.48 versa 210,213 VPS-2402 VGS-4422 64 Solenoid Valve Reactor 211-212, None 4.7.48 Versa Building

' 217 VPS-2401/VPS-4422 VGS-4532/VPS-2402 VPS-2302 65.

Selenoid valves.

Reacter 214-216, Ncne 4.7.49 ASCO Building 221-225 3202006F HT931614 ET8315314 831614 66 Meteri:ed Valve SE and NW 204,493, Ncne 4.7.50 Actuator-Ccener 490 Limiterque/ Peerless Roems de Motor Model Not Stated 67.

Motorized Valve Reactor 227 Ncne 4.7.52 Actuator Building Li:nitorque/ Motor Not Identified SMB-000 68 Pressure Switches Reactor 228-234 None 4.7.3 Static-O-Ring Building 12N-AAS-PP 69 Pressure Switches Reac ce 247-250 Ncne 4.6.16 Static-O-Ring Building 12N-AA5-PP 70 Positien Switch Reactor 23a-242, None 4.7.51 NAMCO Suilding 325-329, Mark 22 D1200-7, Terus Area 342-344 W&

=a. 9

~

.... Fmnx;in Research Center

+

r >mm a % F man esaue o

o es -

,-c, yj,m.,-

v.y-p.-,

+yw---,-v+-

r e- -r-r -

g-m--

w s-e * -r* *-+ re P e--we w--se--.e-v-t++-+-

+vw - w v

=-r-*~en-

' - + * *

<w=-

-mw-

-e e*

-tw==-*

=

~_.

2 TER-C5417-12 I

)

EQUIPMENT.

TER-ITEM ITEM SCEWS

' QUALI?ICATICN SECTICN NO.

DESCRIPTION LCCATION-NO.

~ REFERENCES NO.

71

- Electric Motor

' RHR 286-287 Ncne 4.7.53 Driving Pumps Pump Rocm General Electric

- SK365AK169 72 Electric Motors Corner' 288-290, None 4.6.14 Driving Fans Rooms 292-294 General' Electric 5K213AK2476

$K184AL2151 i

73 Recm Cooler Fan HPCI Recm 291 None 4.7.54-Buffalo Forge G123-HV' Type 15747..

74 Electric. Motor Diesel 295-296 None-4.7.6 Driving Fan Room Manufacturer and Medel Not Stated

- 75 Eleceric Motor Diesel 295-298 Ncne 4.7.7 Driving Pump Room General Electric 5K182BL315 Type K 76 Level Switch Diesel 299,302-303 Ncne 4.7.5 Magnetrol Room A-103F-EPf/P 77 Solenoid valve Diesel.

300-301 None 4.7.8 ASCO Room 8211C89 1

- 78 Solenoid Ball valves Reactor 304-307 None 4.7.55 General Pneumatic Building 608KW106 79-Squib Shear Valves Reacter 308-311 None 4.7.56 Pyred/ne Building Medel Net Stated

! Motorired valve Drywell 312-313, 20,24 4.6.36 Actuator 464-465 Li:nitor:;ue/ Peerless ac Motor SMB-1-40, SMB

_%7 3-10

..a eranklin Research Center 4 0m on a n. r nma m b

v=--t y tm rm * - v 1 " -*

f -e m y-g r-t y e s-* Tre --w w w

re g y -*-

m ' werm aw w w W-t-=e* %-e n W t-m-2 -w ws w v* - w w-- w, ' +e= w e t w

,w=~w w-r ewe m* w w er-- -*-w = W eraw

===e*=--w~~~ae

- = = = *

~ -. -

TER-C5417-12 EQUIPMENT TER' ITEM ITEM SCIWS QUALIFICATICN

- SECTICN NO.

DESCRIPTION LOCATICN NO.

REFERENCES NO.

81

~ Motorized Valve RWCU Rocm 314-315 None 4.6.15 Actuator Limitorque/?eerless de Motor SMB-82 Solenoid Valves Torus Area 316-319 None 4.7.57 ASCO BT831614' 33 Mctori:ed valve Torus Area 322-324 20,24 4.6.37 Actuacor and Inside Limicorque/?eerless Drywell ac Motor SMB-000-5 84 Solenoid valves Reactor 331-334, Ncne 4.7.38 ASCO 3uilding 338-341, HVA-90-405-2A 345-346

i?ELX3 3163 6 EVA-96-082A HVA-96-081A 35 Level Switches Reactor 335-337 Ncne 4.7.59 Magnetrol Building 402 36 Solenoid valve Reactor 320 Ncne 4.7.60 ASCO Suilding Model Not Stated 87 Solenoid Valve Reactor 321 Ncne 4.7.61 ASCO Building SH-681055 38 Pressure Switch Reactor 347-351, None 4.7.62 l

Barksdale Building 365-367, 32T-Ml:SS 369,370 32T-Al2SS 39 Level Indicating Reactcc 330-333, Ncne 4.".63 Swi:ches Building.

357-361 Yarvay 4413C 4413CE d

...a Franxiin Researen Center

~ 33

,~ ~*

s : aman a m ma smasa e

,_--w_

e

,c p,,,,y-,

.,,,,y y

.y-,,_

...,,.-,.,,,,%.y.

c

, w m,

g.,,,.

m,.,,,,~._,,.-._wm_--

,--,.,m..

1 TER-C5417-12 4

EQUIPMENT TER

. ITEM ITEM SCEWS QUALIFICATICN SECTICN NO.

DESCRIP"'ICN LOCATION NO.

REFERENCES NO.

90 Level Indicating Reactor

354U356, None 4.6.17 Switches Building 362-364 Yarway 4418C t

4418CE 91 Differential Pressure Reactor 371-378 None 4.7.64 1

Indicating Switch Building.

.Barton and NE/SE 288.

Corner Rooms 92

' Radiation Detector Turbine 391-392

.Ncne 4.7.65 General Electric Building DWG 194X927GI-93 Solenoid Valve-

' Reactor 393-395-Ncne 4.7.66 Versa /Barksdale Building VPS2402/

~

VGS4422//D1H-A150SS 94.

Diesel Auxiliary Diesel.

404-406 None 4.7.9 Centrol Panel Room Ideal Electric &

Manufacturing S.O.'No. 267777 95 Excitation Cabinet Diesel 407-409 None 4.7.10 Electromotive Div.

Room of GM 9474.

96 Diesel Generator Diesel 410-412 None 4.7.11 Electromotive Div.

Rooms of GM-Model Not Stated 97 Switchgear Reactor 413-416 Ncne 4.7.67 General Electric Building l

AME 4.76-250 AKD-5 98 480 V Meter Reacter 417-419 None 4.7.68 Centrol Center Building General Ziectric 7700 l

d&

..L Franklin,Research Canter 3-12 a c ae = Ana.e==.

TER-C5417-12 EQUIPMENT TER ITEM ITEM SCEWS CUALIFICATICN SECTICN NO.

DESCRIPTION LOCATICN NO.

REFERENCES NO.

99 480 V Motor Reactor 436-441 Ncne 4.3.1 Control Center

. Building General Electric 7700

- 100 Engine Control Panel Diesel'

~ 425-427 None 4.7.12 Electromotive Room Div. of GM Model Not Stated 101 4 k7.Non-segregated-Turbine 428-429 Ncne 4.7.69 i

Bus Building Manufacturer and Model Not Stated 102 D/G Secondary Diesel 430-432 Ncne 4.7.13 Centrol Panel Recm Ideal Electric S.O. No. 267777 103 D/G Neutral Diesel 433-435 None 4.7.14 Grounding Panel Room r

General Electric 208419-68P 4KVA-5 104 Battery Charger Battery 442-443, Ncne 4.7.15 Gould Charger 449-450, GRF240T100X Rocs 458-461 GRF120T100X GRF24S25F30X 105 250 7 de Motor

- Battery 444-445 25 4.7.16 Control Center Charger Cutler' Hammer Room 6002H347B 106 DC Battery-Battery 448,451, None 4.7.17 Gould Charger 456-457 FPS-25 Room FPR-13 DPR-9 107 IC Distributor 3attery 452-453, Ncne 4.7.19 Panel Charger 462-463 Cutler Hammer Recm i

Medel Not Stated A1 3~13

..) Franklin Resesren Center

< oms.oe an ne rme,e.ana 9

m.-

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TER-C5417-12 EQUIPMENT TER ITEM JTEM SCEWS QUALIFICATICN SECTICN NO.

DESCRIPTION

' TATICN NO.

REFERENCES NO.

108 DC Distribution Fraetor 454-455 None 4.3.2 Panel lding Cutler Sammer Model Not Stated 109 Motorized valve Drywell 379-387 None 4.6.39 Actuator Limitorque/ Reliance

&c Motor SMB-2 SMB-000 110 Motorized Valve.

Steam 329,330 7

4.6.40 Actuator Tunnel Limitorque/ Reliance ac Motor-SMB-2-40 111 Solenoid valves Torus 218-220 None 4.6.58 Versa Area VPS 2502 VGS 4522/vGS 4422 112 Differantial Pressure NW Corner 470-472 26 4.7.70 Indicating Switch Room Barton 288 L

113 Temperature Switches NW Corner 473-482 27 4.6.38 Fenwal Room 17002-40 114 Pressure Switch NW Corner 484-487 28 4.7.71 Barksdale Room B2T-A12SS 115 Electric Motor Driving Above 397 None 4.7.79 Return Air' Fan Control Jo'/ Mfg.

Room 38-21-1750 116 Electric Motor Driving Above 396 None 4.7.78 Supply Air Fan Control Trane Co.

Room 30 No. KALF575A W-J-3~14

..k Frankiln.N n an.Cen.ter Researen

:=.aa

. -- =

y w,

e

-rri-w v

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-r-vr---w

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.s TER-C5417-12 EQUIPMENT igR ITEM ITEM' SCZWS QUALIFICATICN

. SECTICN j

NO.

DESCRIPTICM LCCATION NO.

REFERENCES NO.

, 117' Position Switch RWCU Roca 390 None 4.7.73 NAMCO Mark II D1200G 118 Solenoid Valve HVAC 403 None 4.7.80-Manufacturer and Equipment Mcdel Not Stated Rocm 119 Cable outside 505-506 None 4.6.57 General Electric Drywell t

vulkene ISI 57275 120 Cable outside 507-514 None 4.6.46.

+

Si:nplex Drywell Poly Nylon Insulated Shield and Plastex Jacket 121 Cable, Jacket Inside 503-504 Ncne 4.6.41 Si:nplex Drywell

. Rubber Insulatien, PVC Jacket

- 122 Sciencid Valre NW Corner 468,469, Ncne 4.7.73 ASCO Recm 488-489 8302817 123 Electrical Drywell' 517-520 Ncne 4.6.55 Penetration GE-ME3S Model Not Stated 7

124 Water Chillers HVAC 401 None 4.7.81 l

Trane Co.

Equipment 3E5E80 Roca P

125 Electric Motor Driving EVAC 402 Ncne 4.7.82 Chilled Water Pump Equipment Ingersoll-Rand Recm 0469-4154 106 Cable Outside 491-492, Ncne 4.6.40 General Electric Drywell 499-502, Butyl Ru'cer

- 515-516 e

Insulati:n, PVC Jacket:

Orcss Link Polyethy'ene e

4 s-

~l0

..E5nvlin Researcn. Canter 4 cm.on o = von 9

e p +-

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TER-C5 417-12 '

i EQUIPMENT TER i

ITEM ITEM

- SCEWS

- QUALIFICATICN SECTICN NO.

DESCRIPTION

' LCCATION

~ NO.

REFERENCES NO.

l 126 (Continued) -

Insulation,.

1 Neoprene Jackets Rubber Insulation, j

Hypalon Jacket 127 Cable Inside 497-498'

- None 4.6.43.

General Ilectric Drywell Polyethylene Insulation,

-PVC Jacket 128 Electric Cable Not Stated 493-494

- Nene

' 4.6.44 l

~

Simplex:

LPolyvinyl Chloride

. Jacket and Butyl Rubber Insulation -

129 Electric Cable

' Outside 495-496.

None 4.6.45 Simplex Drywell Anhydrex XX.

' t

' Plastic Insulation and Jacket

'i 130 Terminal Blocks Inside 521-524 Ncne 4.6.56 Allen 3radley' Drywell-Medel Not Stated 131 Pcsition Switch Drywell

- 388-389 Ncne

' 4.6.54 NAbCO EA-08011100 132 Electric Air Heater Reactor-251-253 None-

- 4.6.47 E. L. Wiegland-Building I

Model Not Stated

]

133-Motorized

- Reactor 254-259, None 4.7.74 Dampet Actuators Building 263-264 Limitorque SMB 134 Exhaust ran Reactor 260-262 Ncne 4.6.43 New York 310wer

- Suilding E4966

- 135 Flow Transmitter Reactor 265-267 Ncne 4.6.49 Leeds E'Nerthrup Building 1912-3-21-0-0000-3300-0300 MTIhs j

3-16 a,mr-. nanWin Research Center 4 c= ion er he nea.snin ma.

)

i l

y(+r=1

+5t="

W r-ve we'*y-w er

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NS

='-f'WeYvWT@w1WP-99?"-A

' f M # "W'F Vrg eywey

~

. -. ~_

s TER-C5417-12 i

' EQUIPMENT TIR ITEM ITEM SCIWS QUALIFICATICN

.SECTION NO.

DESCRIPTICN LOCATICN NO.

REFERENCES NO. _

g 136 Flow Transmitter Reactor 268-270

.Nene-4.6.50 Foxcoro Building f

15A 137 Flow Switch Reactor 271-273, None 4.6.51 Mercoid Building 277-279 CA-533-3 DA-533-2R1

' 1J8 Temperature Switches Reacter 274-276 Ncne 4.6.52 Chromalex Building Mcdel Not Stated s

139 Local Centrol Panel Reactor 280-282 None 4.3.3 Ea :lo Building s

2tc 312971 S3.30 140 Solenoid Valve Reactor 283-285 Ncne 4.6.53 tersa/ASCO Building

' TS-23 0 2/

3320A23 141 Temperature Element Inside-243-246 Nene 4.6.13 Pall. Trinity Micro Torus 14-T-25 142 Damper EVAC 398-400 Ncne 4.7.4 Manufacturer and Iquipment Model Not Stated Rcom i

143 Position Switch RWCU Room 368 None

. 4.7.47 f

Manufacturer and Model Not Stated l

144 Level Switches Turbine 81 23 4.7.83 l

Mangetrol Building l

291-SP l

145 120 V ac Reacter Electrical 420-421 None 4.7.75

(

?:ocaction sus Iquipment General Ilectric Recm

-?fpe NA3, Style 2A Plant 3 l

3 ~ *..,

,,4 Fmnxiin Research Center 4 om on

w. 7 wi.an m.au, t

.--r---

er

-'- - + - * * ~

----r-ev

--w 6 i

=

t v'e

--m*

v v*-=w+ve w

rT=.=--

e

wwwwe w *, e-t v =re t= rwe t v *-' e e v e-r v+ v e w v -

=*ew,--vv

=v*--

v ve n e w

- v

-*w-Wyt-e

TER-C5417-12 EQUIPMENT TER

-J-ITEM ITEM SCEWS QUA"IFICATICN SECTICN NO.

DESCRIPTION LCCATICN NO.

REFERENCES NO.

.f-.

146 120/240 V ac Bus Electrical 422-423 None 4.'.76 Cutler Hammer Equipment i

6CF655505 Room 147 120/240 V ac Bus Electrical 424 None 4.7.77 MMG Set Equipment General Electric Room SL54404A22Y30 l'48 250 volt de Meter Reactor

- 446,447 None 4.7.84 Centrol Cents:

Suilding Culter Hammer 6002H347B r

?

s l

A s-la

...J Frannlin4 n. naren Center Rese ac -

n.sn in-we

-,e,,

r.

,-r-

.-wg

,m.--.a.-

.,r-,n,-e--,--n x

-,,e.-,...-

-n.m.

y--,

,-,,n

+-,m,.,.

9.,..ne,

~~.,v,.

p

,,s,.,-v ar-,

~,-e

-.,wevn-,...r,,,

e r,-

4..

mm,v

) k l

TER-C5417-12 APPENDIX C - SAFE *Y SYSTEMS FOR WHICH ENVIRCNMINTAL

.QUALIFICATICN IS TO BE ACCRESSED a

, j --

The Licensee submitted the following list of safety-related systems..

that must' function in order to mitigate the consequences of a design basis accident. This information.was included in the Licensee's November 1,1980 response ~(33] to IE Bu11etin'79-01B.

'o Reactor Protection System.

o Core Spray System o 'High-Pressure C:olant Injecticn System i

Auto Oepressuri:ation' System / Main Steam System o

o Residual Heat Removal /C ntainment Spray System Pressure Suppressien System; o

o Standby Gas' Treatment System o,' Service Water System e-Diesel Cil Piping System o Containment Isolatien System

o Control Red Drive Hydraulic System o Reactor (Nuclear Boiler) Recirculatten System

.o Process Radiation Monitoring System o Reactor Building ventilation System

'o Control Poem, HVAC o Standby Alternating Current Power

)

,o Standby Direct Current Power.

1 o Reacter Core Isolation C0 cling System (RCIC)

J o General Use-Electrical Equipment l

' Containment isolatien includes all ecmponents, in various systems, t.t a t perf:rm the centainment isolation function.

J j

C-1

..... ranniin Resenten Center

%.m. %n -u.

0 e

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.,,-,>[-,.,-,%[----,ww..

,w.m,.-r w w a m -,y,,n,7,,,

eye,%-,-,w,-w,.,-,.e,ewy,,we,w,-www,,,,ewm.-nm,%y,y,,,ya,.g.,--,.worme.y..y,,,y,-,m,.may w,.-- y,wes

ML20126M364

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