ML20009H111

Equipment Environ Qualification,Brunswick Steam Electric Plant Unit 1, Technical Evaluation Rept

ML20009H111
Person / Time
Site:	Brunswick
Issue date:	06/10/1981
From:	Crane C FRANKLIN INSTITUTE
To:
Shared Package
ML20009H110	List: ML20009H111 ML20009H112
References
IEB-79-01B, IEB-79-1B, TER-C5417-7, NUDOCS 8108060036
Download: ML20009H111 (100)

Text

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9 THOMM!C.TL EVALUATION REPORT i

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, ", EQUIPNENT ENVlaONMENTAL QUAll. lCAT!ON j

CAROLINA F0WER AND LIGHT CClEANY l'

] BRbNSWICK STEAli ELECTRIC PLANI UNIT 1

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l 1 NRC CCCKET NO. 50-324 NRC TAC NO. 42??? FRC PROJECT CS417 i  : EG1G 'DAHC, tNC. SU S00NTRACT NO. K-7515 FRC TASK 7 i

Pr:parad by Franklin Research Center

! The Parkway at Twentieth Street l Ph!!adelphia, PA 13103 FRC Group Leader: C. J. Crano i

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Precared for i EGdG Idaho, Inc.

Idaho Falls, Idaho 83401 l June 10, 1981 i

I f ., 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 impiled, or assumes any legal liability cr 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 not infringe privately owned rights.

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B108060036 810721 PDR ADP",K 05000324 P PDR i

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l TECHNICAL EVALUATION REPORT EQUIPMENT ENVIRONMENTAL QU ALIFICATION CAROLINA POWER AND LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 NRC DOCKET NO. 50-324 NRC TAC NO. 42484 FRC PROJECT C5417 EG&G IDAHO,INC. SUBCONTRACT NO. K 7615 FRC TASK 7 Prepared by Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 FRC Group Leader: C. J. Crane Prepared for EG&G Idaho, Inc.

Idaho Falls, Idaho 83401 June 10, 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 l States Department of Encrgy. Neither EG&G nor the United States Government nor any agency thereof, or r.ny of their employees, j* makes any warranty, expressed or Imr; co, or assumes any legal llability 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 not infringe privately owned rights.

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l CONTENTS Se ction Title Page j

1 INTRODUCTION. . . . . . . . . . . . . . 1-1 l

l 1.1 Purpose of the Evaluation . . . . . . . . . 1-1 1.2 Generic Issue Background . . . . . . . . . 1-1 l

l 1.3 Scope of the Evaluation . . . . . . . . . 1-7 2 NRC CRITERIA ICR ENVIRONMENTAL QUALIFICATION. . . . . . 2-1 2.1 Criteria Provided by the NRC . . . . . . . . 2-1 2.2 Staff Positions and Supplemental Criteria . . . . . 2-1 9

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

l 2.2.2 Submergence . . . . . . . . . . . 2-2 l 2.2.3 Equipment tocated in Areas Normally Maintained i

at Room conditions . . . . . . . . . 2-2 2.2.4 Simulated Service Conditions and ast Duration . . 2-3 2.2.5 Deferment of Qualification Review . . . . . 2-3 2.2.6 ast Sequence . . . . . . . . . . 2-4 2.2.7 Radiation . . . . . . . . . . . 2-4 3 . METHODOLOGY USED BY FRC . . . . . . . . . . . 3-1 4 TECHNICAL EVALUATION. . . . . . . . . . . . 4-1 4.1 Methodology used by the Licensee . . . . . . . 4-1 4.1.1 Completeness of Equipment List . . . . . . 4-1 4.1.2 Environmental Service mnditions . . . . . 4-2 4.1.3 Aging and Qualified Life . . . . . . . 4-3 4.2 NRC Category I Equipment That Satisfies the General Requirements of the DOR Guidelines and IE Bulletin 79-01B ., . . . . 4-6 l

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I CONTENTS I l

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Section Title Page .

! 4.3 NRC Category II

! Equipment eat the Licensee Will Modify or Relocate . . 4-14 ,

f 4.4 NRC Category III -

Equipment $at the Licensee Believes to Be Exempt From Qualification . . . . . . . . . 4-15 1

4.5 NRC Category IV Equipment $at Has Qualification Testing ']

Scheduled but Not Completed. . . . . . . . . 4-16 j 4.5 NRC Cate9t*,ry V Equipe '* Wat Does N3t Satisfy One or More of the Genert. - quirements of the DOR Guidelines and IE Bull et.1 79-01B . . . . . . . . . . . 4-17 4.7 MRC Category VI r.quipment for which Qualification Is Deferred . . . . 4-32 4.8 Summary of the Evaluation . . . . . . . . . 4-33 5 CONCLUSIONS. . . . . . . . . . . . . . 5-1 6 REFERENCES . . . . . . . . . . . . . . 6-1 ,

l APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS APPENDIX B - LISTING OF SAFETY-RELATED ELECTRICAL EQUIPMENT APPENDIX C - SAFETY SYSTDIS FOR WHICH ENVIRONMENTAL .

QUALIFICATION IS TO BE ADDRESSED e

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1. INTRODUCTION 1.1 PURPOSE OF THE EVALUATION The ' NRC Office' of Inspection and Enforcement (IE) issued Bulletin 79-01B,

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

! action. t i

The objectives of the NRC Equipment Environmental Qualificatior Review program are to evaluate nuclear power plant safety-related electrical equipment in accordance with criteria established by the NRC and to ident ify  !

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

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

l To meet the overall program goals, the objective of this Technical Evaluation Report is to review the Licensee's submittals to determine if the Licensee reviewed its safety-related electrical equipment for environmental a qualification in accordance with the DOR Guidelines and NUREG-0588 as required r by IE Bulletin 79-018. The NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. If discrepancies are fcund, the audit will be extended.

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

! particular concern is the assurance that equipment will remain operable during b Frankun Research Center '

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TER-C5417-7 and following exposure to the harsh environmental conditions (i.e.,

temperature, pressure, humidity (steam), chemical sprays, radiation, and ,

submergence) imposed as a result of a design basis accident. These harsh environments are generally defined by the limiting conditions resulting from the complete spectrum of postulated break sizes, break locations, and sicgle ,

failures consequent to a loss-of-coolant accident (LOCA), main steam line break (MSLB) inside the reactor containment, or a high energy line break (HELB) outside reactor containment (such as a main steam or feedwater line break) . The purpose of equipment qualification is to provide tangible evideace that equipment will operate on demand and to verify design ,

performance, thereby establishing assurance that the potential for common-mode ,

failure is minimized.

Qualification criteria applied during the licensing of the older nuclear power plants have been modified 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 hr 2 l accumulated. Examples of such standards are IEEE Standards 279-71, 323-74, -

38 3-7 4, 317-7 6, 33 4-7 4, 3 81-71, 38 2-8 0, and 627-8 0. NRC NUREG documents 0413 3

and 0588 have been developed to address this topic. In particular, NUREG-0588 (published for comment in December 1979) formally presented the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment in the resolution of General Technical Activity A-24, " Qualification of Class IE Safety Related Equipment." The positions documented therein are applicable to plants that are or will be in >

the construc' tion 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 10CFR50, Appendix A, General Design Criteria for Nuclear Power Plants,Section I, Criterion 4. This criterion states in part that " structures, systems and components important to safe:y shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing and postulated accidents, including loss-of-coolant accidents."

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i TER-C5417-7 l Qualification requirements are also embodied in 10CFR50 Appendix A, General Design Criteria 1, 2, and 23 and Appendix B, Quality Assurance l

Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Criteria III and XI. These requiren.ents are applicable to safety-related equipment located inside as well as outside containment.

l l The NRC staff has evaluated the Licensee's equipment qualification program by reviewing the qualification documentation of selected safety-related equipment as part of the operating license review for ecch plant. The NRC ,

l staf f has also used a variety of methods to assure that these general require-I ments are met for electrical safety-related equipment. In the oldest plants, qualification was based on the fact that electrical components were of high industrial quality. Af ter 1971, qualification was judged on the basis of IEEE

, Std 323-71; however, no regulatory guide was issued adopting this standard.

f For plants whose Safety Evaluation Reports were issued af ter July 1,1974, the l

l Commission issued Regulatory Guide 1.89, which in most respects adopted the most recent standard, IEEE Std 323-74.

In 1977, the NRC staf f instituted the Systematic Evaluation Program (SEP) to determine the degree to which the older operating nuclear power plants l

deviated from current licensing criteria. The subject of electrical equipment environmental qualification (SEP ' topic III-12) was selected for accelerated l evaluation as part of this program. Seismic qualification of equipment was to I be addressed as a separate SEP topic. In December 1977, 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 recommer.ded that additional effort should be devoted to examining the installation and environmental qualification documentation of specific electrical equipment in all operating reactors.

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TER-C5 417-7 On May 31,197 8, the NRC Office of Inspection and Enforcement issued IE Circular 78-08, "Envitenmental Qualification of Safety-Related Electrical ,

Bquipment 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 qualification ,

documentation for equipment function under postulated accident conditions.

Subsequently, on Febru.try 8,1979, the NRC Office of Inspection and Enforce- .

ment issuei IE Bulletin 79-01, which was intended to raise the status of IE Circular 78-08 to the level of Bulletin, i.e., action requiring a licensee re sponse. This Bulletin required a complete re-review of the environmental i qualification of safety-related electrical equipment as described in IE ,

Circular 78-08. -;

The review of the licensee responses indicated certain deficiencies in the scope of equipment addressed, definition of harsh environments, and adequacy of support documentation. It became apparent that generic criteria were needed to evaluate the electrical equipment environmental qualification {'

for both SEP and non-SEP operating plants. Therefore, during the second half of 1979, the Division of Operating Reactors (DOR) of the NRC issued internally a document entitled " Guidelines for Evaluating Environmental Qualification of ,

Class IE Electrical Equipment in Operating Reactors" (74) .* (The document is I

hereaf ter referred eo 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 DDR Guidelines. However, '

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.

I aror References, see Section 6. Note that the reference numbers are not presented in sequential order.

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4 TER-C5417-7 On January 14, 1980, the NRC Office of Inspection and Enforcement issued the DOR Guidelines and IE Bulletin 79-018, which expanded the scope of IE 4.

Bulletin 79-01 and requested additional information on environmental qualification of safety-related electrical equipment at operating facilities, excluding the 11 facilities undergoing the SEP review. This Bulletin cited I the DOR Guidelines as the criteria to be used in evaluating the adequacy of i

! - the safety-related electrical equipment qualification. The scope-of the I review was expanded to include high energy line breaks (inside and outside containment) in addition to equipment aging and ubmergence. The NRC advised 4

the licensees that the criteria contained in the OOR Guidelines would be used ~

in its review of licensee submittals problems arising from this review would be resolved using NUREG-0588 as a guide.

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• In early February 1980, the NRC decided that Indian Point Units 2 and 3 and Zion Units 1 and 2 should be included within SEP Topic III-12 for the

purpose of equipment environmental qualification review.

On February 21, 1980, the NRC and representatives of the SEP Plant Owners 4

l Group held an open meeting at NRC headquarters to discuss an accelerated l review program in accordance with the DOR screening guidelines. Represen-

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tatives of the Indian Point Units and Zion Station also attended this meeting. The NPC formally issued to all licensees represented at the meeting 1 the DOR Guidelines document which included a second document, " Guidelines for 1

i Identification of That Safety Bquipment of SEP Operating Reactors for Which Environmental Qualification Is TO Be Addressed" (74], together with the

! request that the licensees review their plant systems and provide additional

equipment environmental qualification information to the NRC on an accelerated 5 schedule.

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For non-SEP plants, the NRC Office of Inspection and Enforcement formed a task force including a principal reviewer in each region and a task leader from headquarters. The regional members were assigned responsibility for the technical review of the licensees' responses to IE Bulletin 79-01B, and the task leader was assigned responsibility for the overall coordination of the review effort with NRC staff to assure overall consistency. The regional

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reviewers' held meetings with the licensees in their respective regions, which i

resulted in staff positions being issued in a supr'ement to IE Bulletin 79-01B ,

! dated _ February 29, 1980.

I In ~ April 1980, the NRC organizational structure was modified and the Equipment Qualification Branch was formed within the new Division of Engi- .

neering.' Responsibility for reviewing the status of equipment qualification 7

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for all plants was assigned to this branch. ,

On May 27, 1980, the NBC issued Memorandum and Order CLI-80-21 [77),

I specifying that licensees and applicants must meet the requirements set forth /

in the DOR Guidelines and NUREG-0588 regarding environmental qualification of safety-related electrical equipment in order to satisfy 10CFR50, Appendix A, l

i General Design Criteria,Section I, Criterion 4. This Order also established t

that the Safety Evaluation Reports on this subject, to be prepared by the NRC i

l staff, must be issued on Mbruary 1,1981 and that all subsequent actions to l- be taken by licensees to achieve full compliance with the DOR Guidelines or j

f NUREG-0588 must be completed no later than June 30, 1982. {

3e staff held regional meetings with the licensees and interested parties during the week of July 13, 1980. The staff issued a second 1 supplement to IE Bulletin 79-OlB, a response to significant questions raised during the public meetings, and two Orders. The Order, dated May 30, 1980, required the licensees to comply with the previously issued Con. ission

• l Memorandum and Order of May 27,19 80 (CLI-80-21) . The above Orders required ,

_ the licensees to complete the tasks identified in IE L 'letin 79-OlB no later  ;

than November 1,1980 to allow the staff to corply with the February 1,1981 j date imposed by the Commission Order. We responses to the questions were ,

issued on Mbruary 29, 1980; and the second and W ed supplements to IE l

Bulletin 79-OlB, highlighting the staff positions affecting the licensees' l

• responses, were issued on September 29 and October 24, 1980, respectively.

l In October 1980, EG&G Idaho, Inc. awarded Franklin E ,earch Center (FRC) j a contract to provide assistance in the equipment environmental qualification i review for 13 of the plants whose licensees responded to IE Bulletin 79-OlB.

t j FRC was to evaluate the licensees' equipment environmer..al qualification i~

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TER-C5417-7 submittals and to present the results in the form of a 'Ittchnical Evaluation

, Report for each plant.

a 1.3 SCOPE OF THE EVALUATION Environmental qualification of safety-related electrical equipment was selected by the NRC f0r accelerated

• review. Therefore, the scope of this

-. repott is limited to equipment that must function to mitigate the consequences of a LOCA or HELB and whose environment is adversely affected by those events. In addition, IE Bulletin 79-OlB requires environmental qualification in accordance with the DOR Guidelines or NUREG-0588 for all safety-related electric:1 equipment exposed to a harsh environment. Harsh environments include the limiting conditions resulting from (i) the entire spectrum of postulated line breaks resulting from a IDCA or HELB inside and outside containment and (ii) radiation from fluids that are recirculated from inside containment to accomplish long-term cooling subsequent to an accident.

Qualification aspects not ircluded wie the scope of this evaluation are o seismic qualification o equipment protection against natural phenomena o equipment operational service conditions (e.g. , vibration, voltage ,

and frequency deviatior..;)

o equipment located where it !s subject to outdoor environments o equipment protection against fire hazards o equipment protection against missiles.

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2. NRC CRITERIA FOR ENVIRONMENTAL , QUALIFICATION 2.1 CRITERIA PROVIDED BY THE NRC The DOR screening guidelines used by FRC to evaluate the electrical equipment environmental qualification programs were o " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Bquipment in Operating Reactors" (74]

i o " Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Is To Be Addressed" (74]

o NUREG-0588, " Interim Staf f Position on Environrental Qualification of Safety-Related Electrical Equipment" (79].

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

2.2 STAFF POSITIONS AND SUPPLDiENTAL CRITERIA The NRC identified the following staff positions and supplemental criteria f to be used in conjunction with the referenced DOR screening guidelines.

2.2.1 SERVICE CONDITIONS INSIDE CONTAINMENT EUR A IDSS-OF-@OLAha ACCIDENT (DOR Guidelines Section 4.1)

For pressurized water reactors (PWT the DOR Guidelines state tnat the containment temperature and pressure er tons as a function of time shculd be based on the most recent NRC-approved service conditions specified in the Final Safety Analysis Report (FSAR) or other licensee documentation. In the specific case of pressure-suppression type containments, the following minimum high temperature conditions may be used: (1) boiling water reactor (BWR) drywells -- 340*F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and (2) PWR ice condenser lower compartments --

340*F for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. As stated in supplement 2 to IE Bulletin 79-OlB [75],

"these values are a screening device, per the Guidelines, and can be used in lieu of a plant-specific profile, provided that expected pressure and humidity conditions as a function of time are accounted for."

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_1 TER-C5417-7 Service conditions should bound those 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.

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The adequacy of a plant-specific profile depends on the assumptions a'nd design considerations at the time the profiles were developed. The DOR Guidelines and NUREG-0588 provide guidance and considerations required to determine if the calculated plant-specific temperature / pressure profiles encompass the LOCA and EELB accidents inside containment. -

4 3 2-2.2 SUBMERGENCE

, (DOR Guidelines Section 4.1, Subitem 3; and Section 4.3.2, Subitem 3)

Equipment submergence (inside or outside containment) should be addressed where the possibility exists that submergence of equipment may result from HELBs or other postulated occurrences. Supplement 2 to IE Bulletin 79-01B

[75] provides the following additbcoal criterion: If the equipment satisfies the guidance and other requirements of the DOR Guidelines or NUREG-0588 for ,

the LOCA and HELB accidents, and the licensee demonstrates that its failure will not adversely affect any safety-related function or mislead the operator af ter submergence, the equipment can be considered exempt from the submergence portion of the qualification requirements.

2.2.3 EQUIPMENT LOCATED IN AREAS NORMALLY MAINTAINED AT ROOM CONDITIONS j (DOR Guidelines Section 4.3.3)

Supplement 2 of IE Bulletin 79-OlB [75] permits deferment of the review .

of environmental qualification for all safety-related equipment items located in plant areas where the equipment is not exposed to the direct effects of a HELB or to nuclear radiation emanating from circulation of fluids containing radioactive substances. At the licensee's option, the review may be deferred until af ter February 1,1981.

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TER-C5417-7 f By June 30, 1982, all safety-related electrical equipment potentially exposed to a harsh environment in nuclear generating stations licensed to operate on or before June 30, 1982 shall be qualified to either the DOR Guidelines or NUREG-0588 (as applicable) . Safety-related electrical equipment is that required to bring the plant to a cold shutdown condition and to mitigate the consequences of the accident. It is the responsibility of the licensee to evaluate the qualification of safety-related electrical equipment to function in environmental extremes not associated with accident conditions and to document it in a form that will be available for the NRC to audit.

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

2.2.4 SIMULATED SERVICE CONDITIONS AND TEST DURATION (DOR Guidelines Section 5.2.1)

The Guidelines require that the test chamber environment envelop the required service conditions for a tin.e equal to the period from the initiation of the accident until the service conditions return to normal. Supplement 2 to IE Bulletin 79-OlB [75] provides the following additional criterion:

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

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2.2.5 DEFERMENT OF QUALIFICATION REVIEW

, Supplement 3 to IE Bulletin 79-01B [76] permits the submittal of qua)ifica-tion documentation regarding TMI Action Plan equipment and the equipment required to achieve 6.nd maintain a cold shutdown condition to be delayed as follows:

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

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'o Qualification informae*c:.10c future TMI Action Plan equipment (ref.

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

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

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o Qualification information for TMI Action Plan equipment not yet installed which does not require pre-implementation review should be submitted to NRC for review by the implementation date.  ;,

o The qualification 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 (DOR Guidelines Section 5.2.3)

Supplement 2 to IE Bulletin 79-OlB [75] provides the following additional criteria:

" Sequential testing requirements are specified in NUREG-0588 and the DOR Guideline s. Licensees must follow the test requirements of the applicable document.

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

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

3. Test programs in progress should be evaluated regarding the ability to comply by incorporating aging in the proper sequence. These would I

then fall in the first or second <-r*egory." ,

4 2.2.7 RADIATION (DOR Guidelines Sections 4.1.2, 4.2.2, and 4.3.2, Subitem 2)

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Supplement 2 to IE Bulletin 79-OlB [75] provides the following additional criteria:

"Both the DOR Guidelines and NUREG-0588 are similar in that they provide the methods for determining the radiation source term when considering

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TER-C5417-7 LOCA events inside containment (100% noble gases /50% iodine /11 partic-ulates). Sese methods consider - the radiation source term resulting from an event which completely depressurizes the primary system and releases the source term inventory to the containment.

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L' . NUREG-0578 provides the radiation source term to be used for determining the qualification doses for equipment in close proximity to recirculating fluid systems inside and outside of containment as a result of I,0CA.

This method considers a IDCA event in which the primary system may not

- depressurize and the source term inventory remains in the coolant..

i NUREG-0588 also provides the radiation source term to be used for qualifying equipment following non-LOCA events both inside and outside containment (10% noble gases /10% iodine /04 particulates) .

When developing radiation source terms for equipment qualification, the Licensee must ensure consideration is given to those events which provide the most bounding conditions. We following table summarizen these considerations:

l LOCA Non-IDCA HELB Outside Containment NUREG-0578 NUREG-0588 i

(100/50/1 (10/10/0 in RCS)[*1 in RCS)

. Inside Containment targer of NUREG-0503 NPREG-0588 (100/50/1 (10/10/0 in containment) in RCS) or NUREG-J571 (100/50/1 in RCS)

Gama equivalents may be used when consideration of i.he contributions of beta exposure has been included in accordance with the guidance given in

• the DOR 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."

• The numbers in parentheses represent t noble gases /n iodine /t particulates.

RCS means reactor coolant system.

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3. METHODOLOGY USED BY FRC The Licensee, Carolina Power and Light Company, identified an extensive list of safety-related electrical equipment

• items f r. various locations of

- Brunswick Steam Electric Plant Unit 1 in its submiLMis 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. m is analysis resulted in a redaced listing containing 92 different equipment items that formed the basis for the review. In this report, the term " equipment item" refers to a specific type of electrical equipment, designated by manufacturer and model, which is representative of all identical or generically identical equipment in a plant area exposed to the same environmental service conditions (e .g. , Flow Transmitter, Fischer & Porter, Model 10B2496, located within containment) .

Appendix A contains the environmental service conditions for each location, Appendix B contains the tabulation cE the equipment items and locations (the tabulation does not include equipment covered by the evaluation deferment described in Section 2.2.3 of this report), and Appendix C lists the plant systems identified by the Licensee as being essential to safety.

IE Bulletin 79-OlB required the licensees to:

o provide a master list that identifies the safety systems and Class lE electrical equipment required to function during and subsequent to an accident and to maintain the pl at in a safe condition o identify the environmental service conditions e o identify the maximum submergence levels o provide written evidence (System Component Evaluation Work Sheets) of the environmental qualification of the equipment identified in the master list to demonstrate the capability of the equipment to function under postulated accident conditions "In this report, the term " safety-related electrical equipment" refers to the equipment defined by the NRC Guidelines referenced in Section 2.1.

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3-1 Mbu Franidin Research Center

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o evaluate the qualification documentation using the DOR Guidelines and

- NUREG-0588; and, for equipment not having adequate qualification, to

. identify plans and schedules for. establishing qualification ,

l o submit a Licensee Event Report (LER) for Class lE electrical' equipment j determined to be unqualified.

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The responses to IE Bulletin 79-018 were requested by the NRC under ,

j provisions 'of 10CFR50.5 4 (f) , "Oonditions of Licenses," which requires the ,

1 licensees to submit. written statements, signed under oath. To provide. ,

l assurance that the licensees. satisfy the requirements of IE Bulletin 79-OlB i

a 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 5 licensees' responses in relation to the general requirements of the DOR

• Guidelines as augmented by the supplements to IE Bulletin 79-OlB. .

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

submittal are correct. Review of test reports was not within the scope of l FRC's assignment. However, the NRC staff will audit selected analyses and test reports, incorporating the results of the reviews with the conclusions of j the TERs, when developing the plant-specific SERs.

j Each equipment item listed in Appendix B was assigned to one of the NRC i

j categories defined in Table 3-1 af ter review of the associated System

Component Evaluation Work Shset provided by the Licensee.

I Topics not within the scope of the FRC evaluation are i .

j o ' completeness of the licensea's listing of safety-related equipment i

o acceptability of licensee-provided environmental service conditions .

( .

j o acceptability of licensee-stated positions concerning safety systems

j. or component function j o review and acceptability of qualification test reports and other qualification documentation.

i j The NRC Of fice of Inspection and Enforcement established a program to I conduct an onsite verification inspection of selected Class lE equipment to

} verify proper installation of equipment, overall interface integrity, location a

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l. TER-C5417-7 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 Work Sheets of the licensee's report. The specific details of this

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site inspection are documented in IE Inspection Report 50-324/80-18. The information in this report will be used by the NRC in developing the plant-

. specific SER.

Table 3-1. NRC CATEGORIES AND DEFINITIONS o NRC Category I EQUIPMENT THAT SATISFIES THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES AND IE BULLETIN 79-OlB -

This category includes equipment items for which the System Component Evaluation Work Sheets are judged to be in compliance with IE Bulletin 79-OlB, 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-OlB have been satisfied, assuming that the licensee's analyses of qualification documentation are complete and correct.

o NRC Category II EQUIPMENT THAT THE LICENSEE WILL MODIFY OR RELOCATE This category includes equipment items that the licensee has stated will be modified or relocated in order to comply with the DOR Guidelines require-ments.

o NRC Category III EQUIPMENT THAT THE LICENSEE BELIEVES TO BE EXDIPT FROM QUALIFICATION

'Itiis 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 accomplished by some other designated equipment that is fully qualified.

(Continued)

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l TER-CS417-7 9

Table 3-1 (Cont.)

o NRC Category IV EQUIPMENT THAT HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLETED This category includes equipment items that the licensee has determined -

to be deficient or inadequate with respect to qualification. However, the licensee has stated that the equipment item is scheduled to be tested by a designated date.

o NRC Category V EQUIPMENT THAT DOES NOT SATISFY ONE OR MORE OF THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES AND IE BULLETIN 79-OlB This category includes equipment items judged to be deficient or inadequate with respect to the general requirements of the DOR Guidelines and IE Bulletin 79-01B based on a review of the licensee's System Component Evaluation Work Sheets.

I o NBC Category VI i EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED l

l This category includes equipment items that have been addressed by the licensee in the equipment environmental qualification submittals; however, tl a 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 i report.

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4. TECHNICAL EVALUATION General observations concerning the Licensee's approach to qualificauun 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 4

with FRC's technical evaluation of the Licensee's documentation. We results of the evaluation are summarized in Section 4.8.

4.1 METHODOLOGY USED BY THE LICENSEE This section includes observations concerning the Licensee's methodology and procedures, as described in Reference 78, for complying with the requirements of IE Bulletin 79-01B.

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4.1.1 COMPLETENESS OF EQUIPMENT LIST The Licensee's submittal .78] states the following:

"Wis report c en~;,iled as follows:

"We plant AE, United Engineers and Constructors, was requested to provide the master equipment list and to search for qualification data

for all of the identified equipment not in the scope of supply of the NSSS vendor, General Electric Ccmpany.

"We master list of components required to function in a harsh environment to mitigate the consequences of a LOCA or HELB was developed from a review of the plant design basis documentation including Design Reports, The Final Safety Analysis Report, the Technical Specifications and the anergency Instructions in the Brunswick Steam Electric Plant Operating Procedures, Volume VI. Further review of the plant design

. basis was based on an examination of design and installation drawings with field verification.

• In this report, the term " equipment item" refers to a specific type of electrical equipment, designated by manufacturer and model, which is representative of r.11 identical or generically identical equipment in a plant area exposed to the same environmental service conditions (e.g. , Flow Transmitter, Fischer & Porter, Model 10B2496, located within containment).

[dddA cm Franklin Research Center4-1 on a n. Fr.n.en m l

TER-C5417-7 "At least two cognizant engineers, one of whom holds an SRO license on I BSEP, have reviewed each item on the master list for the accuracy of its assessed system function and the appropriateness of its inclusion on the list using Appendix A of DOR guidelines. Only Unit 2 items appear in this listing. Because the units are essentially identical it is expected >

that ih: corresponding components in Unit 1 would be the same. Equipment list comparisons and walk-through inspections are being conducted to l.

identify any discrepancies in installed equipment types."

The Licensee has not presented documentation derived from their walk-

• t l through inspections of Brunswick Units 1 and 2 which would identify any discrepancies between Un!.t 1 and Unit 2 in installed equipment types. FRC has ,

evaluated equipment qua*.ification for Brunswick Unit 1 based on the premise l stated in the preceding paragraph.

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! 4.1.2 ENVIRONMENTAL SERVICE CONDITIONS l

4.1.2.1 7"MPERATURE AND PRESSURE The Licensee has provided pressure and temperature conditions resulting i

from a HELB or LOCA as follows:

o accident profile for temperature inside containment o accident profile for pressure inside containment o accident profile for temperature of RER and chase (EL. 5 ECEN) o accident pcessure table for RHR and chase (EL. 5 ECEN)

( o accident profile for temperature outside containment, elevation 20' ,

l and above o accident pressure table for outside containment, elevation 20' and above o accident profile for temperature of HPCI toom ,

o accident pressure table for HPIC room ,

o accident profile for temperature of core spray rooms o accident pressure table for core spray rooms o accident profile for temperature of RWCU area o accident pressure table for RWCU area o accident profile for temperature of main steam and RCIC/HPCI tunnels o accident pressure table for main steam and RCIC/HPCI tunnels, 4-2 hd Franklin Ao Researe.5 a a m r=nima w-w.

Center

O TER-C5 417-7 FRC considers tha r.icensee's approach to be satisfactory.

The Licensee also states:

"All Class IE electrical eqJipment located in the Control Bailding, Diesel Building, Augmented Of f-Gas Building, Service Water Building and

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Turbine Building have been omitted from the Master List. These areas are not subjected to a harsh environment caused by the postulated accidents."

. Insufficient information is available for FRC to evaluate the adequacy of the above statements. In general, steam lines are present in the turbine building . Consequently. equipment in the building may be subjected to post-NELB environments. Equipment in the service water building may also be subjected to submergence and such conditions should have been addressed.

4.1.2.2 RADIATION The Licensee excludes equipment located in the non-harsh environment from qualification considerations. The Licensee, however, does nc a provide i criteria for determining harsh and non-harsh radiation environtients. It appears that the area where the maximum integrated radiation i.ose is less than 1 x 105 rd is considered non-harsh because only the equipment that is i subjected to a larger total radiation dose is included in the Equipment Evaluation Work Sheets. The Licensee's approach appears to be less conservative than is permitted by the Guidelines. For certain electronic equipment, such as process parameter transmitters, performance degradation may occur at threshold levels lower than 1 x 10 rd. Most BWR plants use 1 x 10 rd as the cutof f point.

4.1.3 AGING AND QUALIFIED LIFE

• . The Licensee has stated:

"With respect to various aging requirements, the incremental improvement in safety from replacing equipment with no specified qualified life, that is in other respects qualified, it not sufficient to justify the expense. In addition, no FSAR commitments were made in the aging area as no equipment was specified to IEEE-323 (1974).

"However, any equipment known or found to include materials that are known to be susceptible to thermal or radiation aging will be qualified or replaced with qualified ' pmant.

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" Testing is performed periodically in accordance with Technical Specification Requirements; this testing provides assurance that the equipment will perform its intended safety function."

The Licensee has not adequately addressed the related topics of aging and 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 i

o implement programs to review detailed surveillance and maintenance records to assure that equipment that exhibits age-related ,

degradation is identified and replaced (or modified) as necessary.

Qualified life is the maximum time period of normal service, under i

specified conditions, for which it can be demonstrated 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 I contingent on implementation of a specified maintenance program. It is '

i acceptable for the qualified life of some subcomponents of an equipment item to be less than the qualified life of the item itself, provided a program for replacement of such components at intervals not exeeding their qualified i lifetimes is specified and fulfilled. The qualified life of an equipment item j may be changed during its installed life when jucti" led 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 .

4 more fully in Reference 80, with the possible exception of certain simple f materials, there is no rigorous basis for establishing qualified lifetimes for ,

periods approaching an installed lifetime of 40 years. Furthermore, additional information regarding possible long-term synergistic effects of temperature, humidity, nuclear radiations, etc. , is extremely limited.

FRC 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 attempt to prove that this " requirement" is 4-4 dijd Franklin Resear.ch at==.onen.rr n m .Center

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met. We Guidelines do not require that the qualified life be shown to be 40 years (or any other value) . Rather, they require that each Licensee provide evidence that the safety functions of the equipment in the plant can be performed adequately at all times. A conservative qualified life value should

. be established for each equipment item, and surveillance testing (necessary to I- monitor performance and identify degradation) should be performed to determine

. the need for maintenance or replacement. In this way, the qualified life

value of , equipment item can be extended as new information is gained.

We ,, .:ensee should review the qualified life values and the present j installed life of the equipment in accordance with the DOR Guidelines to

!' determine a replacement schedule for each equipment item -(or subcomponents 1

j thereof). These schedules may be revised as new information becomes available.

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TER-C5417-7 4.2 NRC Category I EQUIPMENT THAT SATISFIES THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES AND IE BULLETIN 79-01B This category includes equipment items for which the System Component Evaluation Work Sheets are judged to be in compliance with IE Bulletin 79-OlB, l .

its supplements, and the general requirements of the DOR Guidelines. }te these equipment items, the Licensee's System Component Evaluation Work Sheets .

indicate that the requirements of IE Bulletin 79-OlB have been satisfied, assuming that the Licensee's analyses of qualification documentation are complete and correct.

4.2.1 Equipment Item No. 71 Terminal Lug AMP-Special Products PIDG-KYNAR (Licensee Reference 60) - ,

Review of the Licensee's System Component Evaluation Work Sheet indicates 1

that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

4.2.2 Equipment Item Nos. 70A and 70B Electrical Penetration Assembly Incated Inside and Outside Contaicment Westinghouse Model Class B, C and Class F (Licensee References 63, 72, and 73)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied; a test report. is ,

! referenced that envelops the required environmental service parameters.

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4.2.3 Equipment Item Nos. 3 and 22 Level Switch Incated Outside Containment -

Yarway Models 4418C and 4418EC (Licensee References 11, 39, 41, 4 2, and 4 4) .

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE sulletin 79-OlB are satisfied; a test report is referenced that ent _~vps . the required environmental service parameters.

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dbranidin Research Center A Opneupn of The Frenten Insende e

TER-CS417-7 4.2.4 aquipment Item No. 4 Pressure Switch Incated Outside Containment '

Static-O-Ring Models 12N-AA4-X10TT, SN-AA3-X9STT, and GN-AA21-X9SVTT (Licensee References 20 and 42)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are satisfied; a test report is referenced that envelops the required environmental service parameters.

4.2.5 Equipment Item Nos. 14A, 14B, 14C, 14D, 14E, 14F, 14G,14H,14I,14J,14K, and 14L Motor Operator Located Outside Containment Limitorque SMB Models (Licensee References 2, 3, 4 and 57)

Review of the Licensee's System Component Evaluation Work Sheet indicates that u.a requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

4.2.6 Equipment Item tc. 16

[ Pressure Switch Incated Outside Containment Barksdale'Models B2T-M12SS, D2T-M18SS, TC-9622-1, PlH-M340SS, i PlH-M85SS-V, D2H-M150SS, and D2T-M150SS (Licensee References 19, 43-46, 48, and 53)

Review of the Licensee's Syste.n Component Evaluation Work Sheet indicates

[ that the requirements of IE Sulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

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] 4.2.7 Equipment Item No. 17 Motor Incated Outside Containment j GE Models SK6 and SK8 (Licensee References 9,10, and 24)

Review of the Licensee's System Component Evaluation Work Sheet indicates a that the requirements of IE Bulletin 79-01B are satisfied; a test report is j referenced that envelops the required environmental service parameters.

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1 TER-C5417-7 4.2.8 Equipment Item No. 20A-Relay Incated Outside Containment GE Models CR2810A14AT, CR2811A217Y51, HFA51A49H, -

CR2810A14AC, and CR2810A14AK2 #

(Licensee Reference 12)

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

that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters. ],

4.2.9 Equipment Item No. 28 ,

Thermocouple Incated Outside Containment Pyco Model N145C3224-P1 *

(Licensee References .1, 29, and 30) ,

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

i 4.2.10 Equipment Item No. 30 Limit Switch Incated Inside Containment  ;

2 NAMCO Model EA740-80100 (Licensee References 13 and 21)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requiretrents of IE Bulletin 79-01B are satisfied; a test report is referenced that envelops the required environmental service parameters. ,

i 4.2.11 Equipment Item tes. 31A and 31B Limit Switch Incated aOutside Containment NAMCO Nodels EA740-80100 and D2400X-R (Licensee References 13, 21, and 56) .

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

dat the requiremerics of IE Bulletin 79-01B are satisfied; a test report is referenced that envelops the required environmental service parameters.

l gqj] Franklin Research Center 4-8 A Dhieson of The Frennen enessume

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4.2.12 Equipment Item No. 35 Flow Switch Incated Outside Containment -

Magnetrol Model F-521 (Licensee Reference 51)

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

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that the requirements of IE Bulletin 79-01B are satisfied. The Licensee has

. referenced qualification documentation, and the required environmental service-a parameters were enveloped.

4.2.13 Equipment Item No. 36 Position Switch Incated Outside Containment Cherry Electrical Products Corp. Model E23-60H (Licensee Reference 52)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied. The Licensee has referenced qualification documentation, and the required environmental service parameters were enveloped.

4.2.14 Equipment Item No. 41 Motor Control Incated Outside Containment Farr Co. Model D51423 (Licensee Reference 55)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Tulletin 79-OlB are not satisfied. The Licensee has referenced a test report indicating that the required environmental service parameters are enveloped.

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4.2.15 Equipment Item tc. 43

. 'Iemperature Switch Located Outside Containment Barksdale Model T2H-M251S-12 l (Licensee Reference 58) l l

5 Review of the Licensee's System Component Evaluation Work Sheet indicater .

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that the requirements of IE Bulletin 79-OlB art- not satisfied. The Licensee I has referenced a test repcet indicating that the required environmental service parameters are enveloped.

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4 TER-C5417-7 4.2.16 Muipment- Item No. 58

' Instrument cables Incated Inside and outside Containment Raychem Corp. Model Flamtrol 1PR$16 and ITR$16 1

, (Licensee. Re ference ' 65) l.

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

that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters, i

] 4.2.17 Muipment Item No. 59 y

Thermocouple Cable Incated outside containment Boston Ins. Wire & Cable Co. Models IPR $15 and !PR$16 .

j (Licensee References 62 and 64) 1 Review of the Licensee's System Component Evaluation Work Sheet indicates

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2 tnat the requirements of IE Bulletin 79-ole are sctisfied; a test report is referenced that envelops the required environmental service parameters.

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4.2.18 Muipment Item No. 60 ,

Thermocouple Cable Incated outside Contair.nent i Samuel Moore & Co. Models Dekoron ECI, IPR $16, and SPR$16 }

(Li:ensee Reference 66)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied; a test report is f- referenced that envelops the required environmental service parameters.

4.2.19 Muipment Item No. 61 9 Power Cable,1000 V, Incated outside Containment j Cerro Wire & Cable Co. Nels 4/ct6, 4/ct10, 4/ctl6,1/ct12, and 7/cfl6 j (Licensee References 67 and 68) .

f- Review of the Licensee's System Component Evaluation Work Sheet indicates i that the requirements of IE Bulletin 79-OlB are satisfied; a test report is -

referenced that envelops the required environmental service parameters.

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TER-C5417-7 4.2.20 . Equipment Item No. 62 i Power Cable (1000-5000 V) Lo ated outside Containment Okonite Co. Models 4/o AWG, 2/cf8, 4/ct10, 4/c06, 3/c250, 7/c250, and 3/c500 (Licensee Reference 68)

Review of the Licensee's System Component Evaluation Work Sheet indicates j that the requirements of IE Bulletin 79-01B are satisfied; a test report is

. referenced that envelops the required environmental service parameters.

4.2.21 Equipment Item No. 63 Control Cable Located Outside Containment

l. Kerite Co. Models 2/ctl2 and 4/c612

. (Licensee Reference 69) i

- Review of the Licensee's System Component Evaluation Work Sheet indicates p that the requirements of IE Bulletin 79-01B are satisfied; a test report is

, referenced that envelops the required environmental service parameters, t

4 4*.2.22 squipment Item No. 64 4

Control Caole Incated Inside and outside Contrinment Raychem Models #8-9-10-12 AWG Flamtrol I (Licensee Reference 65) .

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied; a test report is

referenced that envelops the required environmental service parameters.

4.2.23 Equipment Item No. 65 Control Cable Located Outside Containment Rockbestos Co. Models 2/cfl2, 4/ctl2,1/ctl2, and 1/c614 (Licensee Reference 70) j Review of the Licensee's System Component Evaluation Work Sheet indicates

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that the requirements of IE Bulletin 79-OlB are satisfied; a test report is j referenced that envelops the required environmental service parameters.

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TER-C5417-7 4.2.24 Equipment Item No. 66 Cable Termination Located Outside Containment Burndy, Okonite Model 5000 V -

(Licensee Reference 68)  ;

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-31B are satisfied; a test report is -

referenced that envelops the required environmental service parameters.

4.2.25 Equipment Item No. 69 Thermocouple Splice Incated Outside Containment AMP, Scotch, Raychem Models 320557, 70, and WCSF-N (Licensee References 69 and 71) ,

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

that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

4.2.26 Equipment Item No. 24 Level Switch Located Outside Containment Barton Models 288A and 288  ;

(Licensee References 25 and 31) 1 Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

4.2.27 Equipment Item No. 56 Instrument Cables Located Outside Containment Boston Ins, wire & Cable Co. Models 1PR$16, 3PRil6, and 1TR$16 (Licensee References 62 and 64)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

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TER-C5417-7 4.2.28 Equipment Item No. 52 terminal Blocks Incated Inside and Outside Containment Weidauller Model 6941 (Licensee Reference 61)

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

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that the requirements of IE Bulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

dOO ranklin Research Center A Demason of The Fransen h

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TER-C5417-7 4.3 NRC Category II EQUIPMENT THAT THE LICENSEE WILL MODIFY OR REIDCATE i

@is category includes equipment items that the Licensee has stated will be modified or colocated in order to comply with the DOR Guidelines j

requirements.

For Brunswick Unit 1, no equipment is assigned to this category. .

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a TER-C5417-7 4.4 NRC Category III EQUIPMENT THAT THE LICENSEE BELIEVES TO BE EXEMPT FROM QUALIFICATION

Mis category includes equipment items that the Licensee believes to be exempt from qualification on the basis that (1) the equipment does not provide

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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 Brunswick Unit 1, no equipment is assigned to this category.

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TER<S417-7 4.5 NEC Category IV EQUIPMENT THAT HAS QUALIFICATION SCHEDULED BUT NOT COMPLETED This category includes equipment items that the Licensee has determined to be deficient or inadequate with respect to qualification. However, the Licensee has stated that the equipment item is scheduled to be tested by a ,

designated date.

4.5.1 Equipment Item No. 19 i Motor Control Center Incated Outside Containment GE Model IC-7700 (Licensee reference not cited) ,

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 tested to establish whether it satisfies qualification requirements.

4.5.2 Equipment Item No. 27 Level Switch Located Outside Containment  ;

Robertshaw Model SL-205-A2-Ril-Bil-1 (Licensee References 22 and 49) i Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of the DOR Guidelines are not satisfied. However, the 1

Licensee stated that the equipment will be tested to establish whether it satisfies qualification requirements.

If the type testing is not successful, the Licensee has committed to replace this item.

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l TER-C5417-7 4.6 NHC Category'V EQUIPMENT THAT DOES NOT SATISFY ONE OR MORE OF THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES AND IE BULLETIN 79-01B This category includes equipment items judged to be deficient or

- inadequate with respect to the general requirements of the DOR Guidelines and IE F 'lletin 79-018 baseC on a review of the Licensee's System Component Evaluation Work Sheets.

4.6.1 Equipment Item No. 1 .

Selector Switch Incated Outside Containment Honeywell Micro Switch Models PTSHE202C-B97, PTKBC221CCB99, PTKBC2221CCC, PTSHA202F-B52, and PTKBC2221CCF9 (Licensee References 5 and 14)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to temperature and, pressure.

4.6.2 Equipment Item No.18B Motor Operator Incated Inside Containment Limitorque Models SMB-00-1 and SMB-00 (Licensee References 2 and 3)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to

temperature, pressure, and radiation.

l i

i nklin Research Center A Dhaman af The Frannen humasse i l

- - - _ . . - , . . _ . . . , _ . . _ _ . . . , , , . _ , -...._. _ , . . , . . , , . , ~ , , . . - . _ . .

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! TER-C5417-7

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4.6.3 squipment Item No. 21 Control Switch tocated Outside Containment Honeywell Microswitch Models PTSHA201 and PTSHA202F-852 .

(Licensee References 5 and 14) j Review of the Licensee's System Component Evaluation Work Sheet indicat es that the requirements of IE Bulletin 79-01B are not satisfied, stie Licensee  ;

has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to ,

temperature and pressure.

4.6.4 Equipment Item No. 23 .

Flow Sw' 'h Located Outside Containment Barton hel 289 i d

(Licensee References 8, 26, 37 and 38)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-018 are not satisfied. The Licensee ,

has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to pressure, radiation, and test duration.

Equipment Item No. 26 i 4.6.5 Flow Trar smitter Incated Outside Containment GE Model 50-555111BDAA3PDH (Licensee Reference 50)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced a test report; however, the required environmental service parameters were not enveloped.

The Licensee states that the equipment will be qualified or replaced by June 1982.

~

!!branklin Research Center A Dmmon of The Frennen insamme

7 TER-C5417-7 4.6.6 Equipment Item No. 67 Power Cable Splice Incated Outside Containment Burndy, Okonite Models T95 and 935 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the !.equirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

4.6.7 Equipment Item No. 29 naperatti.e Switch Incated Outside Containment Iwnwall Model 17002-40 (Licensee References 23 and 28)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced a test reporti however, the rr, quired' environmental service parameters were not enveloped with respect to radiat. 2n.

The Licensee has committed to test the item or replace it at the first J

refueling outage following receipt of material. l 4.6.8 Equipment Item No. 32 Limit Switch Incated Inside Containment Honeywell Micro Switch Model OP-AR (Licensee References 14 and 17)

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

, has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to temperature, pre **"ce, and radiation.

The Licensee states that the equipment will be qualified or replaced, t

300 ranklin Research Center s w an n. vre.en an u.

L 4

TER-C5417-7 4.6.9 Equipement Item No. 37 Position Switch Located Outside Containment Honeywell Micro Switch Model CP-DAR .

, (Licensee References 14 and 17) l Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee .

has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to ,

i temperature and pressure.

4.6.10 Equipment Item No. 38 Level Switch Incated Outside Containment Magnetrol Model 5.0-751  ;

(Licensee Reference 8.5)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced a test report indicating that the required environmental service parameters "ere not enveloped with respect to pressure and radiation.

4.6.11 Equipment Item No. 49 Terminal Lugs Incated Inside and Outside Containment f AMP Special Lug Model PIDG-Nylon and Plasti-Grip (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced a test report, and the required environmental service ,

parameters were not enveloped.

4.6.12 Equipment Item No. 2 Solenoid valve Incated Inside Containment ASCO Models HB-8302C25RU and HT-X-8320A70 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced a test report, and the required environmental service parameters were not enveloped.

_nklin Rese_ arch

_. Center

r -

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.ER-C5417-7 4.6.13 squipment Item No. 5A H2/02 Analyzer Incated outside Containment Welear Measurement Corp. , Model Int Stated (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-018 are not satisfied. We Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

4.6.14 Equipment Item No. 5B Radiation Analyzer Nuclear Measurement Corp., Model Not Stated (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. De Licensee i l

has not referenced qualification documentation, and the required environmental j i

service parameters were not enveloped.

4.6.15 Equipment Item No. 6 Level Pressure Indicator Located Outside Containment amico Model 35W (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. We Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

@e Licensee states that the equipment will be qualified or replaced in accordance with IE Bulletin 79-018.

4,I' 4-21 00JJFranklin Research Center A Dennen of The Franneninsumme o

TER-C5417-7 4.6.16 Equipment Item No. 7 ,

IAvel Transmitter Incated Outside Containment -

Bailey Model BQ15222 (Licensee reference not cited) j l

noview 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, and the required environmental service parameters were not enveloped. .

4.6.17 Equipment Item No. 8 Pressure /IAvel Switch Location Outside Containment Barton Models 289A, 288, and 288A (Licensee References 8, 25, 26, 31-34, and 36) 3 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 qualification documentation; however, the required environ- ,

mental service parameters were not enveloped with respect to pressure.

4.6.18 Equipment Item No. 9 Pressure Transmitter Incated Outside Containment  ;

Bailey Models KQ123 and KQ12C

• i (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped. i 4.6.19 Equipment Item No. 10A Limit Switch' Incated Outside Containment Honeywell Micro' Switch Model OP-AR (Licensee References 14 and 17) .

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced qualification documentation; however, the required environ-mental service parameters were not enveloped with respect to temperature and pressure.

The Licensee states that the equipment will be qualified or replaced.

_nklin Res,e_ arch _ Center

TER-C5417-7 4.6.20 muipment Item No.10B Limit Switch Incated Inside Containment Honeywell Micro Switch Model CP-AR (Licensee References 14 and 17)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced a test report; however, the required environmental service parameters were not enveloped.

The Licensee states that the equipment will be qualified or replaced.

4.6. 21 Equipment Item No.11 Solenoid valve Incated Outside Containment ASCO Models WPHT8321A1, HT8321A6, HT8211B33, HB8342A4, HB8302C25RV, HT8262C71, 8262D23, HT8 316B15, HTX-8320A70, 8302C26D, JV182-084, 8302C26RV, HV180-414, HT832322, HT8 316C37, HVA904052A, HT80033, 8344B5, and HT8344A5 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the tequirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.'

4.6.22 Equipment Item No. 12 Resistance Temperature Detector Located Inside Containment Pyco Model 100-OfM Platinum (Licensee Reference 18)

Licensee Reference 18 is not a test report; therefore, qualification

, documentation is deficient for this item. In addition, the LOCA temperature profile is not enveloped.

4.6.23 Equipment Item No.13 Limit Switch Incated Outside Containment Bettis Models RX-341 and RX-41 (Licensee References 14-16)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced qualification documentation; however, the required environ-mental service parameters were not enveloped with respect to pressure.

nk!!n Research Center A Oswason of The Frenhen W

1 TER-L$417 7 l 4.6.24 squipment Item No.14M Motor Operator Incated Outside Containment '

Limitorque SMB Models (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped. -

4.6.25 Equipment Item Nos. 14N and 140 Motor Operator Incated Outside Containment Limitorque SMB Models (Licensee References 2, 3, 4, and 57)

Review of the Licensee's System Compe"ent Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are cot satisfied. The Licensee has referenced qualification documentation; however, the required environ-mental service parameters were not enveloped with respect to temperature.

4.6.26 Equipment Item No. 15 Radiation Detector Located Outside Containment GE Model 194X927G (Licensee Reference 27)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has referenced qualification documentation; however, the required environ-mental service parameters were not enveloped with respect to pressure, humidity, t.nd radiation.

4.6.27 Equipment Item No.18A Motor Operator Located Inside Containment

• Limitorque Model SMB (Licensee References 2 and 3)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced a test report, and the required environmental service parameters were not enveloped.

4-24 b Franklin Research Center 4 om.aa as m n.a.s. m

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r TER-C5417-7 4.6.28 Equipment Item No. 68 He# Shrink Insulation Located Inside and Outside Containment Pennwalt Corp. , Model Not Stated (Licensee reference not cited) h Review of the Licensee's System component Evaluation Work sheet indicates i that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental

- service parameters were not enveloped.

4.6.29 Equipment Item Im. 20B Relay Incated outside Containment GE Model CR2811A217Y (Licensee Reference 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 qualification documentation; however, the required environ-mental service parameters were not enveloped with respect to radiation. The Licensee states that a qualification investigation is currently being performed; if the equipment is found unqualified, it will be replaced.

4.6.30 Equipment Item No. 20C Relay It.cated Outside Containment GE Model CR120A08002AA (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

. 4.6.31 Equipment Item No. 25 Motor Incated Outside Containment Tuthill Model CD259AT (Licensee reference not cited)

Review, of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

4-25 enklin Research Center A Chaman of The Femen inessume

l l

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TER-C5417-7 6

I 4.6.32 0;uipment Item No. 33 Pressure Transmitter Located Outside Centainment GE Model 552032HKZZ2 (Licensee Reference 50)

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

has not referenced qualification documentation, and the required environmental service parameters were not enveloped with respect to temperature, pressure, .

humidity, and radiation.

The Licensee states that the equipment will be qualified or replaced by June 1982.

4.6.33 Equipment Item No. 34 Solenoid valve Incated Inside containment ASCO Model 5450-(Licensee reference not cited)

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

has not referenced a test report, and the required environmental service parameters were not enveloped.

4.6.34 Equipment Item No. 39 Base Panel Located Outside Containment GE, Model Not Stated (Licensee reference not cited)

Review of the Licensee's System Cor4cnent Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01% 4te not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

Oh ~ranklin

~ ,e_Res arch Center f

l

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l O

} TER-C5417-7' L

t 4.6.35 Equipment Item No. 40 Control Switch Located Outside Containment GE Model CR2940BM204A (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bullctin 79-OlB are not satisfied. The Licensee has not referenced qualification docomentation, and the required environmental service parameters were not enveloped. 'Ibe Liceasee states that a qualifi-cation investigation is currently being performed; if the equipment is found unqualified, it will be replaced.

4.6.36 Equipment Item la). 42 Flow Transmitter Incated Outside Containment Bailey Model BQ13221 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

4.6.37 Equipment I am No. 44 Time Relay Incated Outside Containment Agastat Model 7022AC (Licensee reference not cited)

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, and the required environmental service parameters were not enveloped.

The Licensee has committed to replace this item by June 1982.

!j00fFranklin a cm,=oa.# w r Resea.rch

.m Center

1 TER-C5417-7 l

4.6.38 Equipment Item No. 45 Solenoid Valve Incated Outside Containment Johnson Services Model V-24-2 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requi::ements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped. ,-

The Licensee states that the equipment will be replaced by June 1982.

4.6.39 Equipment Item No. 46 Temperature Switch Located Outside Containment ',

Johnson Services Model A19AAC9 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

The Licensee states that the equipment will be replaced by June 1982.

4.6.40 m uipment Item No. 47 Position Switch Incated Outside Containment Johnson Services Model L-251-595 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

n C' Research Center 4-28 dJ Franidin 4 w as N r=*ma w I

\

l TER-C5417-7 4.6.41 Equipment Item No. 48 Motor Incated Outside Containment Reliance Models 256T, 23-1/4, and 17-1/2-1750

(Licensee Reference 59) 1 Review of the Licensee's System Component Evaluation Work Sheet indicates

~

that the requirements of IE Bt Jietin 79-01B are not satisfied. The Licensee has referenced qualification documentation; however, the required environ-

- mental service parameters were not enveloped with respect to pressure and test duration.

I 4.6.42 Equipment Item No. 50 terminal Lug Incated Inside and Outside Containment TEB Models Sta-Ron-Lug No. C10-10, Ring tungue Nos. G971 and 54108 (Licensee reference not cited) j Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not se.. . P'ied. 7tle Licensee j

has not referenced qualification documentation, and the required environmental 4

service parameters were not enveloped.

4.6.43 Equipment Item No. 51 Terminal Blocks Incated Inside and Outside Containment Curtis type L (Licensee reference not cited)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. :te Licensee has not referenced qualification documentation, and the required environmental i service parameters were not enveloped.

The Licensee states that the terminal blocks will be covered with a nonconducting watertight thermosetting foam or replaced with splices.

I

[~ 2J Franklin Research Center 4-29 4 % w w rwa w I - _ - _ - - _ , - . . - -. . . , _ , _ _ . _ . . . _ . _ ~._

l >

TER-C5417-7 4.6.44 Equipment Item No. 53 Iteminal Blocks Incated Inside and Cotside Containment GE mdels CR151D30 and EB-5 (Licensee reference not cited)

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

has not referenced qualification documentation, and the required environmental service parameters were not enveloped. .

The Licensee states that the terminal blocks will be covered with a nonconducting watertight thermosetting foam or replaced wf *h splices.

4.6.45 Equipment Item No. 54 Connector Incated Inside and Outside Containment Amphenol Model 48-03R18-31 PES (Licensee References 62 and 63)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced a test report; however, the Licensee stated that the ,

required environmental service parameters were enveloped and provided an analysis. ,

4.6.46 Equipment Item No. 55 Connector Incated Outside Containment Pyle-National Model NS2 (Licensee reference not cited)

Review of the Licensee's System Component Evaluation ifork Sheet indicates that the requirements of IE Bulletin 79-013 are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

The Licensee has committed to qualify this connector or replace it by June 1982.

~

_nklin Rese_ arch _ Center

TER-C5417-7 4.6.47 Equipment Item No. 57 Instrument Cables Incated Inside Containment Boston Ins. Wire & Cable Co. Model 1TR$16 (Licensee References 62 and 64)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not F.atisfied. The Licensee has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to pressure, temperature, and test duration.

4 I

l 1

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afl 4-31 aJU Franklin Research Center 4%wwr- m

t TER-C5417-7 4.7 NRC Category VI l EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED Dis category includes equipment items that 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.

Mr Brunswick Unit 1, no equipment is assigned to this category. ,

4 1

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1 UN rank'in Research Center A Omoon of The Fransen m

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l .,:

l-TER-C5417-7

, 4.8 SLMMARY OF THE EVALUATION The following tabulations represent a summary of the results of the equipment environmental qualification evaluation conducted by PRC in

~

accordance with the methodology presented in Section 3.

1. Table 4-1 shows the number of equipment items assigned to each NRC qualification category as a result of the evaluation.

Table 4-2 consists of Equipment Environmental Qualification Summary Forms for each equipment item, identifying compliance with the qualification requirements defined in Section 3. 'Itse following designations are used:

X = A deficiency with respect to compliance with a Guidelines requirement. Deficiencies result in equipmenc items categorized as unqualified or qualification not established.

O = Assignment to an NRC qualification category.

R = Replacement of the equ!mnt by the Licensee is planned. ,

l

• = Either replacement of the equipment or qualification by analysis or l test is planned by the Licensee.

b Frenidin Research Center A DMe=n of The Fransen insomme

t TER-C5417-7 i

Table 4-1 ]

NIMBER OF EQUIPMENT ITEMS IN EACH QUALIFICATION CATEGORY NRC Number of Category Category Definition Equipment Items I Equipment eat Satisfies 42 the General hequirements of the DOR Guidelines and .

IE Bulletin 79-OlB l II Equipment that the 0 Licensee Will Modify ,

or Relocate l

l III Equipment That the O Licensee Believes To Be Exempt From Qualification l

IV Equipment That Has 2.

Qualification Testing Scheduled But 13)t Completed V Equipment That Does Not 48 Satisfy One or More of l

the General Requirements i of the DOR Guidelines and ,

l IE Bulletin 79-OlB VI Equipment for Which Qualification is Deferred j 92 9001 ri.niain ae.e.rch C nte, A Ohamon of The Frarven ineueme

w M

l TER-C5417-7 Table 4-2 N PLANT NAME PAGE PRCTASK

• 4004'7 a"n smaavia Unit 1 l dhh* Franklin Research Cenar -

MfC"1"2"W PROJECT 02G4541741 UTIUTY Carolina Power & Light

\

EQUIPMENT ENVIRONMENTAL

. QUWTION %E TAC DATE/ ENGINEER

_ DOCKET lESJH18 50-324 424S4 r, /j,/ff _b

SUMMARY

REVIEW EQUIPMENTfTEM NUMSER ' # V

{ I l 2 l 3 l 4 lSalsej e l 7 l e l 9 lloajecelIs l 42l 3lseap4ejsecji4cl GUIDEUNE REQUIREMENTS (DESGNATIONS: X- DEFICIENCY.L-UMmMG CONDmON)

EVtDENCE OP OUAuriCATloN X X X X X X X X X X X X X RELATiONSNIP TO TEST SPEoMEN _

AGING DEGRADATION EVALUATED QUAUFIED UPE ESTASUSHED PROGRAM 70tDENTIFY AGING QUAL POR STEAM EXPOSURE PEAMTEMPERATURE ADEQUATE X , X X X PEAx PRESSURE ADEQUATE X X X X X TESTDURATION ADEOUATE X REQUIRED PROFILE ENVELOPED QUAL FOR SUSMERGENCE QU'AL POR CNEMICAL SPRAY X QUAL POR RADIATION X SETA RADIATION CONSIDERED TEST SEQUENCE TEST DURATION (1 HOUR + FUNCTION)

OUAUFICATlON CATEGORY O-CATEGORY DESGNATION

-SCEwS SATiSrY GuiDEuNES O O l O O O O II-OUAL PENDING MODIFICAT10N IN -EXEMPT FROM QUAL N -CU AL. TEST SCHEDULED

. v -sCEwS 00 NOT SATISFY GUIDEUNES O O O O' O O O O O O O O O VI -REVIEW IS DEFERREP REPLACEMENT SCHFLULED M M M UN Franklin Research Center w am v.w.an m.

4 TER-C5 417-7 i

h

! Table 4-2 (Cont.)

i A

}

FRC TASK y PLANT NAMg PAGE 2

4, b Franidin Research Center 4004.7 ava nrun vtek ente 1 ,

I t.D.C"M ITF PROJECy uTiuTV N1M Carolina Power & Light

) EQUIPMENT ENVIRONMENTAL QUAUFICATION '

DOCxET NRC TAC DATE/ ENGINEER 50-324 42484 / / C .

f Es a cis f.//o/f/ n ~

SUMMARY

REVIEW EQUIPMENTITEM NUMSER V

1-ist)4r l:4eliemli41]e44 li4ali46l Hies.lwoj is l is l if lisa{iesl as M i

GUIDEUNE REQUIREMENTS (DESIGNADONS: X- DEFICIENCY.L-UMmNG CONDmON) l X X X X X X X X EVIDENCE OP OUAUFCATION l

RELAT10NSNtP TO TEST SPEOMEN f AGING DEGRADATION EVALUATED i

QUAUP1ED UPE ESTASUSNED PROGRAMTOIDENTIPY AGING ouAL POR STEAM EXPOSURE X X X

! PEAxTEMPERATURE ADEQUATE

. PEAx PRESSURE ADEcuATE X X I- TESTDURATION ADEQUATE REQUIRED PROFILE ENVELOPED f OUAL PoR SUSMERGENCE oU'AL. POR CNEMICAL SPmAY l X X X

ouAL PoR RADIATION l eETA RADIATION CONSIDERED

! TEST SEoUENCE 4 Test DURATION 11 NOUR + FUNCTION) i l

QU AUFICATION CATEGORY O-CATEGORY DESIGN ATION

-sCEws SADSPY GUIDEUNES O O' O O O O O O O O O j u -oV AL PENDING MOOFCATION .

j 10 -EXEMPT FROM QU AL N -OUAL TEST SCNEDULED 0 l v -sCEws 00 NOT SADSFY GUIDEUNES O O O O O O O vi -Review is DEFERRED f M REPLACEMENT SCNEDULED 4

4 k

i [$ nklin Research Center a o- w n. rw in w.

5 i

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t J'

i TER-C5417-7 1

Table 4-2 (Cont.)

1 i

i j.

PLANT NAME PAGE A FRCTASK 3

Ubranklin Research Center 6004.7 m- sr-tek unit 1 kDDM=Y PROJECT 01G-CS417 01 UINTY Carolina Power & Light

! EQuePMENT ENVtRONMENTAL i OUANN DOCKET NRCTAC GmM/ ENGINEER

, iEs.sais ~ 50-32s 426s4 g/jgfe p 1

SUMMARY

REVIEW EQUIPMENTITEM NUMsER ' V j-toc l al l tt j a3l ts l ts l 27l te l tsl 30 hi43se l 3t l 33 l 34l 3S l 3sl 37 l 3e l (CESIGNATIONS: X- DEFICIENCY,L-UMmNG CONOmON) j GuioEUNE REQUIREMENTS

~

EvioENCE OF OUAuFiCATION X X X X X X X X X X XX RELATiONSNeP TO TEST SPEC: MEN AG8NG OEGRADATiON EVALU ATED

]

QU AUFIED UFE ESTAOUSNED l

' l PROGRAM TO IDENTIFY AGING OUAL FOR STEAM EXPO 6URE PEAx TEMPERATURE AoEQUATE X X X X X X FEAK PRESSURE ADEQUATE X X X X X X X i

TESTDURATiON ADECUATE X X g

REQUIRED PROFILE ENVELOPED QUAL FOR SusMERGENCE OdAL FOR CNEMICAL SPRAY QUAL FOR RAotAriON X X X X X X X l jl eETA RAosATION CONSIDERED )

I TEST SEQUENCE

{ TEST DURATION (1 NOUR + FUNCTION) i 1

0 QUAUFICATION CATEGORY O-CATEGORY DEStGNATION I -SCEwS SATISFY GUIDEUNES O O O O O l 0 0 i II-QUAL PENDING MOOlFICATION i e lit -EXEMPT FROM QUAL.

IV -OUAL TEST SCNEDULED 0

) v -SCEwS 00 NOT SATISFY GUIDEUNES O O O O O O O O O O O

. vi -REVIEW IS DEFERRED REPLACEMENT SCNEDULED M M M M 1

)

I t

I

1. ~3 nklin Rese

-~_ arch Center .

- ,m,- ,,-w- ,m----nr. ,, e -r,,---r.,, .,.e e,..w.-.,-nr, - - - - - - - - - - - - - - - - - - - - - - - - -

e 3 l

TER-CS417-7 i

9 Table 4-2 (Cont.)

I t

4 N PLANT NAMg PAGE PRCTASM h 'M' 7 suit stun vtek unic 1 4

! 00h ranidin Reneerch C4nter

$DU*1* "E"W PmOJECT M17-01 UTiuTY ,

Carolina Power & Light

) RoulPMENT ENvlRONMENTAL DOCMET- NRC TAC DATElENGINEER 1E84018 50-324 42484 4 g s

SUMMARY

REVIEW EoulPMENTITEM NUMSER

1. V #

]

) 3s l 4o l 4e l 4a l 43 l 44 l 4Sl 4e l 4?l 4e l 4sl So l Sa l Sal 53 } s4l SSl Se l 57 l 1 GuioEUNE REoUIREMENTS (OESGNATIONS: X- DEFICIENCY.L-UMmNG CONDmON)

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TER-C5417-7

I

! Table 4-2 (Cont.) ,

I i

J PRCTASK , y PLANT NAME PAGE Oh Frenidin Research Center 4ma. 7 m s m wick emit i I- A. D d " 4" E W PROJECT UTluTY EQUIPMENT ENVIRONMENTAL 08tM:sM74 Carolina Power & Lithe A

'DOCMET NRC TAC OATEIENGINEER iEs meis 5o.324 '424s4 g/,,fff p l SuMMAm REV4W EQUIPMENTfTEMNUMSER ' @ ,

j u l u l eol es i a l n l oq u l ular l ul u poalrog ri lu l l l l  !

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} EvioENCE OP ouAuriCAriON X R I RELATiONSHep TO TEST $8EQMEN 1

j AGING DEGRADAT10N EVALUATED j QUAUPIED UPE ESTASUSHED PROGRAM 7010ENTIPY AGING QUAL POR STEAM EXPOSURE PEAKTEMPERATURE ADEQUATE j PEAK PRESSURE ADEQUATE i TESTDURATlON ADEQUATE

} REQUIRED PROFILE ENVELOPED j oust POR SusMERGENCE _

f fXiAL POR CHEMICAL SPRAY i QUAL POR RADIATION SETA RADIAT10N CONSIDERED TEST SEQUENCE 8

TEST DURATION (1 NOUR + PUNCTION) 4 QUAUPICATION CATEGORY O -CATEGORY DESIGNATION j , i-sCEwS SATiSPv GuioEUNES O O O O O O O O O O O O O O

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TER-C5417-7

5. CONCLUSIONS The tabulations presented in Section 4.8 represent a summary of the results of the equipment environmental qualification (EEQ) evaluation

. conducted by FRC in accordance with the methodology presented in Section 3.

The evaluations are based on the available qualification documentation provided by the Licensee, complemented in several cases by other relevant technical information. The major deficiencies that have been identified are i

shown in the Muipment Environmental Qualification Summary Forms (Table 4-2) .

The review has shown that qualification documentation for many equipment items is inadequate or non-existent, and that additional information is essential.

The DOR Cuidelines require the Licensee to have ongoing programs to review surveillance and maintenance records in order to assure that j safety-related equipment that exhibits age-related degradation be identified and, if necessary, replaced. No evidence of such programs was included in the Licensee's submittal.

j

{ The present evaluation of the status of environmental qualification of the safety-related electrical equipment installed in Brunswick Unit 1 involves l only equipment located in the " harsh environment" areas. The EEQ review of equipment items located in " mild" areas and equipment needed for TMI Action Plan compliance has been deferred until af ter February 1,1981.

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- _ . , - . . ~ . - - . . - -. -. . .- .- -

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TER-C5417-7 ,

l'

6. REFERENCES

1. Qualification Test Report of stiermocouples and RTO 770831/8.31.77

2. Qualification Type test Report Limitorques B003/6.7.76

• 3. ' Test of Limitorque Valve operator 0600198/F-C2232-01/ll.68

4. Qualification not of Limitorque valve F-C3117/12.71

(. 5. Micro Switch LTR - 24407

6. F5AR Appendix M Section M7.9 Sept.1972, DRR812, 3/29/72 f'

l- 7. Reactor Building Environmental Report

8. Qualification Test Report for ITT Barton R3-288A-1/10.2.79

9. Material Analysis for GE 4-338-10

10. BWR Qualification Summary for GE QSR 111-A-05

11. Material Analysis for Yarway Imvel Switch H-338-ll

12. Material Analysis for GE H-338-2

13. Namco Limit Switch Index

14. File Reference No. 6335 of Nuclear Rad. and Switch Application

15. Evaluation of Asbestos Free Plastics FR 14171/2.21.79

16. Humidity Test of General Purpose Phenolic M. FR 12774/7.15.75

17. Quality Assurance Test FR 13048/2.3.76

18. Material Analysis for Pylo RTOs H-338-7

19. Material Analysis for Barksdale Pr. SW H-338-15

20. Material A .slysis for Static 'O' Ring B-33-12

21. Material Analysis for Namco Limit SW H-338-16

22. BWR Qualification Summary for R.L.S. QSR-ll6-A-02 I

23. Material Analysis for F.T.S. H-338-7

24. Engineering Evaluation of Motors 10/25/80

25. ITT Barton Eng. Report No. Rl-288S-ll and Qualification Test Procedure

26. BWR Qualification Summary for B. P. S. QSR-029-A-01

?. BWR Qualification Summary for GE Rad Set QSR-015-A-01

2. Viking Laboratory GE Summary NSE79001, 830411

29. Ogden wchnical Laboratory GE Summary NSE 79002, 670822

! 30. Ogden technical Laboratory GE Summary NSE 79003, 670822

! 31. GE Summary NSE 79004 Addendum to TP-199-4 5/24/71 n A eSeEhCeMW

, A Osamen af The Peenten sneemme l

l l

. . _ _ 2 . _ . _ _ _ . - --__-.___ _ . - _ _ . _ . _ _ . _ . _ _ _ _ _ _ _ _ _ . . _ _ . . _ _ . . . _ .

TER-C5417-7

32. GE Summary NSE 79005 Mdendum to TP-199-4; 5/24/71

33. GE Summary NSE 79006 Mdendum to TP-199-4; 5/24/71

34. GE Summary NSE 79007 Mdendum to TP-199-4; 5/24/71 ,

35. GE Sununary NSE 79008 Mdendum to TP-199-4; 5/24/71

36. GE Summary NSE 79009 Mdendum to TP-199-4; 5/24/71 i ,

. 37. GE Sununary NSE 79010 Addendum to TP-199-4; 5/24/71

38. GE Summary NSE 79011 Mdendum to TP-199-4; 5/24/71 +

39. GE Summary NSE 79012 2755-4755 8/4/71

40. GE Sunusary NSE 80014 2755-4755 8/4/71 .

41. GE Summary NSE 80015 2755-4755 8/4/71  ;

42. GE Summary NSE 80021 70526 5/4/71

43. GE Susunary NSE 80024 596-0398 8/13/75

44. GE Summary NSE 80025 596-0398 8/13/75

45. GE Summary NSE 80027 596-0398 8/13/75

46. GE Summary NSE 80030 596-0398 8/13/75 +

47. GE Summary NSE 80031 596-0398 8/13/75 ,

48. GE Susunary NSE 80032 12625 6/5/62 ,

49. GE Sununary NSE 80033 12625 6/5/62 4 50. GE Sununary NSE 80036 4/28/70

51. Material Analysis for Magnetrol Flow Switches, H-338-13

52. Material Analysis for Cherry Electrical Products H-338-9

53. Approved Eng. Mst Laboratories GE Summary NSE 80028 .

1 54. BWR Equipment Qualification Summary for Magnetrol, QSR030-A-01 i 55. Farr Co. Environmental Qualification Test Report Class IE Corp. 10/14/80

56. Material Analysis for Namco Limit Switch Mode _ D2400X; H-338-17

57. Qualification Type Nst Report, Limitorque Valve No. 600376A, 5/13/76

58. Material Analysis for Barksdale W mperature Switch H-338-4

59. Reliance & Co. Sununary Report NUC-9, 7/1/78 .

60. Eng. Nst Report on AMP Rad. Res. #110-11516, 3/6/80

61. Qualification Tent Program for Termination Block F-C5205-03,10/79

62. Radiation Testing 44800R16-24 by Westinghouse 12/1/71

63. Material Analysis for Westinghouse Den. H-338-3

64. General Data Sheet of Boston Ins. Wire & Cable Co. #8714,1/14/72

65. FIRL-Final Report, Mst of Raychem FL. #F-C4033-1

~

nklin Research Center A Opas.o9 of The Fransen Insense

- l TER-C5417-7 {

66. FIRL-Final Report, Qualification est GF-C368

67. FIRL-Final Report, (palification Test GF-C2857

68. Okonite Co. Engineering Report #141, 2/29/72

69. IDCA Qualification of Kerite 600 Volt HTK

70. Qualification of Firewall III Class "lE" 7/7/77

71. Raychem Eng. TT.st Report WCSF-N

, 72. Design Approval 7est in Westinghouse, FP3811, 8/72

73. Accident Enviromental Test Report PEN-RLK-3-16-0174.

74. IAtter from G. Lainas, NRC, to A. Schwencer, NRC, February 19, 1980. .

Subject:

Electrical Equipment Environmental Qualification, including DOR Guidelines.

75. IAtter from Norman C. Moseley, NRC, to B. H. Grier, J. P. O'Reilly, J. G.

Keppler, K. V. Seyfritz, R. H. Engelken, NRC, Sept 1mber 29,1980.

Subject:

IE Class Supplement No. 2 Bulletin 79-01B, Environmental

. Qualification of Class lE Muipment.

76. Letter from Norman C. Moseley, NRC, to B. H. Crier, J. P. O'Reilly, J. G.

Keppler, K. V. Seyfritz, R. H. Engelken, NRC, October 24, 1980.

Subject:

IE Supplement N3. 3 Bulletin 79-OlB, Environmental Qualification of Class IE Muipment.

77. U.S. NRC Memorandum and Order (CLI-80-21) pursuant to the Petition for anergency and Remedial Relief filed with the NRC on November 14, 1977.

78. Carolina Power and Light Company Response, October 31, 1980, to NRC IE Bulletin 79-OlB, Environmental Qualification of Class lE Muipment, for Brunswick Steam Electric Plants 1 and 2.

79. NUREG-0588, " Interim Staf f Position on Environmental Qualification of Safety-Related Electrisal M uipment," October 31, 1980.

80. S. P. Carfagno and R. J. Gibson, "A Review of Muipment Aging Theory and

. Technology," Electric Power Research Institute Report NP-1558, September 1980.

6-3

@i]Uw Franklin Resear.ch Ce.nter A ce .t n rr . .

TER-C5417-7 i

APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS The Licensee has provided information [78] concerning environmental zones and postulated design basis accident conditions. Figures A-1 through A-8 show accident profiles for plant areas subject to transient accident conditions.

The specific environmental service conditions corresponding to plant zones are shown in Tables A-1 through A-3.

Brunswick Units 1 and 2 have a demineralized water spray system rather than a chemical spray system inside containment. This is considered in the Licensee's analysis. The Licensee's analysis of design basis accidents uses the following assumption: In the design of the Brunswick Units 1 and 2 pressure suppression containment (i.e. , drywell-torus) , flooding is not considered to be a credible accident environment due to the high volume, low hydraulic resistance flow paths from the drywell to the torus which immediately direct LOCA blowdown flow away from the drywell. HELB does not af fect environmental conditions inside containment and therefore is not considered for in-containment primary components.

Post-DDCA radiation levels in various regions of the reactor building are due to leakages from the drywell and due to fluids that are recirculated from inside the primary containment to accomplish long-term cooling following a LOCA. The LOCA-induced radiation environment and the subsequent transport process are evaluated in accordance with the guidelines in NUREG-0588. For .

. conservatism, all leakages from dryvell are assumed to be leaking into any one compartment adjacent to drywell. The leakage outflow from that compartment is then assumed to be uniformly mixed in the remainder of the reactor building.

The conservatism of this method lies in the conservatively high computed values for the concentrations of fission products in each of the engineered safety f eatures compartments.

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a Table A-1 ACCIDENT PRESSURE PROFILE TABLE HELB Analysis '

Per Reactor Building LOCA Environmental Report Area Raport Peak Peak Profile Area Description Compt. P essure Pressure Table No. (PSIG) (PSIG)

D RHR Rooms and 2,3,4 IV 1.5 0.2 Chase (El. 5'-0")

F Reactor Bldg.

, 20'-0" & Above 6 IV 1.0 0.2 LL HPCI Roow 1 IV 2.7 0.2 NN Core Spray Rooms 6 IV 1.0 0.2 PP RWCU Area 1 VIII 6.9 0.2 Main Steam Tunnel 6 IV 1.0 0.2 aa _

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l Table A-2 LOCATION OF SUBSTANTIAL FISSION PRODUCT INVENTORY O

e APPROXIMATE PEAK SOURCE LOCATION INVENTORY. Ci Reactor Building (Uniform Dispersal) Total: 8.1 x 106 l' N.G.: 5.6 x 106

, Iodine: 2.5 x 106 SGTS Filters in Reactor Building Iodine: 4.2 x 105.

Drywell Total: 5.5 x 108 N.G.: 4.0 x 108 Iodina: 1.5 x 108 Pressure Suppression chamher Iodine: 3.0 x 108 Typical Small Compartment (Adjacent to dryvell in Reactor Building) Total: 105 o

Typical Large Compartment (Adjacent to drywell in Reactor Building) Total: 10 6 G

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&5 . Normal mg Operating Dose Hemimuss Accident Does a n reehold (Rede) (Rede) h Component Location (Rede) 40 Years First Hour 30 pays Casseente I M reshold dose applies to tubri.

• Limitorque Inside S a 10 I 6 a 10 I --- 4 x 10 ,

S Velve Operatore Drywell (Menimum) cation seals, made of Viton.

' neee seele een be periodically replaced to keep the normal oper-stieg does subetentially below the threshold. S e listed normat operating dose le the mesimum dry-well dose, t.o., et the outside surface of the sacrificial ehtold at core mid-plane. Leekage from the esels does not imply fatture of the operatore to function. .

> 9 a 100 Accident does based on conserve-8 solenald Reactor 6 a 107 2 a 103 1 a 105 valves tive assumption of eon-uniform U sutiding Below 20' El. stains of fleston products la Reactor Butiding. Dose given to monimum for any cogartment adje-cent to the drywell. Normal operating dose based on 5 mr/hr for 40-years.

Pressure Reactor 2 x 10 8 , 2 a 10 3 1 x 105 9 m 10 0 same comment se for solenoid Switches / B 'lding velves.

Transmittere Be.ow 20' 51.

I' ump Hotors: RHR toon 6 e i.ube cs Room 1 a 108 2 a 103 1 a 105 g,g e Insulation 5 x 10I 2 x 103 1 a 105 g,g S a 108 2 a 103 1 a 105 9 a 10 l

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i' TER-C5417-7 i

APPENDIX B - LISTING OF SAFETY-RELATED ELECTRICAL EQUIPMENT l

This appendix lists groupings of safety-related electrical equipment for g Brunswick Steam Electric Plant Unit 1. Bquipment item numbers in the list are

. used in the Equipment Environmental Qualification Sumnary Mrnis and in the equipment qualification discussions in Section 4.

This list was generated from the Licensee's System Component Evaltation Work Sheets (SCENS) in Reference 78. Mr each item, tne list identifiet the manufacturer and model number, plant location, SCEWS number, applicable qualification references, and TER section where the f tem is discussed.

FRC paginated the original Carolina Power and Light Corrpany Environmental Qualification of Electrical Equipment Report as follows:

?

Page Nos.

volume 1,Section V, subsection 1 1-7 volume 1, oection V, subsection 2 8-52 volume 1,Section V, Subsection 3 53-77 Volume 1,Section V, Subsection 4 78-90 volume 1,Section V, Subsection 5 91-129 Volume 1,Section V, Subsection 6 130-185 Wlume 2,Section V, subsection 7 186-212 Volume 2,Section V, subsection 8 213-293 volume 2,Section V, Subsection 9 294-311 e

Volume 2,Section V, Subsection 10 312-328 Volume 2,Section V, Subsection 11 329-354 Volume 2,Section V, Subsection 12 355-384 volume 2, dection V, subsection 13 385-401 Volume 2,Section V, Subsection 14 402-431 Wese page numbers will be used throughout this Technical Evaluation Report, nk!!n Research Center A Os=cenoa of The renseninesswe

TER-C5 417-7 PLANT NAME: BRUNSWICK UNIT 1 EQUIPMENT TER s ITDI ITEM QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCEL NO. REFERENCES NO.

1 Selector Switch Outside 1-3,92,94,164, 5,14 4.6.1 Honeywell Micro Containment 168,170,172,189, Switch- 192,194,230,232, PTSHE202C-B97 235,238,241,244, PTKBC2221CCC 246,248,250,252, PTKBC221CCB99 254,256,258,260, PTKBC2221CCF9 300 PTSHA202F-B81 2 Solenoid valve Inside 130,131,135,137, None 4.6.12 ASCO Ccatainment 139,141,158 HB-8302C25RU HT-8320A70 3 IAvel Switch Outside 5,6,53,98,150, 11,39,41,42 4.2.3 Yarway Containment 151,213-216 4418C 4 Pressure Switch Outside 7,58,75-77,118, 20,42 4.2.4 Static-O-Ring Containmer.t 287,289,290,326, 12N-AA4-X10TT 327 SN-AA3-X9STT .

6N-AA21-X9SVTT SA H2/02 Analyzer Ou tside 8 No t.- 4.6.13 Nuclear Measure- Containment ment Corp.

Model Not Stated a J

5B Radiation Analyzer Outside 9,10 None 4.6.14 Nuclear Measure- Containment

• ment Corp.

Model Not Stated 6 Level / Pressure Ou tside 11,14,15,353 None 4.6.15 Iniicator Containmen t D5. co 3'-

l 1

Jq^

D' LLU Frank!!n Research Center B-2 A Onneson of The Fransen wwemme

TER-C5417-7 EQUIPMENT TER ITEM ITEM QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCENS NO. REFERENCES NO.

7 Imvel Transmitter Ou tside 12 None 4.6.16 Bailey ContainA e BQ15222

, 8 Pressure Switch Outside 13,55,57,115-117, 38,32,34 4.6.17 Barton Containment 152-154,155 288A 289A 288 9 Pressure Trans- Outside 16,17 None 4.6.18 mitter Containment Bailey KQ123 KQ12C 10A Limit Switch Ou tside 18,38,41,48,50,. 14,17 4.6.19 Honeywell Micro Containment 159 Switch i OP-AR 10B Limit Switch Inside 157 14,17 4.6.20 Honeywell Micro Containment Switch OP-AR 11 Solenoid Valve Ou tside 19,20,23-29 None 4.6.21 ASCO Containment 31,33,35,39, WPHT8321A1 40,42,43,45, HT8321A6 47,49,51,143, HT9211B33 145,147,149, HB8342A4 160,181,182, HB8302C25RV 281,303-311,

• HT8262C71 320-323,325, 8262D23 340,344,373-384 HT8316B15

, HTX-8 320A70 8302C26D JV18 2-084 8302C26RV HV180-414 HT832322 HIS316C37 HVA904052A HT80033, 8344B5 HT8344A5

~

I 00 Franklin Research Center J

A Ohanson of The Fransen w

TER-C5417-7 f

E EQUIPMENT TER ITM ITi? QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCDiS NO. REFERENCES NO.

12 Resistance Inside 21,22 18 4.6.22 Temperature containment ,

Detector Pyco

,100-OHN Platinum e

13 Limit Switch outside 30,32,34,44,46 14,15,16 4.6.23 Bettis Containment RX-3 41 RX-41 14A Pitor Ooerator Outside 36,63,64, 2,3,4,57 4.2.5 Limitorque Containment 69,70,71,72 SMB 14B Motor Operator Outside 37,65,66,272, 2,3,4,57 4.2.5 Limitorque Containment 282,283,291,341, SMB 342,345-350,352, 359,360,362,363, 366,367,368,369 14C Motor Operator outside 67,68,280 2,3,4,57 4.2.5 Limitorque Containment SMB 14D Motor Operator Ou tside 103 2,3,4,57 4.2.5 Limitorque Containment SMB 14E Motor Operator Ou tside 106,111,112 2,3,4,57 4.2.5 Limitorque Containment SMB 14F Motor Operator Ou tside 108,109,110, 2,3,4,57 4.2.5 Limitorque Containment 200 SMB 14G Motor Operator Outside 133,198 2,3,4,57 4.2.5 Iimitorque Containment SMB 14H Motor Operator Outside 184 2,3,4,57 '. 2.5 Limitorque Containment SMB nk!!n Research Center

~ ~ - . - .

TER-C5417-7 EQUIPMENT TER ITEM ITEM QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCENS NO. REFERENCES NO.

14I Motor Operator Outside 197 2,3,4,57 4.2.5 Limitorque Containment SMB j 3 14J Motor Operator Outside 270 2,3,4,5'i 4.2.5

Limitorque Containment .

l 2B 14K Motor Operator Outside 274 2,3,4,57 4.2.5 Limitorque Containment SMB

- 14L Motor Operator Ou tside 337,338 2,3,4,57 4.2.5 Limitorque Containment SMB 14M Motor Operator Outside 105,107,113, None 4.6.24

, Limitorque Containment 176,179,199 SMB 14N Motor Operator Ou tside 180 2,3,4,57 4.6.25 Limitorque Containment SMB 140 Motor Operator Outside 201,265-269, 2,3,4,57 4.6.25 Limitorque Containment 271,273,275, SMB 276-372

• 15 Radiation Outside 52 27 4.6.26 De tector Containment.

GE 194X927G 16 Pressure Switch Ou tside 54,56,119-122, 19,43-46, 4.2.6 Barksdale Containment 161,162,204-207, 48,53

. B2T-M12SS 217,227,228,288, D2T-M18SS 291,301,302,318, PlH-M340SS 319

'IC-96 2 2-1 PlH-M85SS-V D2H-M150SS D2T-M150SS

~

Uh Frank!!n Research Center A Omeson of The Founsen tm

TER-C5417-7 i EQUIPMENT TER ITEM ITEM. QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCENS NO. REFERENCES NO.

17 Motor Outside 59,60,263,264, 9,10,24 4.2.7 GE Containment 355-358 s SK6 5K8 18A Moto: Operator Inside 219-226 2 , .' 4.6.27 Limitorque Containment l WB 18B tbtor Operator Inside 73,74,104, 2,3 4.6.2 Limitorque Containment 132,177,178, SW 183,196,284 19 Motor Control Outside 78-90 None 4.5.1 Center Containment GE IC-7700 20A Relay Ou tside 163,166,167, 12 4.2.8 GE Containment 174,175,188,191, CR2810A14AT 229,234,237,240, CR2811A217Y51 243,262,385,387 HFA51A49H CR2810A14AC CR2810A14AK2 20B Relay Ou tside 91 12 4.6.29 '

GE Containment CR2811A217Y 20C Relay Outside 329-332 None 4.6.30 -

GE Containment CR120A08002AA ,

21 Control Switch Outside 93,165,169,171, 5,14 4.6.3 Honeywell Micro Containment ~ 7 3,19 0,19 3,19 5, Switch 231,233,236,239, PTSHA201 242,245,247,249, PTSHA202F-B52 251,253,255,257, 259,261 22 Level Tra.nsmitter outside 95 11,40 4.2.3 Yatway Containmemt 4418EC B-6 dEanklin Research Center A Deweean of The Fruen m

TER-C5417-7 EQUIPME$T TER

! ITDI ITEM

• QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCENS NO. REFERENCES NO.

l

[ 23 Flow Switch outside 61,62,101,285 8,26,37,38 4.6.4 id Barton Containment 289 l

, - 24 Level Switch Ou tside 96,97,186, 25,31 4.2.26 I Barton Containment 202,203,218, 288A 314 288 25 Motor Ou tside 100 None 4.6.31

'tu thill Containment CD259AT 26 Flow Transmitter Outside 102 50 4.6.5 GE Containment 50-555111BDAA3PDR

, 27 Level Switch Outside 114 22,49 4.5.2 Robertshaw Containment SL-205-A2-Ril-Bil-1 28 Thermocouple Ou tside 123,128,129,185, 1,29, 4.2.9 Pyco Containment 208-210 30 N145C3224-P1 29 Temperature Ou tside 124,125,127,156, 23,28 4.6.7 Switch Containment 211,212 Etnwal 17002-40 30 Limit Switch Inside 134,136,138,140, 13,21 4.2.10

• NAMCO Containment 312 EA740-80100

, 31 Limit Switch Outside 142,144,146,148, 13,21,56 4.2.11 NAMCO Containment 313,339,343 An EA740-80100 B: D2400X-R 32 Limit Switch Inside 157 14,17 4.6.8 Honeywell Micro Containment Switch OP-AR

~

_nklin Rese_ arch _ Center

TER-C5417-7 EQUIPMENT TER l

ITM ITM QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCDiS NO. REFERENCES NO.

33 Pressure Trans- Outside 286,293 50 4.6.32 mitter Containment t_

GE 552032HKZZ2 34 Solenoid valve Inside 4 None 4.6.33 ASCO Containment 5450-5 35 Flow Switch Outside 294 51 4.2.12 Magnetrol Containment F-521 36 Position Switch Outside 295,297 52 4.2.13 Cherry Electrical Containment Products Corp.

E23-6 0H 37 Position Switch Ou tside 296,298,299 14,17 4.6.9 Honeywell Micro Containment Switch OP-DAR 38 Level Switch Outside 324 54 4.6.10 Magnetrol Containment 5.0-751 39 Fuse Panel Outside 328 None 4.6.34 GE Containment Model Not Stated 40 Control Switch Outside 333,3J4 None 4.6.35 GE Containment ,

CR2940BM204A 41 Motor Control Outside 335 55 4.2.14 Farr Co. Containment D51423 42 Flow Transmitter Ou tside 354 None 4.6.36 Bailey Containment f BQ13221 43 Temperature Ou ts ide 364 58 4.2.15  :

Switch Containment l Barksdale ,

T2H-M251S1-2 000 r,.nwiin a .,cn cent ,

A Dhimon of The Fransen m

TER-C5417-7 EQUIPMENT TER ITM ITm QUALIFICATION SE,CTION NO. DESCRIPTION LOCATION SCENS NO. REFERENCES NO.

44 Time Relay Outside 386 None 4.6.37

' d Agastat Containment 7022AC

.. 45 Solenoid valve Outside 388,389 None 4.6.38 Johnson Services Containment V-24-2 46 Temperature Outside 390-395 None 4.6.39 Switch Containment Johnson Services A19AAC9 l

47 Position Switch Ou tside 396,397 None 4.6.40 Johnson Services Containment D-251-595 48 Mo tor Outside 398-401 59 4.6.41 Reliance Containment 256T 23-1/4 17-1/2-1753 49 Terminal Lug Inside/ 403-404 None 4.6.11 AMP Special Outside Industries Containment PIDG-Nylon &

Plastigrip 50 Terminal Lug Inside/ 426-428 None 4.6.42 T&B Outside Sta-Kon Containment

' Lug C10-10 Ring tongue G971, 54108 o

51 Terminal Block Inside/ 410 None 4.6.43 Curtis Outside Type L Containment 52 Terminal Block Inside/ 431 61 4.2.28 Weidmuller Outside 6941 Containment

~'

00b Franklin Research Center A DMoon of The Fransen Insense

9 TER-C5417-7 EQUIPMENT TER l ITM ITm QUALIFICATION SECTION NO. DESCRIPTION LOCATION SC NS NO. REFERENCES NO.

53 Terminal Block Inside/ 411-413 None 4.6.44 GE Outside CR151D30 Containment EB-5 l 54 Connector Inside/ 405 62,63 4.6.45 ,

l Amphenol Outside 48-03R18-31P&S Containment 55 Connector Ou tside 420 None 4.6.46 Pyle-National Containment NS2 56 Instrument Cable Outside 406 64 4.2.27 Boston Ins. Wire Containment

& Cable Co.

IPR $16 3PR$16 ITR$16 57 Instrument Cable Inside 407 64 4.6.47 Boston Ins. Wire Containment

& Cable Co.

1TR$16 58 Instrument Cable Inside/ 422 65 4.2.16 Raychem Corp. Outside Flamtrol Containment IPR $16 ITR$16 59 Thermocouple Ou tside 408 64 4.2.17 Cable Containment Boston Ins. Wire 8

& Cable Co.

1PR$16 SPR$16 .

60 Thermocouple Outside 425 66 4.2.18 Cable Containment Samuel Moore &

Co.

Dekoron ECI 1PR$16 SPR$16 ON Franklin Research Center 4 % or n Fr.,wn %

TER-C5417-7 EQUIPMENT TER

. ITEM ITEM QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCDiS NO. REFERENCES NO.

61 Power Cable Outside 409 67 4.2.19 4 1000 V Containment Cerro Wire &

Cable Co.

4/c66, 4/ct10,

.1/ct12, 4/ctl6, 7/ctl6 62 Power Cable Outside 415,416 68 4.2.20 1000-5000 V Containment Okonite Co.

, 4/o AWG, 2/cf 8,

!' 4/cf10,4/ct6, 3/c250, 7/c250, '

3/c500 63 Control Cable Outside 414 69 4.2.21 Kerite Co. Containment 2/c412 4/ctl2 64 Control Cable Inside/ 421 65 4.2.22 Raychem Outside

! #8-9-10-12 Containment AWG Flamtrol 65 Control Cable Outside 424 70 4.2.23 Rockbestos Co. Containment 2/ctl2,

, 4/cel2, 1/ctl2, 1/cf14

, 66 Cable Wrmination Outside 417 68 4.2.24 Burndy, Okonite ' Containment 5000 V 67 Power Cable Outside 418 None 4.6.6 Splice Containment Burndy, Okonite T95 635 n n'" B-ll 1 U Franklin Research Center l 4 % as Th. rrmen m 1

TER-C5417-7 EQUIPMENT TER ITEM ITEM QUALIFICATION SECTION NO. DESCRIPTION , LOCATION SCEWS NO. REFERENCES NO.

68 Heat Shrink Inside/ 419 None 4.6.28 Insulation Outside a Pennwalt Corp. Containment Model Not Stated 69 Thermocouple Outside 423 69,71 4.2.25 Splice Containment AMP, Scotch, Raychem 320557,

1. 70, WCSF-N 70A Electrical Inside/ 429 63,72,73 4.2.2 Penetration Outside Assembly Containment Westinghouse Class B,C 70B Electrical Inside/ 430 4.2.2 Pene tration Outside Assembly Containment Westinghouse Class F 71 Terminal Lug Inside/ 402 60 4.2.1 AMP Special Ou tside Products Containment PIDG-Kinar a

e l

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2 nklin Research Center A Ch.sion of The Frarmen bestute -

TER-C5417-7 1

l

APPENDIX C - SAFETY SYSTEMS FOR Y5fICH ENVIRONMENTAL l

QUALIFICATION IS TO BE ADDRESSED o The Licensee has submitted the following list of safety-related systems that must function in order to mitigate the consequences of a design basis t

accident. This information was included in the Licensee's October 31, 1980 response (78] to IE Bulletin 79-01B.

o Automatic Depressurization System (ADS) - B21 o Containment Atmospheric Control System (CAC) o Core Spray System (CS) - E21

o Electrical Distribution System (ED) o High Pressure Coolant Injection System (HPCI) - E41 o Nuclear Steam Supply Shutoff System (NSSS) - A71 o Reactor Core Isolation Cooling System (RCIC) - 351 i o Residual Heat Removal System (RHR) - E'.1 o Reactor Instrument Penetration System (P

)

o Reactor Protection System (RPS) - C72 o Standby Gas Treatment System (SBGT) o Service Water System (SW)

, o Ventil-C ; air System (VA)

L i

e l.

1 0004 wFranklin or nw r, enResea.rch

==u. Center

. ._. -_ _ -. . _ _ , _ . . , . - , _ . _ ~ _ _ _ _ . _ ._._,- ,-