ML20009H112

Equipment Environ Qualification,Brunswick Steam Electric Plant Unit 2, Technical Evaluation Rept

ML20009H112
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-C5417-8, NUDOCS 8108060038
Download: ML20009H112 (100)

Text

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J TECHNICAL EVALUATION REPORT

. EQUIPMENT ENVIRONMENTAL QU ALIFICATION

. CAROLINA POWER AND i.IGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 NRC DOCKET NO. 50-325 NRC TAC NO. 42485 FRC PROJECT C5417 EG&G IDAHO, INC. SU8 CONTRACT NO. K-7615 FRC TASK 8 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 States Department of Energy. Neither EG&G nor the United States a Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, or any information, apparatus, product or process dis-closed in this report, or represents tha. 'ts use by such third party would not infringe privately owned rights.

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.. . Franklin Research Center A Division of The Franklin Institute 8108060938 810721 The Ben)ernn Frenkhn Parkway. Ptula, Pa. 19103(215)448 1000 PDR ADOCK 05000324 P pgg

TECHNICAL EVALUATION REPORT

. EQUIPMENT ENVIRONMENTAL QU ALIFICATION CAROLINA POWER AND LIGHT COMPANY

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BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 NRC DOCKET NO. 50-325 NRC TAC NO. 42485 FRC PROJECT C5417 EG&G IDAHC, INC. SU BCONTRACT NO. K-7615 FRC TASK 8 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 i . This report was prepared as an account of work performed under a subcontract from EG&G Idaho, Inc., a prime contractor to the United i States Department of Energy. Neither EG&G nor the United States Government nor any agency thereof, or any of their employees, I makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, or any information, apparatus, product or process dis-

! closed in this report, or represents that its use by such third party would not infringe privately owned rights.

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. . . Franklin Research Center A Division of The Franklin Institute The Ben 3arrsn Frarthn Parkway Phila Pa. 19103 (215) 448-1000

I TER-Cf417-8 CONTENTS Section Title Page 1 INTRODUCTION. . . . . . . . . . . . . . 1-1 1.1 Purpose of the Evaluation . . . . . . . . . 1-1 1.2 Generic Issue Background . . . . . . . . . 1-1 1.3 Scope of the Evaluation . . . . . . . . . 1-7 2 NRC CRITERIA PCR ENVIRONMENTAL QUALIFICATION. . . . . . 2-1 2.1 Criteria Provided by the NRC . . . . . . . . 2-1 2.2 Staff Positions and Supplemental Criteria . . . . . 2-1 2.2.1 Service Conditions Inside Containment for a Ioss-of-Coolant Accident. . . . . . . . 2-1 2.2.2 Submergence . . . . . . . . . . . 2-2 2.2.3 Equipment Incated in Areas Normally Maintained at Room Conditions . . . . . . . . . 2-2 2.2.4 Simulated Service Conditions and w st Duration . . 2-3 2.2.5 Deferment of Qualification Review . . . . . 2-3 2.2.6 Wst Sequence . . . . . . . . . . 2-4 2.2.7 Radiation . . . . . . . . . . . 2-4 3 METHODOIDGY 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 Enyironmental Service Conditions . . . . . 4-2 4.1.3 Aging and Qualified Life . . . . . . . 4-3 4.2 NRC Category I Equipment That Satisfies the General Requirements of 1

the DOR Guidelines and IE Bulletin *S-tilB . . . . . 4-6 i

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CONTENTS i

Section Title Page j 4.3 NRC Category II 3 Equipment That the Licensee Will Modify or Relocate . . 4-14  ;

4.4 NRC Category III Equipment W at the Licensee Believes W Be i Exempt From Qualification . . . . . . . . . 4-15 4.5 NRC Category IV ,

Equipment That Has Qualification '14 sting

! Scheduled but Not Completed. . . . . . . . . 4-16  ;

4.6 NRC Category V Equipment That Does Not Satisfy One or More of the Genere . Requirements of the DOR Guidelines and l

IE Bu",'A tin 7 9-OlB . . . . . . . . . . . 4-17 4.7 NRC Category VI Equipment for which Qualification Is Deferred . . . . 4-32 I 4.8 Summary of the Evaluation . . . . . . . . . 4-33 ,

S CONCLUSIONS. . . . . . . . . . . . . . 5-1 6 REFERENCES . . . . . . . . . . . . . . 5-1 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS APPENDIX B - LISTING OF SAFETY-RELATED ELECTRICAL EQUIPMENT APPENDIX C - SAFETY SYSTD4S FOR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED '

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1. INTRODUCTION 1.1 PURPOSE OF 11tE EVALUATION The NRC Office of Inspection and Enforcement (IE) issued Bulletin 79-018, i

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

The objectives of the NRC Equipment Environmental Qualification Review program are to evaluate nuclear power plant safety-related electrical equipment in accordance with criteria establiched by the NRC and to identify (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 anvironment and (3) equipment whose qualification documentation is deficient, i.e. , does not give reasonable assurance that the equipment is capable of performing its specified safety function.

To meet the overall program gosi , tr.c cbjective of this Technical Evaluation Report is to review the Licensee's submittals to determine if the Licensee reviewed its safety-related electrical equipment for environmental qualification in accordance with the 00R Guidelines and NUREG-0588 as required by IE Bulletin 79-01B. @e NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. If discrepancies are found, the audit will be extended.

1.2 GENERIC ISSUE BACKGROUND Safety-related electrical equipment must be capable of pe rforming design safety functions under all normal, abnormal, and accident conditions, of particular concern is the assurance that equipment will remain operable during 1-1

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l TER-C5417-8 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 emeironments are generally defined by the limiting conditions resulting from I

t the complete spectrum of postulated break sizes, break locations, and single .

failures consequent to a loss-of-coolant accident (LOCA), main steam line '

break (MSta) inside the reactor conta*nment, or a high energy line break (HELB) outside reactor containment (such as a main steam or feedwater line break) . The purpose of equipment qualification !s to provide tangible evidence 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 has e accumulated. Examples of such standards are EEE Standards 279-71, 323-74, 3d 3-7 4, 317-76, 33 4-7 4, 3 81-77, ? 82-8 0, and 627-8 0. NRC NUREG documents 0413 and 0588 have been developed to address this topic. In particular, NUREG-0588 I

(published for comment in December 1979) formally presented the NRC staf f 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 construction permit or operating license review process.

Although qualification standards and regulatory requirements have undergone considerable development, all of the currently operating nuclear power plants are required to comply with 10CFRSO, Appendix A, General Design Criteria for Nuclear Power Plants,Section I, Criterion 4. This criterion states in part tha t " structures, systems and components important to safety shall be designed to accommodate the effeccs of and to be compatible with the environmental conditions associated with normal operation, maintenar.ee, testing and postulated accidents, including loss-of-coolant accidents. "

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TER-C5417-8 Qualification requirements are also embodied in 10CFR50 Appendix A,

( General Design Criteria 1, 2, and 23 and Appendix B, Quality Assurance Criteria tor Nuclear Power Plants and Fuel Reprocessing Plants, Criteria III and XI. These requirements are applicable to safety-related equipment located inside as well as outside containment.

Tb1 NRC staff has evaluated the Licensee's equipment qualification l program by reviewing the qualification documentation of selected safety-related

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equipment as part of the operating license review for each plant. The NRC staf f has also used a variety of methods to assure that these general require-ments are met for electrical safety-related equipment. 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 323-71y however, no regulatory guide was iusued adopting this standard.

For plants whose Safety Evaluation Reports were issued af ter July 1,1974, the Commission issued Regulatory Guide 1.89, w' h ich 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 v agree to which the older operating nuclear power plants deviated from current licensing criteria. The subject of electrical equipment environmental qualification (SEP Topic III-12) was selected for accelerated evaluation as part of this program. Seismic qualification of equipment was to be addressed as a seperate 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 recommended that addit.onal effort should be devoted to examining the installation and environmental qualification documentation of specific electrical equipment in all operating reactors, 1-3

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

l Equipment at Nuclear Power Plants," which required all licensees of cperating 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 February 8,1979, the NRC Office of Inspection and Enforce- . j ment issued IE Bulletin 79-01, which was intended to raise the status of IE l Circular 78-08 to the level of Bulletin, i.e., action requiring a licensee response. This Bulletin required a complete re-review of the environmental qualification of safety-related electrical equipment as described in IE ,

Circular 78-08. ,

The review of the licensee responses indicated certain deficiencies 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 hereaf ter referred to as the " DOR Guidelines.") The document was prepared as ,

a screening standard for reviewing all operating plants, including SEP plants. It was originally intended that the licensees would evaluate their qualification documentation in accordance with the DOR Guidelines. However, initial NRC review of this documentation, which was compiled to support .

licensee submittals, revealed the need for obtaining independent evaluations '

and for accelerating the qualification review program.

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

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l TER-c5417-8 l-on January 14, 1980, the NRC Office of Inspection and Enforcement issued the DOR Guidelines and IE Bulletin 79-013, which expanded the scope of IE

, sul stin 79-01 and requested additional information on environmental qualification of safety-related electrical ee;uipment at operating facilities, excluding the 11 facilities undergoing the SEP review. $1s Bulletin cited the Dom Guidelines as the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification. We scope of the review was expanded to include high energy line breaks (inside and outside containment) in addition to equipment aging and submergence. - Se NRC advised the licensees that the criteria contained in the DOR Guidelines would be used in its review of licensee submittals; problems arising from this review would be resolved using NUREG-0588 as a guide.

In early February 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 Group held an open meeting at NRC headquarters to discuss an accelerated review program in accordance with the DOR screening guidelines. Hepresen-tatives of the Indian Point Units and Zion Station also attended this meeting. De NRC formally issued to all licensees represented at the meeting the DOR Guidelines document which included a second document, " Guidelines for Identification of Wat safety equipment of SEP Operating Reactors for Wnich Environmental Qualification Is to se 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 schedule.

For non-SEP plants, the NRC Office of Inspection and Enforcement formed a task force including a principal reviewer in each region and a task leader from headquarters. The regional members were assigned responsibility for the technical review of the licensees' responses to IE Bulletin 79-013, and the task leader was assigned responsibility for the overall coordination of the review effort with NRC staff to assure overall consistency. De regional enhan Reneerch Center 1-5 A DhEmen af The FrenaGRIneghes .

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, reviewers held meetings with the licensees in their respective regions, which resulted in staf f positions being issued in a supplement to IE Bulletin 79-OlB dated February 29, 1980. ,

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

• neering. Responsibility for reviewing the status of equipment qualification for all plants was assigned to this branch.  ;

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

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 10CTR50, Appendix A, General Design Criteria,Section I, Criterion 4. This Order also estatlished that the Safety Evaluation Reports on this subject, to be prepared by the NRC staf f, must be issued on Mbruary 1,1981 and that all subsequent actions to  !

be taken by licensees to achieve full compliance with the DOR Guidelines or NUREG-0588 must be completed no later than June 30, 1982. [

W e staff held regional meetings with the licensees and interested ,

parties during the week of July 13, 1980. The staff issued a second ,

supplement to IE Bulletin 79-01B, a response to significant questions raised during the public meetings, and two Orders. The Order, dated May 30, 1980, required the licensees to comply with the previously issued Commission Memorandum and Ceder of.May 27, 19 80 (CI.I-8 0-21) . The above orders required the licensees to complete the tasks identified in IE Eulletin 79-01B no later .

than mvember 1,1980 to allow the staff to comply with the February 1,1981 date imposed by the Commission order. @ e responses to the questions were issued on February 29, 1980; and the second and third supplements to IE Bulletin 79-OlB, highlighting the staff positions affecting the licensees' -

responses, were issued on September 29 and Octcber 24, 1980, respectively. (

In October 1980, EG&G Idaho, Inc. awarded Franklin Research Center (FRC) a contract to provide assistance in the equipment environrental qualification review for 13 of the plants whose licensees responded to IE Bulletin 79-01B.

FRC was to evaluate the licensees' equipment environmental qualification 1-6

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TER-C5417-8 submittals and to present the results in the form of a Technical Evaluation Report for each plant.

1.3 SCOPE OF THE EVALUATION Environmental qualification of safety-related electrical equipment was j selected by the NRC for accelerated review. Therefore, the actpe of this report 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 79-01B requires environmental qualification in accordance with the COR Guidelines or MUREG-0588 for all safety-related electrical equipment exposed to a harsh environment. Harsh environments include the limiting conditions resulting from (1) 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 included within 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 deviations) o equipment located where it is subject to outdoor environments o equipment protection against fire hazards o equipment protection against missiles, e

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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 i Electrical Equipment in Operating Reactors" (74]

o " Guidelines for Identification of D at Safety Bquipment of SEP Operating Reactors for Which Environmental Qualification Is 10 Be Addressed" (74]

l o NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Muipment' [79].

! Wese guidelines were issued for implementation to all licensees by the t

, NRC in February 1980.

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2.2 STAFF POSITIONS AND SUPPLDIENTAL CRITERIA a

stie NitC identified the following staff positions and supplemental criteria

!' to be used in conjunction with the referenced ocR screening guidelines.

j 2.2.1 SERVICE CONDITIONS INSIDE CONTAINMENT PCR A IDSS-OF-COOLANT' ACCIDENT (DOR Guidelines Section 4.1)

}~. For pressurized water reactors (PWRs) , the DGR Guidelines state that the containment temperature and pressure conditions as a function of time should be based on the most recent NRC-approved service conditions specified in the i

Final Safety Analysis Report (FSAR) or other licensee documentation. In the specific _ case of pressure-suppression type containments, the following minimum j 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 f unction of time are accounted for."

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TER-C5417-8 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.

The adequacy of a plant-specific profile depends on the assumptions and -

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 HELB accidents inside containment.

2.2.2 SUBMERGENCE (DOR Guidelines Section 4.1, Subitem 3; and Section 4.3.2, Subitem 3) equipment submergence (inside or outside containment) should be addressed where the possibility exists that submergence of equipment may result from HEtas or other postulated occurrences. Supplement 2 to IE Bulletin 79-OlB (75] provides the following additional 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 ,

after submergence, the equipment can be considered exempt from the submergence portion of the qualification requirements.

2.2.3 EQUIPMENT LOCATED IN AREAS NORMALLY MAXNTAINED AT ROOM CONDITIONS .

(DOR Guidelines Section 4.3.3)

Supplement 2 of IE Bulletin 79-01B [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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l TER-C5417-8 By Juns 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 tedt chamber environment envelop the required service conditions for a time 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:

"Dquipment 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 thac 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. Ihe 1-hour qualification requirement is based on the acceptance of a type test for a single unit and the spectrum of accidents (small and large breans) bounded by the single test."

2.2.5 DEF'.RMENT OF QUALIFICATION REVIEW

. Supplement 3 to IE Bulletin 79-OlB (76] permits the submittal of qualifica-tion documentation regarding TMI Action Plan equipment and the equipment i-required to achieve and maintain a cold shutdown condition to be delayed as follows:

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

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o Qualification information for 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.

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 Februa ry 1, 19 81. "

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 D)R '

Guidelines. Licensees must follow the test requirements of the '

applicable document.

l. 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 then fall in the first or second category " ,

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

Supplement 2 to IE Bulletin 79-018 [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 2-4

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TER-C5417-8 LOCA events inside containment (100% noble gases /50% iodine /lt partic-

ulates). These 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.

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 LOCA.

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

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

NUREG-0588 also provides the radiation source term to be used for qualifying equipment following non-LOCA events both-inside and outside containment (10% noble gases /l0t iodine /04 particulates) .

When developino :adiation source terms for equipw .t qualification, the License < must ensure consideration is given to chose events which provide the most bounding conditions. We following tr.ble summarizes these considerations:

LOCA Non-IDCA HELB Outside Containment NUREG-0578 NUREG-0588 (100/50/1 (10/10/0 in RCS)[*] in RCS)

Inside Containment Larger of NUREG-0588 NUREG-0588 (100/50/1 (10/10/0 in containment) in RCS) s or J

NUREG-0578 (100/50/1 in RCS) t j Ganna equivalents may be used when consideration of the 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 j' radiation source for environmental qualification of safety-related equipment. Cesium 137 may also be used."

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

RCS means reactor coolant system.

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

• items in various locations of Brunswick Steam Electric Plant Unit 2 in its submittals to the NRC. FRC f analyzed the Licensee's listing and grouped all identical or generically loentical equipment items located within plant areas that are exposed to the same environmental service conditions. This analysis resulted in a reduced listing containing 92 different equipment items that formed the basis for the review. In this report, the term "equipaent item" refers to a specific type of electrical equipment, designated by manufacturer and model, which is representative of all identical or go erie ally identical equipment in a plant area exposed to the same environmental service conditions (e.g., Flow Transmitter, Fischer & Porter, Model 10B2496, located within containnent) ,

Appendix A contains the anvironmental service conditions for each location, Appendix B contains the tabulacion of the equipment items and locations (the tabulation does not include equipment covered by the evalustion 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 tot 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 plant in a safe condition o identify the environmental service conditions o identify the maximum submergence levels o provide wt t*' en evidence (System Component Evaluation Work Sheets) of the enviraraental qualification of the equipment identified in the mastor list to demonstrate the espability 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 retest.r ed in Section 2.1.

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2 TER-C5417-8 o evaluate the qualification documentation using the DOR Guidelines and NUREG-05883 and, for equipment not having adequate qualification, to '

identify plans and schedules for establishing qualification o submit a Licensee Event Report (LER) for Class lE electrical equipment determined to be unqualified. ,

The responses to IE Bulletin 79-01B were requested by the NRC under provisions of 10CFR50.54(f), " conditions of Licenses," which requires the licensees to submit writtan statements, signed under oath. To provide assurance that the licensees satisfy the requirements of IE P'lletin 79-OlB and to provide a basis for the NRC Safety Evaluation Report R), FRC was requested to develop this Technical Evaluation Report (TER) by assessing the licensees' responses in relation to the general requirements of the DOR Guidelines as augmented by the supplements to IE Bulletin 79-018.

I The results and conclusions contained in this report a:e valid assuming that the Licensee's analyses of test reports referenced ir- the Licensee submittal are correct. Review of test reports was not within the scope of

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! FRC's assignment. However, the NRC staf f will audit selected analyses and test reports, incorporating the results of the reviews with the conclusions of the TERs, when developing the plant-specific SERs.

Each equipment item listed in Appendix B was assigned to one of the NRC categories defined in Table 3-1 af ter review of the associated System Component Evaluation Work theet provided by the Licensee.

i Topics not within the scope of the FRC evaluation ares o completeness of the licensee's listing of safety-related equipment o acceptability of licensee-provided environmental service conditions o acceptability of licensee-stated positions concerning safety systems a or component function .

o review and acceptability of qualification test reports and other qualification documentation.

The NRC Office of Inspection and Enforcement established a program to conduct an onsite verification inspection of selected Class lE equipment to verify proper installation of equipment, overall interface integrity, location i

nklin Research Center A Chamon of The Frannan Iriseause

4 TER-C5417-8 i

with respect to flood level for equipment inside containment, and m.inufac-turer's nameplate data. The manufacturer and model number from the nameplate data were to be compared to information given in the System Compoaent Evaluation Work Sheets of the licensee's report. The specific details of this

~

site inspection are documented in IE Inspection Report Sn-324/80-18. We I 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 EQUIPMEFF THAT SATISFIES THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES

' AND IE BULLETIN 79-01B nis category includes equipment items for which the System Component Evaluation Work Sheets are judged to be in compliance with IE Bulletin 79-01B, its supplements, and the general requirements of the DOR Guidelines. Por these equipment items, the licensee's System Component Evaluation Work Eneets indicate that the requirements of IE Bulletin 79-018 have been satirned, assuming that the licensee's analyses of qualification documentatian are complete and correct.

l 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 relcicated in order to comply with the DOR Guidelines require-

j. ments.

o NRC Ca tegory III EQUIPMENT THAT THE LICENSEE BELIEVES TO BE EXEMPT FROM QUALIFICATION

' ~

This category includes equipment items that the licensee believes to be exempt from qualification on the basis that (1) the equipment does not 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.

E a

(Continued) j.

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g-e TER-C5417-8 Table 3-1 (Cont.) ,

8 1

o NRC Category IV .

EQUIPMENT THAT HAS QUALIFICATION TESTING SCHEDULED BUT Nor COMPLETED

$1s 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 GENEkAL REQUIREMENTS

. OF THE DOR GUIDELINES AND IE BULLETIN 79-01B l

( This category includes equipment items judged to be deficient or j inadequate with respect to the general requirements of the DOR Cuidelines and IE Bulletin 79-OlB based on a review of the licensee's System Component ,

i Evaluation Work Sheets, i o NRC Category VI I

EQUIPMENT FOR WHICH QUALIFICATION IS DEFFRRED tis category includes e uipment items that have been addressed by the

. Licensee in the equipment env ronmental qualification submittals; however, the

! qualification review of this equipment has been 4-ferred by the NRC in j accordance with criteria presented in Sections 2.2.3 and 2.2.5 of this

report.

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TER-C5417-8

4. TECHNICAL EVALUATION General observations concerning the Licensee's approach to qualification are included in Section 4.1. Sections 4.2 through 4.7 identify the equipment  !

. items

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

4.1 ME' HODOLOGY 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 79-018.

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

"This report was compiled as follows:

"The 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 Company.

"The master list of cceponents 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 Derdgn Reports, The Final Safety Analysis Report, the Technical Specifications and the emergency Instructions in the Brunswick Steam Electric Plant Operating Procedares, 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 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) .

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1 TER-C5417-8

" At leant two cognizant engineers, one of whom holds an SRO license on l

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 the corresponding components in Unit I would be the same. Equipment  !

list comparisons and walk-through inspections are being conducted to ,

identify any discrepancies in installed equipment types."

'Ihe Licensee has not presented documentation derived from their walk- .

through inspections of Brunsuick Units 1 and 2 which would identify any

( discrepancies between Unit 1 and Unit 2 in installed equipment types. FRC has evaluated equipment qualification for Brunswick Unit 2 based on the premise ',

l ~

stated in the preceding paragraph.

l 4.1.2 ENVIROte4 ENTAL SERVICE CONDITIONS 4.1.2.1 TEMPERATURE AND PRESSURE l

The Licensee has provided pressure and temperature conditions resulting ,

from a HELB or LOCA as follows?

o accident profile for temperature inside containment o accident profile for pressure inside containment o accident profils for temperature of RHR and chase (EL. 5 ECEN) l o accident pressure table for RHR and chase (EL. 5 ECEN) o accident profile for temperature outside containment, elevacion 20' and above o accident pressure table fer outside containment, elevation 20' and above o accident profile for temperature of EPCI toom ,

l o accident pressure table for HPIC room l 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 ULU Franklin Research Crnter A DMesen af The Fransen m

TER-C5417-8 FRC considers the Licensee's approach to be satisfactory.

The Licensee also states:

"All Class IE electrical equipment located in the Control Building,

, Diesel Building, Augmented Of f-Gas Building, Servict Water Building and 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-RELB environments. Bquipment 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 not provide criteria for determining harsh and non-harsh radiation environments. It appears that the area where the maximum integrated radiation dose is less than 1 x 10 rd is considered non-harsh because only the equipment that is 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

• 4 1 x 10" rd. Most BWR plants use 1 x 10 rd 6s the cutoff point.

a 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) . ,

l "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 equipment, j libbranklin

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TER-C5417-8

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

o implement programs to review detailed surveillance and maintenance records to assure that equipment that exhibits age-related 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 contingent on implementation of a specified maintenance program. It is 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 lifetimes is specified and fulfilled, the qualified life of an equipment item may be changed during its installed life when justified by new information i that permits a reanalysis of the qualification program.

Establishing the qualified life for equipment is a technically challenging task because of the paucity of information concerning degradation of materials and components under long-term exposure to the environmental >

service conditions in a nuclear power generating station. As is discussed ,

more fully in Reference 80, with the possible exception of certain simple 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 Ms OWJ Franidin Research Center 4-4 4 cm e n r.a.no m

1 TER-C5417-8 4

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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 l 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 monitor performance and identify degradation) should be performed to determine l the need for maintenance or replacement. In this way, the qualified life l

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

We Licensee should review the qualified life values and the present installed life of the equipment in accordance with the DOR Cuidelines to determine a replacement schedule for each equipment item (or subcomponents thereof) . These schedules may be revised as new information becomes available.

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TER-C5417-8 4.2 NRC Category I EQUIPMENT THAT SATISFIES THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES AND IE BULLETIN 79-01B t

i 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. Por ,'

these equipment items, the Licensee's System Component Evaluation Work Sheets indicate that the requirement 4 of IE Bulletin 79-OlB have been satisfied, -

assuming that the Licensee's analyses of qualification documentation are complete and correct. l 4.2.1 Equipment Item No. 71 Mrminal Lug AMP-Special Products PIDG-KYNAR (Licensee Reference 60) xeview 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.

4.2.2 Equipment Item N3s. 70A and 70B Electriccl panetration Assembly Incated Inside and Outside Containment Westinghouse ecdel Clacs B, C and Class F (Licensee References 63, 72, and 73)

Review of tlie Licensee's System Component E7aluation Work Sheet indicates that the requirements of IE Bulletin 79-018 are satisfied; a test report is referenced that envelops the required environmental service parameters.

, 4.2.3 Equipment Item Nos. 3 and 22

Level Switch tocated 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 tl e requirements of IE Bulletin 7?-OlB are satisfied; a test report is re ferenced that envelops the required environmental service parameters.

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TER-C5417-8 4.2.4 Equipment Item No. 4 Pressute Switch Located Outside Containment Static-O-Ring Models 12N-AA4-X10TT, SN-AA3-X9STT, and GN- AA2' -X9SVTT (Licensee References 20 and 42)

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

. report is referenced that envelope the required environmental service parameters.

4.2.5 equipment Item Nos.14A,14B,14C,14D, 14E, 14F, 14G, 14H, 14I, 14J, 14r and 14L Motor Operator Incated t side Containment Limitorque SMB Models (Licensee References 2, 3, 4 and 57)

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

4.2.6 Equipnent Item No.16 Pressure Switch Locsted Outside Containment Barksdale Models B2T-M12SS, D2T-M18SS, TC-9622-1, PlH41340SS, PlH-M8 5SS-V, D2H-M150SS, and D2T-M150SS (Licensee References 19, 4 3-4 6, 4 8, a nd 5 3)

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.

4.2.7 ?quipment Item No.17

+

Motor Located Outside containment GE Models 5K6 and SK8 (Licensee Rsferences 9,10, and 24)

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

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TER-C5417-8 4.2.8 Equipment Item No. 20A Relay Located Outside Containment GE Models CR2810A14AT, CR2811A217Y51, HrA51A49ti, CR2810A14AC, and CR2810A14AK2 (Licensee Reference 12) ,

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 paraneters.

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 IF Dulletin 79-OlB are satisfied; a test report is referenced that envelops the required environmental service parameters.

4.2.10 Equipment Item No. 30 Limit Switch I4cated Inside Containment NAMCO Model EA740-80100 (Licensee References 13 and 21)

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.

4.2.11 Equipment Item ms. 31A and 31B Limit Switch I4cated 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 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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I i i TER-C5417-8 4.2.12 Equipment Item No. 35 Flow Switch Incated Outside Containment

[ Magnetrol Model F-521

/ (Licensee Reference 51) l l, Review of the Licensee's System Component Evaluation Work Sheet indicaeca that the requirements of IE Bulletin 79-01B are satisfied. De Licensee has l referenced qualification documentation, and the required environmental service parameters were enveloped.

I 4.2.13 Equipment Ites No. 36 l Position Switch I4cated Outside Containment l Cherry Electrical Products Corp. Model E23-60H j (Licensee Reference 52) i b Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are satisfied. De 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 i that the requirements of IE Bulletin 79-01B are not satisfied. @e Licensee i

j has referenced a test report indicating that the required environmental service parameters are enveloped.

l

• 4.2.15 Equipment Item No. 43 Temperature Switch Tocated cutside Containment

, Barksdale Model T2H-M251S-12 (Licensee Reference 58)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B are not satisfied. @e Licensee has referenced a test report indicating that the required environmental service parameters are enveloped.

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b FranWin Research 4 % e n r rwm >. u. C. enter

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.L TER-C5417-8 4.2.16 squipment Item No. 58 Instrument Cables Incated Inside and Outside containment Raychem Corp. ItAel Flantrol IPRil6 and ITRfl6 (Licensee Reference 65)

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.

I 4.2.17 Equipment Item No. 59 Thermocouple Cable Incated outside containment ,

Boston Ins. Wire & Cable Co. Models IPR $16 and SPR$16 i (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.

4.2.18 Equipment Item No. 60 Thermocouple Cable Incated Outside Containment

• Samuel Moore & Co. Models Dekoron ECI,1PR$16, and SPR$16 (Licensee Reference 66)

Review of the Licer.see'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.

4.2.19 Equipment Item No. 61 Power Cable,1000 V, Incated Outside Containment Cerro Wire & Cable Co. Models 4/cf 6, 4/c610, 4/ctl6,1/ctl2, and 7/ctl6 (Licensee References 67 and 68) ,

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.

dil0' nklin Research Center A Dmenen of The Feeneen ineemme m___ _ _ . _ _ _ _ _ _ . _ _ _ _ __ _ .. . _ _ _ . . . . . .

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TER-C5417-8 4.2.20 Equ'pmerit Item No. 62 Po ur Caple (1000-5000 V) recated Outside Containment Okonite Co. Models 4/o AWG, 2/c6 8, 4/c010, 4/c0 6, 3/c250, 7/c250, and 3/c500 (Licensee Reference 68)

Review of the Licensee'r, 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. 21 Equipment : tem No. 63 Control Cable Incated Outside Containment Kerite Co. Models 2/c012 and 4/ct12 (Licensee Reference 69)

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.

4.2.22 Equipment Item No. 64 Control Cable Incated Inside and Outside Containment Raychem Models 98-9-10-12 AWG Flamtrol (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 Incated Outside Containment Rockbestos Co. Models 2/cfl2, 4/cil2,1/cil2, and 1/ct14 (Licensee Reference 70)

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.

innPM ~ 4-11 MU %Franklin w m r, Resear.ch

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• TER-C5417-8 t

4.2.24 Equipment Item No. 66 Cable 'Iwenination Incated 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 79-01B are satisfied; a test report is ,

referenced that envelops the required environmental service parameters. l 4.2.25 Equipment Item No. 6'9 Thermocouple Splice Located Outside Containment ,

AMP, Scotch, Raychem Models 320557, 70, and WCSF-N (Licensee R6ferences 69 and 71)

Review of the Licsnsee'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 Incated Outside Containment Barton Models 288A and 288 (Licensee References 25 and 31)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are satisfiad; a test rep 0rt is referenced that envelops the required environmental service parameters.

4.2.27 Equipment Item No. 56 Instrument Cables Incated Outside Containment Boston Ins. Wire & Cable Co. Models IPR $16, 3PR$16, and ITR$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.

nk!b Research Center A Ohemen af Dhe Frasusp insensee

TER-C5 417 -8 4.2.28 Equipment Item No. 52 .

Terminal Blocks Incated Inside and outside cont.ainment Weidmuller Model 6941 (Licensee Reference 61)

Review of the Licensee's System Component Eveluation 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.

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1 TER-C5417-8 9

4.3 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 requirements. -

Per Brunswick Unit 2, no equipment is assigned to this category. .

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4.4 NRC Category III EQUIPMENT THAT THE LICENSEE BELIEVES TO BE EXDtPT FROM QUALIFICATION This category includes equipment items that the Licensee believes to be exempt from qualification on the basis that (1) the equipment does not 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 accomplish,ed by some other designated equipment that is fully qualifd.ed.

For Brunswick Unit 2, no equipment is assigned to this category.

I 00bV Franklin Research Center a w .r m r.en m

TER-C5417-8 4.5 NRC Category IV EQUIPMENT THAT HAS QU.%IFICATION SCHEDULED BUT NOT COMPLETED 7tiis category tacludes 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 dato.

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

Review of the Licensee's System Component Evduation 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.

Equipment Item No. 27 4.5.2 Level Switch Incated Outside Containment

! Robertshaw Model SL-205-A2-Rll-Bil-1 (Licensee References 22 and 49)

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.

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

J 00h FrankBn Research Center A Osmiemn af The Fransen insumme

O TER-C5417-8 4.6 NRC Category V EQUIPMEfff THAT DOES NOT SATISFY ONE OR MORE OF THE GENERAL REQUIREMENTS OF THE DOR GUIDELINES AND IE BUL4ETIN 79-OlB This catogory includes equipment items judged to be deficient or

. inadequate with respect to the general requirementa of the DOR Guidelines and IE Bulletin 79-013 based 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-BS2, and PTKBC2221CCF9 (Licensee References 5 and 14)

Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-01B 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. @e Licensee has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to temperature, pressure, and radiation.

o 4-17

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s TER-C5417-8 4.6.3. Dquipment Item No. 21 Control Switch Incated Outside Containment Honeywell Microswitch Models PTSHA201 and PTSHA202F-B52 ,

(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. We 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 Switch Located Outside Containment >

Barton Model 289 .

(Licensee References 8, 26, 37 and 38)

Review of the Licensee's Systr/a Component Evaluation Work Sheet indicates l that the requir1ments of IE Bulletin 79-OlB 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.

\

4.6.5 Equipment Item No. 26 Flow Transmitter Incated Outside Containment CE 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.

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4.6.6 Equipment Item No. 67 Power Cable Splice Incated Outside Containment Burndy, Okonite Models T95 and $35 (Licensee reference not cited)

Revaew 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 i service parameters were not enveloped.

, 4.6.7 Equipment Item No. 29 l Temperature Switch Located outside containment l renwall Model 17002-40 *

(Licensee References 23 and 28)

Review of the Licensee's System Compcnent 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 with respect to radiation.

The Licensee has committed to test the item or replace it at the first refueling outage following receipt of material.

4.6.8 Equipment Item No. 32 Limit Switch Located 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, pressure, and radiation.

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

nkli Resea

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TER-C5417-8 4.6.9 Equipment Item No. 37 Position Switch Located Outside Containment Honeywell Micro Switch Model OP-DAR '

(Licensee References 14 and 17) .

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

that the requirements of IE Bulletin 79-01B are Inot satisfied. The Licensee has referenced qualification documentation indicating that the required environmental service parameters were not enveloped with respect to

, temperature and pressure.

4.6.10 Bquipment Item No. 38 4 Level Switch Located Outside Containment Magnetrol Model 5.0-751 (Licensee Reference 54) 1 Review of the Licensee's System Component Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. The Licensee r

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

4.6.11 Equipment Item No. 49 Terminal Lugs Located Inside and Outside Containment

• AMP Special U.lg 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 Located 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.

4-20

_nkun Rese_ arch._ Center

TER-C5417-8 4.6.13 Equipment Item No. 5A H2/02 Analyzer . Incated Outside Containment Nuclear Measurement Corp. , P.x2el Dt Stated (Licensee reference not cited)

Review of the Licensee's Syst.em Component Evaluation Work Sheet indicates that the requirements of IE Bulletin' is-UlB 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. SB 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. We Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

4.s.15 Equipment Item No. 6 I4 vel Pressure Indicator Incated Outside Containment snico Model 35W (Licensee reference not cited)

Review of the Lic',.Mee'; System Component Evaluation Work Sheet indicates that the requirementr of IE Bulletin 79-OlB are not satisfied. The Licensee has not referenced palification documentation, and the required er"'ronmental

. service parameters were not enveloped.

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

, accordance with IE Bulletin 79-01B.

4-21 M'F Franklin Research Center Awasner w.

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i TER-C5417-8 4.6.16 Equipment Item No. 7 Level Transmitter Located Outside Containment Bailey Model BQ15222 1 (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 4.6.17 Equipment Item No. 8 l 9tessure/ Level Switch Location Outside Containment ratton Models 289A, 288, and 288A (T.icensee References 8, 25, 26, 31-34, and 36)  :

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

7 4.6.18 Dquipment Item No. 9 Pressure Transmitter Located Outside Containment Bailey Models KQ123 and KQ12C (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. -

4.6.19 Equipment Item No. 10A Limit Switch Located Outside Containment Honeywell Micro Switch Podel OP-AF (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.

4-22 Mr'4Franklin Resear h Center w .# n. n cn m .

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TER-C5417-8 4.6.20 squipment Item No.10B Limit Switch Incated Insiew 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 79-01B are not satisfied. The Licensee l_, has referenced a test report; hcwever, the required environmental service l parameters were not enveloped.

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

4.6.21 squipment Item No.11 Solenoid valve Incated Outside Containment ASCO Models WPHT8321Al, HT8321A6, HT15211B33, HB8342A4, HB8302C25RV, HT8262C71, 8262D23, HT8316B15, HTX-8320A70, 8302C26D, JV182-084, 8302C26RV, HV180-414, HT832322, HT8316C37, HVA904052A, HT80033, 834485, and HT8344A5 (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.

4.6.22 Equipment Item No. 12 Resistance 7tmperature Detector Located Inside Containment Pyce Model 100-OIM Platinum (Licensee Reference 18)

Licensee heference 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 Located 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.

brankun Research Center A Osmemon of The Fromen insumuse

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N TER-C5417-8 4.6.24 Equipment 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. @e Licensee l has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

4.6.25 Equipment Item Nos. la:N and 140 Motor Operator Incated Outside Containment ,

Limitorque SMB Models (Licensee References 2, 3, 4, and 57) -

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

4 4.6.26 Equipment Item No. 15 ,

Radiation Detector Incated 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 79-01B are not satisfied. The Licensee has referenced qualification documentation; however, the required environ-mental service parameters were not enveloped with respect to pressure, .

humidity, and radiation.

4.6.27 Equiptaent ;*cm No.18A Motor Operator Located InGde 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. ..

NbFrank!!n Research Center A Dewesan of The Franhan ineseuse

TER-C5417-8 4.6.28 Equipment Item No. 68 Heat Shrink Insulation Located Inside and Outside Containment Pennwalt 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. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not envelcped.

4.6.29 Equipment Item No. 20B Relay Incated Outside Containment GE Model CR2811A217Y (Licensee Reference 12)

Review of the Licensee's System Compons.nt Evaluation Work Sheet indicates that the requirements of IE Bulletin 79-OlB are not satisfied. @e Licensee has referenced qualification documentations however, the required environ-mental service parameters wSte 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 Located 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 net referenced qualification documentation, and the required environmental service parameters were not enveloped, d

buuNnklin Research Center A Denman of The Fransen enseswe

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i TER-<5 417-8 i 4.6,32 Equipment Item No. 33 Pressure Ts insmitter Located Oatside Containment GE Model 5f2032HKZ22 .

(Lic.snsee 1 eference 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 i has not referenced qualification documentation, and the required environmental service paramaters were not enveloped with respect to temperature, pressure, ,

huiuidity, and radiation.

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

'- June 1982.

4.6.33 Equipment Item No.-34  !

l Solenoid valve Incated Inside Containment ASCO Model 5450-5 (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 a test report, and the required environmental service

y. .

parameters were not enveloped.

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

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

that the requirements of IE Bulletin 79-01B are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental service parameters were not enveloped.

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4.6.35 33uipment Item No. 40

. Control Switch I4cated outside Containment GE Model CR2940BM204A ,

(Licensee reference not cited) 4 .

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. We Licensee states that a qualifi-

, cation investigation is currently be'ng performed; if the equipment is found

. ur. qualified, it will be replaced.

4 4.6.36 . Equipment Item No. 42 Flow Transmitter I4cated Outside Contairisent Bailey Model BQ13221 (Licensee reference not cited)

Review of the Licensee's System component Evaluation Work Sheet indicates I- that the requirements of IE Bullet'.n 79-OlB are not satisfied. The Licensee has not referenced qualification documentation, and the required environmental f service p*;:ameters were not enveloped.

I j 4.6.37 Equipment Item No. 44

i. Time Relay Incated Outside Containment I

Agastat Model 7022AC

(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 i , has not referenced qualification documentation, and the required environmental 4 service parameters were not enveloped.

4

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

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, Ubbl Franklin Research Center

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TER-C5417-8 '

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 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 states that the equipment will be replaced by June 1982.

4.6.39 Equipment Item No. 46 Temperature Switch I4cated 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 I

service parameters were not enveloped. ,

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

4.6.40 Equipment Item No. 47 Position Switch Located outside Containment Johnson Services Model D-251-595 ,

(ricensee reference not cited)

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

k service parameters were not enveloped. '

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~l TER-C5417-8 4.6.41 Squipment Item No. 48 Motor Incated Outside Containment Reliance Models 25cT, 23-1/4, and 17-1/2-1750 (Licensee Reference 59)

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 and test duration.

4.6.42 Equipment Item No. 50 Terminal Lug Located Inside and Outside Containment T&B Models Sta-Kon-Lug No. C10-10, Ring 'fongue tes. c971 and 54108 (Licensee reference not cited)

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

4.6.43 Equipment Item No. 51 Terminal Blocks Incated Insida 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-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 watartight thermosetting foam or replaced with splices.

4~29

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

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I TER-C5417-8 4.6.44 - Equipment Item No. 53 Terminal Blocks Incated Inside and Outside Containment GE Models CR151D30 . ' EB-5 ,

(Licensee reference -ited) i Aaview 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 dccumentation, and the required environmental l

[ ' service parameters were not enveloped. .

I l

The Licensee states that the terminal' blocks wi?.1 be covered with a macoM.seting watertight thermosetting foam or reolaced with splices, j 4.6.45 Equipment Ites No. 54  ?

Connector Incated Inside and Outside Containment Amphenol Mode 1 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.

l 4.6.46 Equipment Item No. 55 Connector Incated Outside Containcent '

Pyle-National Model NS2

! (Licensee reference not cited)

{

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

that the requirements of IE Bulletin 79-au 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.

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1. u uth Franklin Research Center A Dhemen W The Fransen enessues -

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TER-C5417-8 4.6.47 Equipment Item No. 57 Instrument cables Incated Inside containment Boston Ins. Wire & Cable Co. Model ITR$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 satisfied. @e Licensee has referenced a test report indicating that the required environmental service parameters were not enveloped with respect to pressure, temperature, and test duration.

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4-31 Ubd Frankhn Research Center

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I TER-C5417-8 4.7 NRC Category VI EQUIPMEfff FOR WHICH QUALIFICATION IS DEFERRED This 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.

For Brunswick Unit 2, no equipment is assigned to tais category. .

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.TER-C5417-8 i 4.8

SUMMARY

OF THE EVALUATION The following tabulations represent a summary of the results of the i , equipment environmental qualification evaluation conducted by PRC in accordance with the methodology presented in Section 3.

. 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. We following designations are used:

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

O = Assignment to an NRC qualification category.

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

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

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TER-C5417-8 Table 4-1 NIMBER OF EQUIPMENT ITDIS IN EACH QUALIFICATION CATEGORY NRC Number of Category Category Definition Equipment Items ,

I Equipment That satisfies ' 42 the General Requirements  !

of the DOR Guidelines and  ;

IE Bulletin 79-01B'

.J J

k

II Equipment itiat the 0 Licensee Will Modify ,

3.

• or Relocate i ,

III Equipment That the 0 ,

Licensee Believes j to Be Exempt From Qualification IV Equipment That Has 2 ,

Qualification testing Scheduled But tot  ;  ;

Completed V Equipment That Does Not 48 .

Satisfy one or More of the General Requirements

• of the DOR Guidelines and IE Bulletin 79-OlB VI Equipment for Which Qualification is Deferred J s

92 .

i i Ob nklin Research Center 4 % orn.Fr=mn m

h TER-C5417-8 1,

l 1

r Table 4-2 l .

4 PRCTAsst y PLANT NAMg PAGE i

U00; rr.naan n ,en c.n , too4.s .vii or ie, c.1, 2 i

• b D N=Y PROJECT UTIUTY 3 SQUIPMENT ENVIRONMENTAL MN Carolina Power & Light DoCMET NRCTAC OATE/ ENGINEER i

lEsas.01s 50-325 42485 gg l

SUMMARY

REVIEW EQUIPMENTffEM NUMVA ' # I./

j e l 2 l 3 l 4 lsalsel s l 7 l e l 9 poapool se litl13 pea lsespecl leo [

GulOEUNE REQUIREMENTS (des 4 NATIONS: X- DEPICIENCY,L-UMmMGCoNomoN)

EvioENct or oVAuricATioN X X X X X X X X X X X X X f

RELATIoNsNIP To Test sP8CMEN AGING OGGRADAT1oM EVALUATED i QUAUPIED UPE EsTA9UsNED PROGRAM ToIDENTIFY AGING

[ QUAL Pon STEAM EXPosumE i PEAK TEMPERATURE A0GGua rt X X X X l PEAx PRESSURE ACIoVATE X X X X X i TEstDURAtioN ADSQUATE X REQUIRED PP. ALE ENVELOPED '

i oust rom susMERGLnct i Qu'AL PoM CNEMICAL SPRAY X ouAL poR RAOIATloN X

SETA RADIATloN CoNslOERED j Test suoOENCE

TEstoURAvio n ,ouR . ,u cTio ,

i i I

ouauricaTion CATEGORY o-CATEGORY ots4NA noN l* i-scEws sArisPY GuetuMEs O O O O O O a -ouAt PENoeNG uocericaTioN l m -ExEMPTPRoM ou AL

j. rv -ouAL Test scNEDutto

y -acEws oo NoT sansPY GutOEUNEs O O O 01O O O O O O O' O O l vi -Review ts oEFERRED i REPLACEMENT sCNEDULED lM M M l 1

1 I

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I 4-35

. b ' AFranklin Research Center Chiman of the Fearann aneende

-1

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

i TER-C5417-8 s

Table 4-2 (Cont. )

PRC TA38( PtANT NAME PAGE Nuu~ Franklin Research C' enter 4 24.s ava nrunavick vatt 2 2 DOMW PROJECT UT1UTY EOUIPMENT ENVIRONMENTAL M12 Carolina Power & !.tsht  ;

OUAUPICAT10N DOCKET NRC TAC DATElENGINEER IENE 50-325 42485 gh/g

SUMMARY

Review # #

EQUDPMENT fTEM NUMSER [/

let h4F l14Gll%43l14d ll%i4Lllessl#4alla404 IS l 16 (17 l lea lisSl19 @(

GUtoEUNE REOUIREMENTS (DESIGNATIONS: X- DEFICIENCY.L-UMmMG CON 0 MON)

} EvloENCE OP OUAuriCATION X X X X X X X X RELATIONSHIP TO TEST SPECIMEN

, AGING DEGRADAT1ON EVALUATED OU AUPIED UFE ESTASUSNED PROGRAM 7010CNTIFY AGING QUAL POR STEAM EXPOSURE j PEAM TEMPERATURE ADEOUATE X X X 3 PEAK PRESSURE ADEOUATE lX X ,

TESTDURATION ADEQUATE REQUNtED PROP 1LE ENVELOPED QUAL POR SUSMERGENCE QU'AL FOR CHEMICAL SPRAY QUAL POR RADIATION X X X f SETA RADIAT10N CONSIDERED j TEST SEQUENCE _

TESTDURATION(1 HOUR 4 P'JNCTIONI OUAUPICATION CATEGORY O-CATEGORY DESIGNATION i -SCEwS SATISPY GuiofuMES O O O O O O O O O O O .

II-OUAL PINDING MOOlFICAT10N lil -EXEMPT FROM QUAL N -OUAL TEST SCHEDULED 0 ,

y -SCEwS 00 NOT SATISFY GUIDEUNES O O O O O O IOl VI -REVIEW IS DEFERRED l REPLACEMENT SCHEDULED l M i

i i

l b nklin Research Center A Dmoon of The Franen boosute

TER-C5417-8 i

i Table ' 4-2 (Cont. )

i a

e N PLANT NAMg [ PM PRCTAsk

• 8 n m vick unie 2 3

! b Frankun Reneerth Center UTIUTY I

~

$.DDETN PROJECT 03G C&e1701 Carolina Power & Light gggepugny guyimOkigNTAL OU DOCxET NRCTAC DATE/ ENGINEER 85545018 50-325 42kSS J//o[ff V l

SUMMARY

REVIEW EQulPMENTITEMNuMSER '

acclatItal:3l ts l as l 2712e l 2s l 3o hWas l 3a l 33 l 34 l st l u l 3T l 3s l GulDEUNE REOulREMENTs (DEssGNATIONS: X- DEPICIENCY.L-UMfTING CON 0fTION) 1 X X X X X X X X XI X X: X EvioENCE OP OuAUPICATION l

RELATiONaNIP TO TEST SPECIMEN 1

$ AGING DEGRADATION EVALUATED M*L=ito uPE EstAem l

j rmmRAM TOloENTIPY ACM i QUAL POR STEAM OPCsuRE X X X X X X __

! PEAxTEMmfuRE ArnauATE X X X X X X X i PEAx PRESSURE.:.oEOuATE

~ X X TEsTDuRATION ADEOuATE j I

' RaQueREc PROPiLE ENVELOPEO QUAL PoR susMERGENCE Sl*L POR C;;rf'_AlsPRAY X X X X X X X Qu AL POR RACIATION

{

OETA RA08ATION CON 4G,m r l

j T_Est sEOutNC'i

TEST DURATION (1 >.3uR + PuMCTION)

O-CATEGORY DEstGNATION

, . QuAUPICATION CATEGORY O O O O O O O  !

i-sCEws sATisPY GuioEuMEs j u -Ou At PENoiNO MOOeFiCATiON

. m -EXEMPT PROM QUAL O

!^ iv -QUAL TEST sCNEoutEo O O O O O O I v -sCEws 00 NOT SAT 1 SPY GutOEUNES O O O O O .

vi REviEwis oEPERREo i REPt.ACEMENT sCNECuLED M M M Mi l l e

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TER-C5417-8 l

l f Table 4-2 (Cont. ) ,

i U0 F m R M C' m t ACTAS8C Aoo4.s W avn

• PLANT h1E arun ,1ck Unie 2 P E L"2:'fL".1"EI'M" PROJECT UTiuTy EQUIPMENT ENVIRONMENTAL 03tM 381741 Carolina Poiter & Light '

OUAWM DOCMET NRCTAC DATE/ENG4NEER me.mois so.32s ' 6sas c',//o/ R B A -

SUMMARY

REvew touiPMENTrTEM NuMeER '

V se l 4c l 4s l 4al 4s l44 l 4el 4e l 47l 4e l 4el So l ss l stl 33l s4l sel se l s7 l GusoEuME REoutREMENTS (DESIGNATM: X- DEFICIENCY,L-UMmMG CONOmON)

EvioENCE OP ouAuriCATiON X X X X X X X X X X X X X RELATioNSNep m TEST SPEOMEN i AG#eG DEGRADATION EVALU ATED

! "^U8tED UPE ESTAOUSHED .

PROGRAMTOIDENT AG#eG OUAL POR STEAM EXPOSURE PEAM TEMPERATURE ACEQUATE X

PEAM PRESSURE ADEQUATE X X Test DuRATics AotouATE X X REouiREo PMoPiLE ENVELOPED QUAL POR SUSMERGENCE Qu'AL POR CHEMeCAL SPRAY

} QUAL. POR RADIATION SETA RA0 EAT 10N CONS 80ERED TEST SEQUENCE TEST DURATION O HOUR + PUNCT10N) ll QU AUPICATION CATEGORY O-CATEGORY DESaGNATION i- SCEws sATiSPY GuiosuNES O G O O -

II --QU AL PENDING MOO 8PICATION lil -EXEMPT PROM QUAL N -QUAL TEST SCHEDULED .

v -SCEwS OO NOT SATISPY GulOEUNES O O O O O O O O O O O O O O O Vi -REVIEW IS DEFERMED RE.vCEMENT SCHEDULED M R R R *i 4-38 0000 Franklin Research Center A Dhenson of The Frenede insatuse a

- n -.%, ,r,, - . , - ,- - - - - - m- - - , - ,w,w-- - - - - , , v - -- w- , - , - - . - , r --v ,vw- , --

4

! TER-C5 417-8 Table 4-2 (cont. )

N PLANT NAMg PAGE P9tCTASK 4

• *8 rres ' srunm,tek enie 2 5

J Frarikhn Regeerch Center awit i 0 it. M ,1 D .C" T 1"!!lf' PeEcf utuTT 00G041M Carolina Power & Light

.! EcueMENT ENVmONMENTAl.

DOCKET NRCTAC OATE/ ENGINEER lES 76418 50-325 2 85 6 ///f1,-b--

V

' suMMAm REv.Ew EcurMENT rrEM NuMeER

s. I n l ol m q u i n l.4.. l ..!.r l u j u lro.posl ri la. l l l l I GuioEuNE REoumEMENTs toEslGNATiONs: x- oEPiCiENCv.L-uMmNG CONomON>

l l X X EVIDENCE OP oVAUPlcAT10N

~

RELATiONSeseP TO TEST sPEOMEN AGING DEGRADATION EVALU ATED i

^U.^U81E0 uPE ESTA8utpH8.D 1 PROGRAM TO IDENT:PY ^CM_

l QUAL POR STEAM EXPOSURE PEAM C. 27URE AWuATE f

3 PEAK PRESSURE ADEC:- ATE I TESTDuRAT10N ADEcuATE

! REcuiREo PROPtLE ENvELOPlo i

! ca1*L PoR susMERGENCE 4

ou'At PoR CNEMiCAL sPRAv l QUAL POR RADIATION .

j SETA RADIATION CO****n8stED TEST sEcutNCE i TEST DURATION (1 Hour + PUNCT10N)

O-CATEGORv DESIGNATION

)

• ouAuPiCAT10N CATEGORY O O O O O O'O O O O O O O O s -sCEws sATisPv GusOEuMEs II-QUAL PENDING MOOePICATION I m --EXEMPT PRO'J ouAL

• IV -Cu AL Tost SCHEOuLED V -SCIWS LC NOT SATISPY GulOduMES I

Q Q Vt -REVIEW IS DEPER* ED

. REPLACEMENT SCHEDULED

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TER-C5417-8

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 tr.: Lf eensee, complemen' ;4 in several cases by other relevant technical info rmation. The major def teiencies that have been identified are shown in the Equipment Environmental Qualification Summary Ecems (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 Guidelines require the Licensee to have ongoing programs to l review surveillance and maintenance records in order to assare that safaty-related equipment that exhibits age-related degradation be identified a nd , if necessary, teplaced. No evidence of such programs was included in the Licensee's submittal.

The present evaluation of the status of environmental qualification of the safety-related electrical equipment installed in Brunswick Unit 2 involves 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.

e nklin Research Center

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TER-C5417-8

6. REFERENCES

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

2. Qualification Type Test Report Limitorques B003/6.7.76

3. Test of Limitorque valve operator 8600198/F-C2232-01/ll.68

4. Qualification Test of Limitorque valve F-C3117/12.71

. 5. Micro Switch LTR - 24407

6. FSAR Appendix M Section M7.9 Sept.1972, DRRil2, 3/29/72

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 lil-A-05

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

12. Material Analysis for GE H-338-2

13. Namco Limit Switch'Index

14. File Reference No. 6335 of MJc1. ear Rad. and Switch Application l 15. Evaluation of Asbestos Free Plastics FR 14171/2.21.79

16. Humidity Test of General Purpose Pheno'lic M. FR 12774/7.15.'5

17. Quality Assurance Test FR 13048/2.3.76

18. Material Analysis for Pylo RTOs H-?33-7

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

20. Material Analysis for Static 'O' Ring H-33-12

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

22. BWR Qualification Summary for R.L.S. 2SR-ll6-A-02

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

24. Engiaeering Evaluation of Motors 10/25/80 s

25. ITT Barton Eng. Report No. Rl-288S-11 and Qualification Test Procedure

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

27. BWI! Qualification Summary for GE Rad Set QSR-015-A-01

28. Viking Laboratory GE Summary NSE79001, #30411

29. Ogden Technical Laboratory GE Summary USE 79002, #70822

30. Ogden Technical Laboratory GE Summary NSE 79003, #70822

31. GE Summary NSE 79004 Addendum to TP-199-4; 5/24/71 6-1 aw.m.ne m.r nklin Research Cente

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TER-C5417-8

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

33. GE Susunary NSE 79006 Mdendum to TP-199-4 5/24/71 ,

34. GE Summary NSE 79007 Mdendum to TP-199-4; 5/24/71 1

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

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

j 37. GE Summary NSE 79010 Mdendum to TP-199-4; 5/24/71

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

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

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

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

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

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

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

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

46. GE Sununtry NSE 80030 596-0498 8/13/75 +

47. GE Sununary MSE 80031 596-0398 8/13/ 75

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

49. GE Sununary NSE 80033 12625 6/5/62

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-3'

53. Approved Eng. Test Laboratories GE Sununary NSE 80028

54. BWR Equipment Qualification Sununary for Magnetrol, QSR030-A-01 .

55. Farr Co. Environmental Qualification Test Report Class IE Corp. 10/14/80 ,

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

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

58. Material Analysis for Barksdale temperature Switch H-338-4

! 59. P*liance & Co. Summary Report NUC-9, 7/1/78 ,

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

61. Qualification Test Program for Mrmination Block F-C5205-03, 10/79

62. Radiation Testing 94800R16-24 by Westinghouse 12/1/71

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

64. General Data Sheet of Boston Ins. Wire & Cable Co. 98714, 1/14/72

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

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TER-C5417-8

66. FIRL-Final Report, Qualification Test #F-C36b

67. FIRL-Final Report, Qualification Test #F-C2857

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

69. LOCA Qualification of Kerite 600 Volt HTK

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

71. Raychem Eng. Test Report WCSF-N

72. Design Approval Test in Westinghouse, FP3811, 8/72

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

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

Subject:

Electrical Equipment Environmental Qualification, including DOR Guideliner.

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

Keppler, K. V. Seyfritz, R. H. Engelken, NRC, September 29, 1980.

Subject:

IE Class Supplement No. 2 Bulletin 79-OlB, Environmental Qualification of Class lE Equipment.

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

Keppler, K. V. Set ;- Atz, R. H. Engelken, NRC, October 24, 1980.

Subject:

IE Suppa< ment No. 3 Bulletin 79-01B, Environmental Qualification of Class IE Equipment.

77. U.S. NRC Memorandum and Order (CLI-80-21) pursuant to the Petition for Emergency *.nd 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 Qualificatc:n of Class lE Equipment, for Brunswick Steam Electric Plants 1 and 2.

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

, 80. S. P. Carfagno and R. J. Gibson, "A Review of Equipment Aging Theory and Teci.nology," Electric Power Research Institute Report NP-1558, September 1980. .

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l TER-C5417-8 l

APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS The Licensee has provided information [78) concerning environmental zones and postulated design basis accident coeditions. 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 .cnes are shown in Tables A-1 through A-3.

Brunswick Units 1 and 2 have a domineralized water spray system rather I

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 i considered to be a credible accident environment due to the high volume, low bydraulic resistance flow paths from the drywell to the torus which immediately direct LOCA blowdown flow away from the drywell. HELB does not af fact environmental conditions inside containment and therefore is not considered for in-containment primary components.

Post-LOCA radiation levels in various regions of the reactor building are due to leakages from the drywell and Cue to fluids that are recirculated from i

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 drywell are assumed to be leaking into any one compartment adjacent to drywell. The leakage outflow from (2at 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 features compartments.

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I Table A-1 ACCIDENT PRESSURE PROFILE TABLE t

HELB Analysis

• l Per Reactor Building LOCA ,

Environmental Report i Area P

Report Peak Peak Profile Area Description Compt. P essure Pressure Table ,

No. (PSIG) (PSIG)

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

P Reactor Bldg

• i 20'-0" & Above 6 IV 1.0 0.2 i LL HPCI Room 1 17 2.7 0.2 I '

NN Core Spray Rooms 6 IV 1.0 O.2

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PP RWCU Area 6.9 1 VIII 0.2 Main Steam Tunnel 6 IV 1.0 0.2 t

RR RCIC/HPCI Tunnel 5 IV 3.2 0.2 FIGURE SUPPLIED '

. BY THE LICENSEE A-10 nklin Research Center

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d TER-C5417-8 Table A-2 LOCATION OF SUBSTANTIAL FISSION PRODUCT INVENTORY l

.6 APPROXIMATE PEAK SOURCE LOCATION INVENTORY. Ci Reactor Building (Uniform Dispersal) Total: 8.1 x 106 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 Iodine: 1.5 x 108 Pressure Suppression Chamber Iodiae: 3.0 x 108 Typical Small Compartment (Adjacent to drywell in Reactor Building) Total: 105 Typical Large Compartmenc

. (Adjacent to drywell in Reactor Building) Total: 106 l

FIGURE SUPPLIED BY THE LICENSEE A-11 l

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<= Table A-3 IN Page 1 of 2 E@ BEPECTED DOSES FOR BADIATION :'ENsITIVE ESF onnroutstrs la IL 5' Normel ff Operating Hestmum Accident Dose Dose f'ig R  % reehold (Rede) (Rede) 5Qr Component 1.ocatip3 (Rede) 40 Yeare F1 ret Hour M pays C e nte Limitorque Inside 5 x 10 7 6 x 107 --- 4 x 10I D reehold dose applies to tubri-S Velve Operatc.ro DryweD (Heatmum) cation seale, made of Vitoa.

n eee seale een be periodically replaced to keep the normel oper-eting dose subetontially below the threshold. %e listed normal operating dose is the mentmum dry-well dose, t.e., et the outside surface of the sacrificist ehteld at come mid-plane. 1,eshage from the emelo does not imply fatture of the operators to function.

3*

8 solenoid Reactor 6 x 107 2 x 103 1 x 10 5 9 x 100 Accident dose beoed on conserve-U velves Building tive eneumption of nor.-uniform Below 20' E1. mfming of fisotoa products la Reactor Building. Dose given te mesimum for any compartment adja-cent to the drywell. Normd operettag does based on 5 mr/hr for 40-years.

Pressure Reactor 2 x 10 8 2 x 10 3 1 x 105 9 x 10 0 Same cosement se for colanoid Switches / Butiding valves.

Transmittere Below 20' E1.

Pump Hotores R11R Room e 1.ube CS Room 1 x 108 2 x 103 1 x 105 9 x 100 e Insulation 5 x 10 7 2 x 103 1 x 105 9 x 100 e Seele 5 x 10 6 2 x 103 1 x 105 9 x 100 Fetture of seele leads to leakage, g uhich does not reader pump in- tg operable, ue W

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Table A-3 (Cont. )

{1}

q rege 2 of 2 D '

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]Mar

}/ -

Operating Dose Hextaus Accident Dose d5 threshold (Bade) (Rade)

Component

{:0 1.ocation nede) 40 Years First flour 30 Dave Corsente 3Y gs Electrontcet Reactor 33# e Semiconductors Building 1 x 108 2 x 103 1 x 105 9 x 108 F e capacitors selow 20' E1. 3 x 108 2 x 103 1 x 105 , ,go6 lh

• y e Inductors 2 x 109 2 x 103 1 a33 9 x 106 e Insulatore 5 x 107 2 a 103 1*'33 9 x 108 (organic)

Solenoid Reactor Bldg.

Valvte Above 20' E1. 6 x 107 2 x 103 1 103 1 x 103 Pressure peactor Bldg.

Suttcheaf Above 20' E1.

Transmittere 2.1 x 108 2 a 103 1 x 103 1 x 105 Fuey Ntors: Reactor 31ds.

>8 e I.ube Above 20' fl. 1 x 108 2 x 103 1 x 103 1 x 105 e Insulation 5 x 107 2 x 103 1 x 103 1 x 163 C e Seats 5 x 108 2 x 103 1 x 103 1 x 105 Elect ronica: Beactor Eldg.

e Semiconductore Above 20' E1. 1 x 108 2 x 103 1 x 103 1 x 105 e capacitora 3 x 108 2 x 103 1 x 103 1 x 105 e Inductore 2 x 109 2 x 103 1 x 103 1 x 105 e Insulatore 5 x 107 2 x 103 1 x 103 1 x 105 (Organic)

RFFERENCES:

(1) "the Effects of helaar Radiation on Electronte Componente, Includtag Seatccaductors," REIC Report No. 36.

Battelle Memortal Institute, Columbus, Ohio, October 1,1964.

(2) " space Meteriale Handbook," Second Edition, Document No. IE.-IDE-64-40, AF Heteriale 1.aboratory, Wright-Patterson Air Force Base, Ohio (Frepared by tacKeed Mtselles and Space Company, Sunnyvale, Celtf.),

January 1965.

A tg

=

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FIGURE SUPPUED a BY THE LICENSEE ,

4 t _

TER-C5417-8 APPENDIX B - LISTING OF SAFETY-RELATED ELECTRICAL EQUIPMENT This appendix lists groupings of safety-related electrical equipment for

. Brunswick Steam Electric Plant Unit 2. Muipment item numbers in the list are used in the Equipment Environmental Qualification Summary forms and in the equipment qualification discussions in Section 4.

This list was generated from the Licensee's System Component Evaluation Work Sheets (SCEWS) in Reference 78. For each item, the list identifies the manufacturer and model number, plant location, SCEWS number, applicable qualification references, and TER section where the item is discussed.

FRC paginated the original Carolina Power and Light Ccmpany Environmental i

Qualification of Electrical Equipment Report as follows:

Page Nos.

Volume 1,Section V, Subsection 1 1-7 Volume 1,Section 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

! Volume 2,Section V, Subsection 7 186-212 volume 2,Section V, subsection 8 213-293

. Volume - 2,Section V, Subsection 9 294-311 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,Section V, Subsection 13 385-401 volume 2,Section V, subsection 14 402-431 These page numbers will be used throughout this Technical Evaluation Report.

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i TER-C5417-8 PLANT NAME: BRUNSWICK UNIT 2 EQUIPMENT TER +

ITEM ITEM QUALIFICA'/ ION SECTION PO. DESCRIPTION LOCATION SCEWS NO. REFERENCES NO.

1 Selector Switch Outside 1-3,92,94,164, 5,14 4.6.1 Honeywell Micro Conttinment 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-B5 2 2 Solenoid valve Inside 130,131,135,137, None 4.6.12 ASCO Containment 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 Containment 287,289,290,32o, 12N-AA4-X10TT 327 SN-AA3-X9STT l 6N-AA21-X9SVTT i

SA H2/02 Analyzer Outside 8 None 4.6.13 Nuclear Measure- Cortainment ment Corp.

Model mt Stated

. 5B Radiation Analyzer Outside 9,10 None 4.6.14 Nuclear Measure- Containment a meist Corp.

Model Not Stated 6 IAvel/ Pressure Ou tside 11,14,15,353 None 4.6.15 Indicator Containment anico 35W

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TER-C5417-8 l

EQUIPMENT TER IT!!M ITEM QUALIFICATION SECTION I

NO. DESCRIPTION LOCATION SCBfS NO. REFERENCES NO.

~, / I4 vel Transmitter Ou tsi<!e 12 None 4.6.16 Bailey Containment BQ15222 8 Pressure Switch Ou tside 13,55,57,115-117, 38,32,34 4.6.17 Barton Containment 152-154,155 288A 269A 288 4

9 Pressure Trans- Outside 16,17 None 4.6.18 mitter Containment Bailey KQ123 KQ12C 10A Limit Switch Outside 18,38,41,48,50, 14,17 4.6.19 Honeywell Micro Containment 159 a switch OP-AR 108 Limit Switch Inside 157 ?4,17 4.6.20 Honeywell Micro Containment Switch OP-AR i

) 11 . Solen 11d valve Outside 19,20,23-29 None 4.6.21

ASCO Containment 31,33,35,39, WPiff8321A1 40,42,43,45, HT8321A6 47,49,51,143, HT8211B33 145,147,149, HB8342A4 160,181,182,

, HB8302C25RV 281,303-311, HT8262C71 320-323,325, 8262D23 340,344,373-384

[, HT8316815 HTX-8320A70 j 8302C16D-

JV18 2-084 8302C26RV l HV180-414 l HT832322 I

4 Nd316C37 HVA904052A HN 0033,-8344B5

HTC344A5

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)

i TER-C5417-8 9

4 EQUIPMENT TER ITM ITm QUALIFICATION SECTION  ;

NO. DESCRIPTION LOCATION SCDiS NO. REFERENCES NO. ,

12 3esistance Inside 21,22 18 4.6.22 Temperature Containment l ,

8 Detector Pyco 100-OHM Platinum ', .

! 13 Limit Switch Ou tside 30,32,34,44,46 14,15,16 4.6.23 Bettis Containment ,

RX-3 41  !

l RX-41 i 14A Motor Operator Outside 36,63,64, 2,3,4,57 4.2.5 j Limitorque Containment 69,70,71,72 ,

i 2B

! 14B Motor Opetator Outside 37,65,66,272, 2,3,4,57 4.2.5 Limitorque Containment 282,283,291,341, l SMB 342,345-350,352, l- 359,360,362,363, 366,367,368,369 ,

l j 14C Motor Operator Outside 67,68,280 2,3,4,57 4.2.5 ,

t Limitorque Containment i SMB 140 Motor Operator Outside 103 2,3,4,57 4.2.5 ,

Limitorque Containment . ,

l SMB 14E Motor Operator Outside 106,111,112 2,3,4,57 4.2.5 Containment Limitorque SMB ,

14F Motor Operator Outside 108,109,110, 2,3,4,57 4.2.5 Limitorque Containment 200 SMB e 14G Motor Operator Outside 133,198 2,3,4,57 4.2.5 Limitorque Containment SMB 1 411 Motor Operator Outside 184 2,3,4,57 4.2.5 Limitorque Containment SMB

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haqiu Franklin Research Center B-4 4 Chimon of The Fransen 6nesause

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TER-C5417-8 EQUIPMENT TER ITEM ITEM QUALIFICATION SECTION NO. DESCRIPTION LCCATION SCENS NO. REFERENCES NO.

. 14I Motor Operator Ou tside 197 2,3,4,51 4.2.5 j Limitorque containment SMB 14J Motor Operator Outside 270 2,3,4,57 4.2.5 l Limitorque Containment 2B l

'14 K Motor Operator Outside 274 2,3,4,51 4.2.5 Limitorque Containment SMB l 14L Motor Operator Outside 337,338 2,3,4,57 4.2.5 Limitorque Containment l SMB 14M Motor Operator outside 105,107,113, None 4.6.24 Limitorque Containment 176,179,199 SMB I 14N Motor Operator Outside 180 2,3,4,57 4.6.25 l Limitorque Containment SMB 140 Motor Operator outside 201,265-269, 2,3,4,57 4.6.25 j Limitorque Containment 271,273,275, l SMB 276-372 l

l 15 Radiation Outside 52 27 4.6.26 De tector Containment GE e 194X927G 16 Pressure Switch Outside 54,56,119-122, 19,43-46, 4.2.6 Barksdale Containment 161,162,204-207, 48,53

, B2T-M12SS 217,227,228,288, l D2T-M18SS 291,301,302,318,

! PlH-M340SS 319 l

TC-9622-1 i P1H-M8 5SS-V D2H-M150SS D2T-M150SS

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s TER-C5417-8 EQUIPMENT TER ITIM ITEM QUALIFICATION SECTION NO. DESCRIPTION LOCATION SCDiS NO. REFERENCES NO.

17 Motor Ou tside 59,60,263,264, 9,10,24 4.2.7 GE Containment 355-358 ,

SK6 SK8 18A Motor Operator Inside 219-226 2,3 4.6.27 Limitorque Containment SMB 18B Motor Operator Inside 73,74,104, 2,3 4.6.2 Limitorque Containment 132,177,178, ,

SMB 183,196,284 19 Motor Control Outside 78-90 Nole 4.5.1 Ce nter 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 4

HFA51A49H '

CR2010A14AC CR2810A14AK2 20B Relay Outside 91 12 4.6.29 ,

GE Containment CR2811A217Y Outside 20C Relay 329-332 None 4.6.30 GE Containment CR120A08002AA .

21 Control Switch Ou tside 93,165,169,171, 5,14 4.6.3 Honeywell Micro containment 173,190,193,195, ,

Switch 231,233,236,239, PTSHA201 242,245,247,249, PTSHA202F-B 5 2 251,253,255,257, 259,261 22 Level Transmitter Outside 95 11,40 4.2.3 Yarway Containmemt 4418EC

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\s TER-C5 417-8 l

t EQUIPMENT TER ITEM ITEM QUALIFICATION SECTION

[

I NO. DESCRIPTION IDCATION SC1!NS NO. REFERENCES -NO.

i l 23 Flow Switch outside 61,62,101,285 8,26,37,38 4.6.4 I8 Barton containment 289

. 24 Level Switch Ou tside 96,97,186, 25,31 4.2.26

! Barton Containment 202,203,218, 288A 314 288

( 25 Motor Ou tside 100 Noae 4.6.31 l Tuthill Containment CD259AT 26 Flow Transmitter Outside 102 50 4.6.5 GE Containment 50-555111BDAA3 PDH i 27 Level Switch Outside 114 22,49 4.5.2 l Robertshaw Containment SL-205-A2-Rll-Bil-1 28 Thermocouple Outside 123,128,129,185, 1,29, 4.2.9 Pyco containment 208-210 30 N145C3224-P1 29 Temperature Outside 124,125,127,156, 23,28 4.6.7 Switch Containment 211,212 Fwnwal l 17002-40 l

l 30 Limit Switch Inside 134,136,138,140, 13,21 4.2.10 l

8 NAMCO containment 312 l EA740-80100

. 31 Limit Switch Outside 142,144,146,148, 13,21,56 4.2.11 l NAMCO Contpinment 313,339,343 At EA740-80100 B D2400X-R 32 Limit Switch Inside 157 14,17 4.6.8 Honeywell Micro Containment Switch OP-AR b Franidin Research Center 4 c>= a as Tu rr ma =

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l TER-C5417-8 TER EQUIPMENT ITEM QUALIFICA.ON SECTION l IT!!M REFERENCES NO.

i NO. DESCRIPTION LOCATION SCDiS NQ 33 Pressure Trans- Outside 286,293 50 4.6.32 mitt (r Containment ,

GE 552032HK222 l

• 34 . Solenoid valve Inside 4 None 4.6.33 l

I ASCO Containmert 5450-5 35 Flow Switch Ou tside 294 51 4.2.12 Magne trol Containment F-521 36 Position Switch Outside 295,297 52 4.2.13 Gerry Electrical containment Products Corp.

E23-60H 37 Position Switch Outside 296,298,299 14,17 4.6.9

! Honeywell Micro Containment Switch OP-DAR 38 Level Switch Outside 324 54 4.6.10 Magne trol Containment 5.0-751 39 fuse Panel ou tside 328 ,ene 4.6.34 GE Containment Model F t Stated ,

40 Control Switch Outside 333,334 None 4.6.35 l

GE Containment ,

CR2940BM204A

- 41 Motor Control Outside 335 55 4.2.14 ,

Farr Co. Containment D51423 42 Flow Transmitter Outside 354 None 4.6.36 l

Bailey Containment l BQ13221 i

43 Temperature Ou tside 364 58 4.2.15 Switch containment Barksdale T2H-M251SI-2

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TER-C5417-8 EQUIPMENT TER (TDI ITEM QUALIFICATION SECTION

_NO2 DESCRIPTION LOCATION SCDiS NO. REFERENCES NO.

44 Time Relay Outside 386 None 4.6.37 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 47 Position Switch Outside 396,397 None 4.6.40 Johnson Services Containment D-251-595 48 Motor Outside 398-401 59 4.6.41 Reliance Containment 256T 23-1/4 17-1/2-1750 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 i Lug C10-10 Ring Tongue G971, 5 4108

. 9 51 Terminal Block Inside/ 410 tione 4.6.43 Curtis Outside

• type L Containment 52 Terminal Block Inside/ 431 61 4.2.28 Weidmuller Outside 6941 Containment

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6 TER-C5417-8 EQUIPME:iT TER ITD4 ITEM QUALIFICATION SECTION NO. DESCRIPTION I4 CATION SCENS NO. REFERENCES NO.

53 Nrminal Block Inside/ 411-413 None 4.6.44 GE Outside '

CR151D30 Containment EB-5 54 Connector Inside/ 405 62,63 4.6.45 ,

Amphenoi Outside 48-03R18-31P&S Containment 55 Connector Ou tside 420 None 4.6.46 ,

Pyle-National Containa.ent NS2 56 Instrumen' Cable Outside 406 64 4.2.27 Boston Ins. Wire Containment I

& Cable Co.

1PRil6 3PRfl6 ITR$16 57 Instrument Cable Inside 407 64 4.6.47 Boston Ins. Wire Containment ,

& Cable Co.

ITR$16 ,

58 Instrument Cable In-ide/ 422 65 4.2.16 Raychem Corp. Outside '

Flamtrol Containment 1PR$16 ,

1TR$16 4

59 Thermocouple Ou tside 408 64 4.2.17 Cable containment

• Boston Ias. Wire

& Cable Co.

IPR $16 8

SPR$16 60 Thermocouple Outside 425 66 4.2.18 Cable Containment Samuel Moore &

Co.

Dekoron ECI 1PR$16 SPR$16

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! ITEM ITEM QUALIFICATION SECTION NO. DESCRIPTION LOCrf(ON SCENS NO. REFERENCES NO.

61 Power Cable Outside 409 67 4.2.19

'd 1000 V Oontainment Cerro Wire &

Cable Co.

• 4/cf 6, 4/c610, 1/c812, 4/ct16, 7/c616 l

62 Power Cable Outside 415,416 58 4.2.20 1000-5000 V Containment Okonite Co.

4/o AWG, 2/c68, 4/c010,4/cf 6, 3/c250, 7/c250, l 3/c500 t

l 63 control Cable Outside 414 69 4.2.21 Kerite Co. Containment 2/cel2 4/c812 64 control Cable Inside/ 421 65 4.2.22 Raychem Outside l 68-9-10-12 Containment i AWG Flamtrol 65 Control Cable Outside 424 70 4.2.23 i Rockbestos Co. Containment 2/cil2, l 4/c812, 1/c812, 1/ cpl 4 66 Cable Termination Outside 417 68 4.2.24 Burndy, Okonite Containment 5000 V 67 Wuer Cable Outside 418 None 4.6.6 Splice Containment Burndy, Okonite T95

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bd ranklin Research Center A Ema==a os N rmmaa m

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TER-C5417-8 ,

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EQUIPMENT QUALIFICATION SECTION ITEM ITEM SCI *AS NO. REFERENCES NO.

NO. DESCRIPTION LOCATION .

Inside/ 419 None 4.6.28 68 Heat Shrink Insulation Outside .

Pennwalt Corp. Containment l' b Model Not Stated Thermocouple Outside 423 69,71 4.2.25 .

69- l!

Splice containment AMP, Scotch, '

Raychem ,

320557, l 870, WCSF-N 70A Electrical Inside/ 429 63,72,73 4.2.2 ]

i Penetration Outside As sembly Containment t

Westinghouse Class B,C ,

Inside/ 430 4.2.2 70B Electrical ,

Penetration Outside Assembly Containment Westinghouse Class F 71 'Iteminal Lug Inside/ 402 60 4.2.1 AMP Special Outside Products Containment PIDG-Kynar

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TER-C5417-8 l

l APPENDIX C - SAFETY SYSTEMS FOR WHICH ENVIRONMENTAL

. QUALIFICATION IS N BE ADDRESSED The Licensee has submitted the following list of safety-related systems that must function in order to mitigate the consequences of a design basis accident. This informatior was included in the Licensee's October 31, 1980 response (78] to IE Bulletin 79-OlB.

o Automatic DePressurization System (ADS) - B21 4 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 Shu.off System (NSSS) - A71' o Reactor Core Isolation Cooling System (RCIC) - E51 o Residual Heat Removal System (RHR) - Ell o Reactor Instrument Penetration System (RIP) o Reactor Protection System (RPS) - C72 o Standby Ga Treatment System (SBGT) o Service Water System (SW) o Ventilating Air System (VA)

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