ML20004E291

Equipment Environ Qualification,Brunswick Unit 2, Final Draft Technical Evaluation Rept

ML20004E291
Person / Time
Site:	Brunswick
Issue date:	01/31/1981
From:	Crane C FRANKLIN INSTITUTE
To:
References
IEB-79-01B, IEB-79-1B, TER-C5417-008, TER-C5417-8, NUDOCS 8106110504
Download: ML20004E291 (100)

Text

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O TECHNICAL EVALUATION REPORT FIN AL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION i

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42485 FRC Pc0 JECT C5417 NRC TAC NO.

EG&G IDAHO,INC. SUBCONTRACT NO. K 7615 FRC TASK 3

Prepared by Franklin Research Center The Parkway at Twentieth Street l

Philadelphia, PA 19103 FRC Group Leader: C. J. Crane Prepared for EG &G Idaho, Inc.

Idaho Falls, Idaho 33401 January 31,1981 l

This recert was prepared as an accouit o' work per'ctmed under a subcontract from EG&G idaho. Inc., a crime contractor to the United States Cecartment of Energy. Neither EG&G nor the United States Government nor any agency thereof. cr any of their empicyees.

makes any warranty. expressed or implied. or assumes any legal liacility cr rescensicility for any third carty's use. or the results of such use. or any information accaratus. pecauct or process disclosed in this report, or represents that its use by such third party acula not infringe privately owned rights.

NOTE-THIS IS A DRAFT 8ecauss of schedule limitations. tnis report draft has not gone througn tne comclete I

review cycle of FRC. While the overall conclusion is expected to remain the same. the reader is cautioned that some details of the recort may change as the review is ccmcleted.

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TECHNICAL EVALU ATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION CMCLIfM F0hER #0 LIC4, T C0F#1Y EFLtSWICK STEN 1 EECTRIC PUWT LilIT 2 1

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42485 FRC PROJECT C5417 NRC TAC NO.

EG&G 10AHO, INC. SU BCCNTRACT NO. K-7615 FRC TASK S

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 January 31,1981 This report was prepared as an acccunt of work performed under a succontract from EGiG Idaho, Inc., a prime contractor to the United States Cepar* ment of Energy. Neither EG&G nor the United States Government nor any agency therect. or any of their empicyees.

makes any warranty. expressed or implied, or assumes any legal liacility or,

nonsibilit/

for any third party's use, or the results of such use. or any intermation apparaa.:

ccuct or process disclosed in this report, or represents that its use oy such *hird party wouic not infnnge privately owned rights.

NOTE -THIS IS A DRAFT l

Because of schedule limitations. this repor+ draft has net gone through the complete review cycle of FRC. While the overall conclusion is expected to remain the same, the readeris cautioned that some details of the report may change as the review is completed.

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TER-CS417-8 CCNTENTS Section Title Page 1

INTRODUCTICN.

1-1 l.1 Purpose of the Review.

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

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

NRC CRITERIA FCR ENVIRCNMENTAL QUALIFICATION.

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

2-1 l

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

2-1 2.2.2 Submergence.

2-2 2.2.3 Equipment Located in Areas Normally Maintained j

at Room Conditions.

2-2 2.2.4 Simulated Service Conditie s and Test Duration.

2-3 2.2.5 Deferment of Qualification Review 2-3 f

2.2.6 Test Sequence 2-4 2.2.7 Radiation 2-4 l

3 METHODCLCGY USED BY FRC.

3-1 4

TECHNICAL EVALCATICN.

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

4.1.1 Environmental Conditions 4-1 4.1.2 Aging.

4-1 4.1.3 Identification of Electrical Components 4-2 4.2 Equipment Qualified for Plant Life.

4-3 4.2.1 NRC Category I.a Equipment That Fully Satisfies All Applicable Requirements of the DCR Guidelines.

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TER-C5417-8 CONTENTS Section Title Page 4.2.2 NRC Category I.b Equipment for Whica Deviations From the DCR Guide-lines Are Judged Acceptable.

4-3 4.3 Equipment Qualified With Restrictions.

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4.3.1 NRC Category II.a Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines and Has a Service Life Less Than Plant Life.

4-4 4.3.2 NRC Category II.b Equipment That Fully Satisfies All Applicable s

Requirements of the DOR Guidelines Provided That Specific Modifications Are Made.

4-4 4.3.3 NRC Category II.c

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Equipment for Which Deviations From the DCR Guidelines Are Judged Acceptable 4-4 4.4 NRC Category III Equipment That Is Exempt From Qualification 4-6 4.5 Equipment for Which Documentation Contains Deviations Frca the Guidelines That Are Judged Unresolved.

4-7 4.5.1 NRC Category IV.a Equipment Which Has Qualification Testi.%

Scheduled but Not Completed.

4-7 4.5.2 NRC Category IV.b a

Equipment for Which a Qualification Documentation in Accordance With the Guidelines Has Not Been Established.

4-7 4.6 NRC Category V i

Equipment Which Is Unqualified.

4-22 4.7 NRC Category VI Equipment for Which Qualification is Deferred.

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CONCLUSICNS.

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REFERENCES.

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APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS t.

APPENDIX B - EQUIPMENT ITEM TABLE APPENDIX C - SAFETY SYSTEMS AND EQUIPMENT FOR WHICH ENVIRONMENTAL QUALIFICATION IS % BE ADDRESSED APPENDIX D - EQUIPMENT ITEM CROSS-REFERENCE LIST r=

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

" Environmental Qualification of Class 12 Equipment" in January 1980. This Bulletin required the Licensee to perform a detailed evaluation of the environmental qualification of Class lE electrical equipment required to function under postulated accident conditions and to submit a report on this action.

The objectives of the NBC Equipment Environmental Qualification Review program are to evaluate nuclear power plant safety-related electrical equipment in accordance *aith critaria established by the NRC and to identify (1) equipment whose qualification documentation is adequate, i.e.,

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

To meet the overall program goals, the objective of this Technical Evaluation Report is to review the Licensee's submittala to determine if the

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Licensee reviewed its safety-related electrical equipment for environmental qualification in accordance with the DOR Guidelines and NUREG-0588 as required by IE Bulletin 79-013. The NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. If Jiscrepancies are found, the audit will be extended.

GENERIC ISSUE' BACKGROUND 1.2 Safety-related electrical equipment must be capable of performing design safety functions under all normal, abnce:nal, and accident conditions. Of particular concern is the assurance that equipment will remain operable during 6

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TER-C5417-8 and following exposure to the harsh environmental cond' 'ons (i.e.,

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

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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 plants have been modified over the years, and industry standards concerning qualification have been revised as une design of reactor systems has changed and as regulatory and operating experience has accumulated. Examples of such j

standards are IEEE Standards 279-71, 323-74, 383-74, 317-76, 334-74, 382-72, and 381-77. NaC NUREG documents 0413 and 0588 have been developed to address l

this topic. In particular, NUREG-0588 (published for comment in December 1979) formally presented the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment in the a

resolution of General Technical Activity A-24, " Qualification of Class 12 f

Safety Related Equipment." The positions documented therein are applicable to 1

plants that are or will be in the construction permit or operating license j

review process.

l Although qualification standards and regulatory requirements have undergone considerable development, all of the currently operating nuclear l

power plants are required to comply with 10CFR50, Appendix A, General Design Criteria for Nuclear Power Plants,Section I, Criteria 4.

This criterion states in part that " structures, systems and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, :naintenance, l

testing, and postulated accidents, ine',uding loss-of-coolant accidents."

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In addition, qualification requirements are also embcdied in 10CFR50

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Appendix A, General Design Criteria 1, 2, and 23 and Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, L

l Criteria III and XI.

These rguirements are applicable to safety-related equipment located inside as all as outside of containment.

The NRC staff has evaluated the Licensee's equipment qualification program by reviewing the qualification documentation of selected u,

s.2fety-related equipment as part of the operating license review for each r-plant. The NRC staff has also used a variety of methods to assure that these

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general requirements are met for electrical safety-related equipment. In the oldest plants, qualification was based on the fact that electrical components were of high industrial quality. Af ter 1971, qualification was judged on the basis of IEEE 323-71; however, no regulatory guide was issued adopting the L.

IEEE 323-71 standard. For plants whose Safety Evaluation Reports were issued after July 1,1974, the Commission issued Regulatory Guide 1.89 which in most

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respects adopted the most recent standard, IEEE 323-74.

In 1977, the NRC staff instituted the Systematic Evaluation Program (SFP) to determine the degree to which the older operating nuclear plants deviated from current licensing criteria. The subject of electrical equipment environ-mental qualification (SEP Tcpic III-12) was selected for accelerated evalua-O tion as part of this program. Seismic qualification of equipment was to be r'

addrassed as a separate SEP topic. In December 1977, the NRC issued a generic letter to all SEP plant Licensees requesting that they initiate reviews to l

determine the adequacy of existing equipment qualification documentation.

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Preliminary NBC review of Licensee responses led to the preparation of u

NUREG-0458, an interim NBC assessment of the environmental qualification of electrical equipment. This document concluded that "no significant safety I

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deffuiencies requiring imeediate remedial actions were identified." However,

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it was recommended that additional effort should be devoted to examining the l

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

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On May 31, 1978, the NRC Office of Inspection and Enforcement issued IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants," which required all Licensees of operating plants (except those included in the SEP program) to examine their installed safety-related electrical 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-ment issued IE Bulletin 79-01, which was intended to raise the status of IE Circular 78-08 to the level of Bulletin, i.e., action requiring a Licensee response. This Bulletin required a complete re-review of the environmental qualification of safety-related electrical equipment as described in IE Circular 78-08.

The review of the Licensee responses indicated certain deficiencies within the 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 j

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

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

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

On January 14, 1980, the NRC Office of Inspection and Enforcement issued the DOR Guidelines and IE Bulletin 79-01B, which expanded the scope of IE Bulletin 79-01 and requested additional information on environmental qualification of safety-related electrical equipment at operating facilities, excluding the 11 facilities undergoing the SEP review. This Bulletin stated that the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification are the DCR Guidelines. The scope of the review was expanded to include high energy line breaks (inside and outside containment) in addition to equipment aging and submergence. The NRC advised the Licensees that the criteria contained in the DOR Guidelines would be used in its review of Licensee submittals; problems arising from this review would be resolved using NUREG-0588 as a guide.

In early February 1980, the NRC decided that Indian Point Units 2 and 3 t

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

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on February 21, 1980, the NRC and representatives of the SEP Plant Owners Group held an open meeting at NBC headquarters to discuss an accelerated review program in accordance with the DOR screening guidelines. Represen-tatives of the Indian Point Units and Zion Station also attended this meeting. The NRC formally issued to all Licensees represented at the meeting the DOR Guidelines document [741* which included a second document,

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

together with the request that the Licensees review their plant systems and provide additional equipment environmental qualification information to the

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NRC on an accelerated schedule.

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task force including a principal reviewer in each region and a task leader from headquarters. The regional members are responsible for the technical

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l TER-C5417-8 review of the Licensees' responses to IE Bulletin 79-OlB, and the task leader is responsible for the overall coordination of the review effort with NRC to

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assure overall consistency. The regional reviewers held meetings with the Licensees in their respective regions which resulted in staff positions being issued in a supplement to IE Bulletin 79-013 dated February 29, 1980.

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

On May 27, 1980, the NRC issued Memorandum and Order CLI-80-21, [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 10CFR50, Appendix A, General Design Criteria,Section I, Criterion 4.

This order also established that the Safety Evaluation Reports on this subject, to be prepared by the NRC staff, must be issued on February 1,1981 and that all subsequent actions to be taken by Licensees to achieve full compliance with the DOR Guidelines or NUREG-0588 must be completed no later than June 30, 1982.

In October 1980, EG&G awarded Franklin Research Center (FRC) a contract to provide assistance in the equipment environmental qualification review for 13 of the plants whose Licensees responded to IE Bulletin 79-013. - FRC was given the assignment to evaluate the Licensee's equipment environmental qualification submittal and to present the results in the form of a Technical

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Evaluation Report for each plant.

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1.3 SPECIFIC ISSUE BACKGROUND The staff held regional meetings with the Licensees and interested parties during the week of July 13, 1980 in various locations. The staf f 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 Order of May 27,198 0 (CLI-80-21). The above Orders 6

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TER-C5417-8 required the Licensees to complete the tasks identified in IE Bulletin 79-OlB no later than November 1, 1980 to allow the staff to comply wi 3 the February i

1, 1981 date imposed by the Commission Order. The responses to the questions were issued on February 29, 1980; and the second and third supplements to IE Bulletin 79-01B, highlighting the staff positions affecting the Licensees' responses, were issued September 29 and October 24, 1980, respectively.

1.4 SCOPE OF THE REVIEW Environmental qualification of safety-related electrical equipment was selected by the NRC for accelerated review. Therefore, the scope of this report is limited to equipment that must function to mitigate the consequences of a loss-of-coolant accident (LOCA) or high energy line break (HELB) and whose environment is adversely affected by that event. In addition, IE Bulletin 79-01B requires enviromental qualification for all safety-related electrical equipment exposed to a harsh environment in accordance with the DOR Guidelines or NUREG-0588. Harsh environments include the limiting conditions

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resulting from (i) the entire spectrum of postulated line breaks resulting from a loss-of-coolant accident (LOCA) or a high energy line break (HELB) inside and outside of containment and (ii) radiation from fluids which are recirculated from inside containment to accomplish long-term cooling subsequent to an accident. Qualification aspects not included within the secpe of this evaluation are:

e seismic qualification e equipment protection against natural phenomena equipment operational service conditions (e.g., vibration, voltage, e

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

r e equipment protection against fire hazards e equipment protection against missiles.

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NRC CRITERIA POR ENVIRONMENTAL QUALIFICATION 2.1 CRITERIA PROVIDED BY THE NRC The DOR screening guidelines used by FRC to evaluate the electrical equipment environmental qualification program were:

e " Guidelines for Evaluating Environmental Qualification of Class lE Electrical Ikguipment in Operating Reactors" (74]

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

e NUREG-0588, " Interim Staff Position on Environmental Oualification of Safety-Related Electrical Equipment." (79]

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

2.2 STAFF POSITIONS AND SUPPLEMENTAL CRITERIA L

Ihe NRC identified the following staff positions and supplemental criteria to be used in conjunction with the referenced DOR screening guidelines.

2.2.1 SERVICE CONDITIONS INSIDE CONTAINMENT ICR A IDSS-OF-COOLANT ACCIDENT (DOR GUIDELINES SECTION 4.1) o For Pressurized Water Reactors (PWRs), the DOR Guidelines state that the e

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

In the specific case of pressure-suppression type containments, the following mini:kum high temperature conditions may be used:

(1) Boiling Water Reactor (BWR)

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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 79-01B, [751 "these values are a screening device, per the Guidelines, and can be used in 5

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

Service conditions should bound those expected for coolant and steam line breaks inside containment with due consideration given to analytical uncertaintie s.

Ihe steam line break condition should include superheated conditions, with peak temperature and subsequent temperature / pressure profile as a function of time.

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

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

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

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

[75] provides the following 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 af ter submergence, the equipment can be considered exempt from the submergence l

portion of the qualification requirements.

l 2.2.3 EQUIPMENT LOCATED IN AREAS NORMALLY MAINrAINED AT ROCM CONDITIONS l

(DOR GUIDELINES SECTION 4.3.3) l Supplement 2 of IE Bulletin 79-013 (75] permits deferment of the review of environmental qualification for all safety-related equipment items located l

in plant areas where the equipment is not exposed to the direct effects of a 1

EELB 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 By June 30, 1982, all safety-related electrical equipment potentially exposed to a harsh environment in nuclear generating stations licensed to I

operate on or before June 30, 1982 shall be qualified to either the DOR 1

Guidelines or NUREG-0588 (as applicable). Safety-related electrical equipment l

i is that required to bring the plant to a cold shutdown condition and to

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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 nct 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 30,198 2.

2.2.4 SIMULATED SERVICE CONDITIONS AND TEST CURATICN (DOR GUIDELINES SECTION 5.2.1) l

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

Supplement 2 to IE Bulletin 79-013 [75] provides the following additional criterion:

" Equipment designed to perform its safety-related function within i

I 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 1

indicated that time is the most significant factor in terms of the margins required to provide an acceptable confidence level that a safety-related function will be completed. The 1-hour qualification requirement is based on the acceptance of a type test for a single unit and the spectrum of accidents t

(small and large breaks) bounded by the single test."

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2.2.5 DEFERMENT OF QUALIFICATION REVIEW Supplement 3 to IE Bulletin 79-01B (76] permits the submittal of qualification documentation regarding the TMI Action Plan equipment and the a

equipment required to achieve and maintain a cold shutdown condition to be delayed as follows:

e Qualification information for installed TMI Action Plan equipment must

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be submitted by F4bruary 1, 1981.

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TER-C5417-8 Qualification information for future TMI Action Plan equipment e

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

Qualification information for TMI Action Plan equipment currently e

under NRC review should be submitted as soon as possible.

Qualification information for TMI Action Plan equipment not yet e

installed that does not require pre-implementation review shcold be submitted to NRC for review by the irplementation date.

I Qualification information for equipment required to achieve and e

maintain a cold shutdown condition should not be submitted later than February 1, 1981.

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2.2.6 TEST SEQUENCE (DOR GUIDELINES SECTION 5.2.3)

-s Supplement 2 to IE Bulletin 79-013 (75] provides the following additional criteria:

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

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

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

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Test programs in progress should be evaluated regarding the ability

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to comply by incorporating aging in the proper sequence. These programa would then fall in the first or second category."

2.2.7 RADIATION (DCR GUIDELINES SECTIONS 4.1.2, 4.2.2, and 4.3.2, SUBITEM 2) j Supplement 2 to IE Bulletin 79-01B (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 LOCA events inside containment (100% noble gases /50% iodine /11 partic-ulates). Tnese methods consider the radiation source term resulting from an event which completely depressurires the primary system and releases the source term inventory to the containment, d<$21s j

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TER-C5 417-8 NUREG-0578 provides the radiation source term to be used for determining the qualification doses for equipment in close proximity to recirculating fluid systems inside and outside containment as a result of LOCA. This method considers a LOCA event in which the primary system may not depressurize and the source term inventory remains in the coolant.

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

~

qualifying equipment following non-LOCA events both inside and outside containment (10% noble gases /l0t iodine /04 particulates).

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

LOCA Non-LOCA 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)

~

of NUREG-0578 (100/50/1 in RCS)

Gamma equivalents may be used when consideration of the contributions of beta exposure nas been included in accordance with the guidance given in the COR Guidalines and NUREG-0588. Cobalt-60 is one acceptable ganna radiation source for environmental qualification of safety-related equipment. Cesium-137 may also be used."

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3.

METHCDOLOGY USED BY FRC IE Bulletin 79-01B required the Licensee to:

provide a master list which identifies the systems and electrical e

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

evaluate the qualification documentation using the DOR Guidelines and e

i.

NUREG-0588 l

r-e submit a Licensee Event Report (LER) for electrical equipment l

determined not to be environmentally qualified.

1 The requi aments of IE Bulletin 79-015 were requested under provisions of 10CFR50.5 4 ( f), " Conditions of Licenses," which requires the Licensee to submit written statements, signed under oath or affirmation, to enable the Commission f

to determine whether or not a license should be modified, suspended, or a

revoked.

t To provide assurance that the Licensee implemented the requirements of IE

~'

Bulletin 79-01B and to provide a basis for the NRC Safety Evaluation Report (SER), FBC developed this Technical Evaluation Report (TER) by:

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e assessing the Licensee's responses in relation to the general p

requirements of the DOR Guidelines as augmented by the supplements to l

the 79-01B Bulletin e using NUREG-0588 to resolve open issues.

l The results and conclusions contained in this report are valid assuming that the Licensee's analyses of test reports referenced in the Licensee submittal are correct. Review of test reports was not within the scope of i

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FRC's assignment. However, the NRC staff will audit selected analyses and 6

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TER-C5417-8 test reports, incorporating the results of the reviews with the conclusions of the TERS, when developing the plant-specific SERs.

The Licensee, Carolina Power and Light Co., identified an extensive list of saf- ~related electrical equipment items in various locations of the 7

Brunswies Steam Electric Plant Unit 2 in its submittals to the NRC.

FRC analyzed the Licensee's listing and grouped together all identical equipment items located within plant areas that are exposed to the same environmental service conditions. This analysis resulted in a reduced listing containing 1

(71) different equipment items that formed the basis for the review. Appendix

[>

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

Using the listing of safety-related electrical equipmen*, items,* each i

equipment item was reviewed by FRC in relation tot vi e NRC DOR Guidelines, as modified by NRC staff interpretations e Licensee definition of harsh service environments (Appendix A) e analysis and/or justification of qualification e Licensee-proposed remedies for qualification deficiencies.

Topics not witnin the scope ~ of FRC evaluation are:

o completeness of the Licensee's listing of safety-related equipment e acceptability of Licensee-provided environmental service conditions e acceptability of Licenseo-stated position concerning safety system or component function

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e review and acceptability of, qualification test reports and other l

qualification documentation.

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• In this report, the term " safety-related electrical equipment" refers to 7

the equipment defined by the two NRC Guidelines referenced in Section 2.1.

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TER-C5 417-8 Upon completion of the final review for each equipment item, FRC j

developed an overall evaluation of the component and a specific conclusion with respect to its qualification. Based on the FRC conclusion, each i

equipment item was assigned to one of the generic qualification categories provided by the NRC.

NRC categories are described below.

All equipment item numbers discussed in Section 4 of this report are associated with Reference 78.

The NRC Office of Inspection and Enforcement conducted an on-site verification inspection of selected 1E equipment to verify proper installation of equipment, overall interface integrity, location with respect to flood level for equipmenc inside the containment, and manufacturer's nameplate data. The manufawturer and model number from the nameplate data were compared to information given in the System Component Evaluation Work Sheets (SCEWS) of I

the Licensee's report. The details of this site inpection are documented in C

the IE Inspection Report Number 50-325/80-21 and will be addressed by the NRC.

I i.

NRC QUALIFICATION CATEGORIES AND DEFINITIONS I

I l

e NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES i

This category includes equipment items which are fully acceptable on the l

basis that all applicable criteria defined in the DOR Guidelines are satisfied l

and that the equipment has been found to be qualified for the life of the plant.

i e NRC Category I.b I

I MUIP*ENT FOR WHICH DEVIATIONS FRCM THE DCR GUIDELINES ARE JUDGED l

ACCEPTABLE

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l This category includes equipment items which do not satisfy one or more 3

of the applicable criteria defined in the DOR Guidelines; however, sufficient

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information has been presented to determine that the specific deviations are

[I acceptable.

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,A TER-C5417-8 e NRC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLT.NT LIFE s

This category includes equipment items that are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life..

e NRC Category II,b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES PROVIDED THAT SPECIFIC MODIFICATIONS ARE MADE This category includes equipment items which will be fully acceptable and u

will satisfy all applicable criteria defined in the DOR Guidelines provided

~

that specific modifications are made on or before the designated date. When the modifications are complete, the equipment can be considered qualified.

e NRc Category II.c EQUIPMENT FOR WHICH DEVIATIONS FRCH THE DOR GUIDELINES ARE JUDGED ACCEPTABLE This category includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelines; however, either sufficient bases have been presented to allow a determination that the specific deviations are judged to be acceptable for less than plant life or 1

the specific deviations are judged by FRC to be acceptable for less than plant life based on review of the applicable qualification documentation associated 4

with the general equipment environmental qualification program.

.s e NRC Category III EQUIPMENT THAT IS EXEMPT FRCM QUALIFICATICN l

This category includes equipment items which are exempt from qualification on the basis that (i) the equipment does not provide a safety function (i.e., should not have been included in the equipment list submitted by the Licensee), (ii) the specific safety-related function of the ecmponent can be accomplished by some other designated component which is fully qualified, or (iii) the equipment is not subject to a potentially adverse 0

environment as a result of accidents for which proper operation of the equipment is required. In addition, any failure of the exempt component must j

not degrade the ability of a qualified component to perform its required safety-related function.

q e NRC Category IV.a i

EQUIPMENT WHICH HAS QUALIFICATION TEi,5 TING SCHEDULED DUT NOT COMPLETED The qualification of equipment items in this category has been judged y

deficient or inadequate based upon review of the documentation provided by the Licensee. However, the Licensee has stated that the equipment item is 6

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t scheduled to be tested by a designated date. The results of the testing will dictate the specific qualification category of the equipment item. Specific I

justification for interim plant operation prior to testing should be provided l,

for each item.

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l e NRC Category IV.b EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION IN ACCORDANCE WITH THE GUIDELINES HAS NOT BEEN ESTABLISHED f~

The qualification of equipment items in this category is deficient or inconclusive based upon review of the documentation provided by the Licensee.

This equipment is judged to have a high likelihood of operability l-'

for the specified environmental service conditions; however, complete and iuditable records reflecting comprehensive qualification documentation have not been made available for review. Specific justification for interim plant operation should be provided for each item.

7 e NRC Category V EQUIPMENT WHICH IS UNQUALIFIED Tne DOR Guidelines require that complete and auditable records reflecting a comprehensive qualification methodology and program be referenced and made

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available for review of all Class lE equipment.

l.

The qualification of equipment items in this category has been judged to be deficient or inadequate, based upon review of the documentation provided by l'

the. Licensee. The extent to which the equipment items fail to satisfy the criteria of the DOR Guidelines can be categorized as follows:

(i) documen-tation reflecting qualification as specified in the DOR Guidelines has not been made available for review, (ii) qualification documentation made i

available for review is inadequate, or (iii) the documentation indicates that the equipment item has not passed the required tests.

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e NRC Category VI 31 EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED This category includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittals; however, the l

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

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

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TER-C5417-8 4.

TECHNICAL EVALUATION 4.1 METHODCIDGY USED BY THE LICENSEE The final response to IE Bulletin 79-OlB from the Licensee dated Octcber 31, 1980 contained a general introductory section which described the Licensee's basic approach to qualification and evaluation methodology. A review by FRC has generated the following observations and concerns.

4.1.1 ENVIRCNMENTAL CONDITIONS The Licensee excludes equipment located in the non-harsh environment from qualification considerations. The Licensee, hoaever, does not ; ovide criteria for determining harsh and non-harsh environment. It appears that an l

area where the maximum integrated radiation dose is less than 1 x 10$ rads is considered non-harsh because only the equipment which is subjected to a larger total radiation dose is included in the Equipment Evaluation Work Sheets. If this is true, the Licensee's approach is less conservative than is

~

permitted by the Guidelines. For certain electronic equips nt, such as process parameter transmitters, to performance degradation may occur at 5

threshold levels lower than 1 x 10 rads.

4.1.2 AGING In response to aging qualification, the Licensee states:

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, is not sufficient to justify the expense. In addition, no FSAR commitments were made in the aging area as no equipment was specified to IEEE-323 (1974).

However, any equipment known or found to include materials that are known to be susceptible to ther:nal or radiation aging will be qualified or replaced with qualified equipment.

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TER-C5417-8 Testing is perfor: sed periodically in accordance with Technical Specification Requirements; this testing provides assurance that the

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equipment will perfor:a its intended safety function.

The Licensee has not provided information for identifying the plans or a schedule for conducting an aging review program.

4.1.3 IDENTIFICATION OF ELECTRICAL CDMPONENTS h

With regard to the identification of electrical components for review, the Licensee states the following:

All Class 1E electrical equipment located in the Control Building, Diesel Building, Augmented Of f-Gas Building, Service 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 statement.

In general, steam lines are present in the Turbine

~

Building. Consequently, equipment in the building may be subjected to post-IIELB environments. Equipment in the Service Water Building may also be subjected to submergence.

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

Page Nos.

Volume 1,Section V, Subsection 1 1-7 2

8-52 3

53-77

=

4 78-90 5

91-129 6

130-185 volume 2, 7

186-212 8

213-293 9

294-311

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10 312-328 1

11 329-354

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12 355-384 13 385-401 14 402-431 These page numbers will be used throughout this Technical Evaluation Report.

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4.2

%UIPMENT QUALIFIED FOR PLANT LIFE

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This section includes equipment items which are fully acceptable on the basis that (i) all criteria defined in Section 2 of the report are satisfied or (ii) sufficient data exist to determine acceptability by judgment. For t

Brunswick Unit 2, ne equipment items fall into this category.

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4.2.1 NRC Category I.a QUIPMENT THAT FULLY SATISFIES AIL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES This section normally includes equipment items which are fully acceptable 4

on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and the equipment has been found to be qualified for the life of the plant. For Brunswick Unit 2, no equipment items fall into this category.

4.2.2 NRC Category I.b QUIPMENT FOR WHICH DEVIATIONS FROM THE DOR GUIDELINES ARE JUDGED ACCEPTABLE

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This section normally includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelinest however,

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sufficient information has been presented to determine that the specific

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deviations are acceptable. For Brunswick Unit 2, no equipment items fall into this category.

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TER-CS417-8 4.3 EQUIPMENT QUALIFIED WITH RESTRICTIONS This section includes equipment items fully acceptable on the basis that (i) all criteria defined in Section 2 of this report are satisfied, (ii) the

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equipment is qualified for a time interval less than plant life, or (iii) the equipraent requires specific modification which, when completed, will establish full qualification.

4.3.1 NRC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR

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GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE

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The equipment items in this category are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life. For Brunswick Unit 2, no equipment items fall in this category.

1 4.3.2 NBC Category II.b QUIPMENT THAT FULLY SATISFIES ML APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES PROVIDED THAT SPMl!IC MODIFICATIONS ARE MADE I

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The equipment items in this category will be fully acceptable and will satisfy all applicable criteria defined in the DOR Guidelines provided that specific modifications are made on or before the designated date. When the modifications are ccepleted, the equipment can be considered qualified. For q

Brunswick Unit 2, nt *:ruipment items fall into this category.

4.3.3 NRC Category II.c EQUIPMEN! FOR WHICH DE7IATIONS PROM THE DOR GUIDELINES ARE JUDGED ACCEPTABLE i

Ihis section includea equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelines; however, either sufficient bases have been presented to allow a determination that the specific deviations are judged to be acceptable for less than plant life, or the specific deviations are judged by FRC to be acceptable for less than plant life based on review of other applicable qualification documentation

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associated with the general equipment environmental qualification program.

For Brunswick Unit 2, no equipment items fall into this category.

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TER-C5417-8 4.4 NRC Category III EQUIPMENT THAT IS EXEMPT FRCM QUALIFICATION The equipment items in this category are exempt from qualification on the

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basis that (i) the equipment does not provide a safety function (i.e., should not have been included in the equipment list submitted by the Licensee), (ii) the specific safety-telated function of the component can be accomplished by some other designated component which is fully qualified, or (iii) the equipment is not subjected to a potentially adverse environment as a result of accidents for which proper operat.an of the equipment is required In addition, any failure of the exempt component must not degrade the ability of

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a qualified component to perform its required safety-related function. For

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Brunswick Unit 2, there are no equipment items that fall into this category.

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TER-C5417-8 4.5 EQUIPMENT FOR WHICH DOCUMENTATICN CONTAINS DEVIATICNS FRCM THE GUIDELINES THAT ARE JUDGED UNRESCLVED This section includes equipment items which are deficient on the basis that all criteria defined in the DOR Guidelines are not satisfied. However, the equipment item is either scheduled to be tested or is judged to have a high likelihood of operability.

4.5.1 NRC Category IV.a y

EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLETED r-L The qualification of the equipment items in this category has been judged 2eficient or inadequate based upon FRC's review of the documentation provided i

by the Licensee. However, the Licensee has stated that the equipment item is scheduled to be tested by a designated date. The results of the testing will dictate the specific qualification category of the equipment item. Specific u.

justification for interim plant operation prior to testing should be provided for each ites. For Brunswick Unit 2, there are no equipment items that fall i

into this category.

i 4.5.2 NRC Category IV.b i-EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION IN ACCORDANCE WITH THE GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of the following equipment items is deficts: t. or c.

inconclusive based upc.: FRC's review of the documentation provided by the Licensee. This equipment is judged to have a high likelihood of cperability for the specified environmental service conditions; however, complete and auditable records reflecting comprehensive qualification documentation has not been made available for review. Specific justification for interim plant operation should be provided for each item.

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TER-C5417-8 4.5.2.1 Equipment Item No. 2 Solenoid Valve Located Inside Containment ASCO Models HB-8302C25RV and HT-X-8320A70 (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-6 and VII-A.*

4.5.2.2 Equipmet. Item No. 3 Level Swtech Located outside Containment Yarvay Model 4418C (Licensee References 11, 39, 41, 42, and 44)

Licensee References 11, 39, 41, 42, and 44 are not qualification test reports; therefore, qualification documentation is deficient for this item.

Regarding aging, see the Licensee's statements and ccmmitments in Section VII-A.

4.5.2.3 Equipment Item No. 4 Pressure Switch Located Cutside Containment i

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

Licensee References 20 and 42 are not qualification test reports; therefore, qualification documentation is deficient for this item.

Regarding aging, see the Licensee's statements and commitments in Section VII-A.

4.5.2.4 Equipment Item No. 5 H2/02 Analyser Located Cutside Containment Nuclear Measurement Corp., Model Not Stated (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-31 and VII-A.

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• Section numbers refer to Reference 78.

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TER-C5417-8 4.5.2.5 Equipment Item No. 6 Level Pressure Indicator Located Outside Containment Emico Mocal 35W (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-32 and VII-A.

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l 4.5.2.6 Equipment Item No. 7 Level Transmitter Located Outside Containment o

Bailey Model SQ15222 r'

(Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-33 and VII-A.

4.5.2.7 Equipment Item No. 8 Pressure / Level Switch Located Cutside Containment Barton Models 289A, 288, and 288A (Licensee References,8, 25, 26, 31-34, and 36)

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Licensee References 8, 25, and 26 are qualification test reports for Barton Models 288A and 289A. Howeve r, the Licensee has failed to provide i

docusentation to show qualification in the areas of pressure and aging.

i 4.5.2.8 Equipment Item No. 9 Pressure Transmitter Located Outside Containment Bailey Models KQ123 and KQ12C i'

(Licensee reference not cited)

I

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No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-33 and VII-A.

m-4.5.2.9 Equipment Item No. 10 Limit Switch Located Outside Containment l

Boneywell Micro Switch Model CP-AR (Licensee References 14 and 17)

I Licensee References 14 and 17 are not qualification test reports; therefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

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TER-C5417-8 on the information provided by the Licensee, this equipment is unqualified in the areas of temperature and pressure.

4.5.2.10 Equipment Item No. 11 Solenoid Valve Located Cutside Containment ASCO Models WPHT8321A1, HT8321A6, HT8211B33, HB8342A4, HB8302C25RV, HT8262C7, 8262D23, HT8316B15, HTX-8320A70, 8302C26D, JV182-084, 8302C26RV, HV180-414, HT832322, HT8316C37, HVA904051A, HT80033, 8344B5, and HT8344A5 (Licensee reference not cited)

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No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-6 and VII-A.

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

Licensee Reference 18 is not a qualification test report; the re fore,

qualification

• documentation is deficient for this item. Regarding agl7g, see the Licensee's statements and commitments in Section VII-A.

m 4.5.2.12 Equipment Item No. 13 Limit Switet Located Outside Containment Bettis Models RX-341 and RX-41 (Licensee Refererces 14-16)

Licensee References 14, 15, and 16 are not qualification test reports; therefore, qualification documentation is deficient for this ites. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the information supplied by the Licensee, this equipment item fails to meet qualification requirements in the areas of pressure and aging.

4.5.2.13 Equipment Item No. 14 Motor Operator Located Outside Containment Limitorque Models SMB-000-5; SMB-00; SMB-1,

-2,

-3,

-4; SMB-0; SMB-ST; SMB-00-15; and SMB-000-2 (Licensee References 2-4 and 57)

Licensee References 2, 3, 4, and 57 are qualification type test reports for Limitorque valves. However, the Licensee has failed to show that the test

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reports referenced for this equipment item correlate with the specific valves

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installed at Brunswick Unit 2.

The Limitorque Report [2] applies only to a specific series of valves and may not apply in this case.

4.5.2.14 Equipment Item No. 15 Radiation Detector Located Outside Containment l

GE Model 194X927G (Licensee Reference 27) i i

Licensee Reference 27 is a qualification summary for a GE radiation I'

detector; however, insufficient documentation is provided to evaluate qualification of this system.

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l 4.5.2.15 Equipment Item No. 16 Pressure Switch Located Outside Containment Barksdale Models B2T-M12SS, D2T-M18SS, TC-9622-1, PlH-M340SS, PlH-M85SS-V, D2H-M150SS, and D2T-M150SS (Licensee References 19, 43-46, 48, and 53)

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Licensee References 43 through 46, 48, and 53 are qualificatien documents t

which FRC has not previously reviewed. Regarding aging, see the Licensee's I

r-statements and commitments in Section VII-A.

Based on the information I.

provided by the Licensee, aging requirements have not been met.

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4.5.2.16 Equipment Item No. 17 Motor Located Outside Containment GE Modals SK6 and 5K8 (Licensee References 9,10, and 27)

Licensee Refe.cnce 10 is a qualification document which FRC has not previously reviewed. Regarding aging, see the Licensee's statements and commitements in Section VII-A.

Based on the information provided by the Licensee, aging requirements have not been met.

t-4.5.2.17 Equipment Item No. 18A Motor Generator Located Inside Containment Limitorque Models SMB-00-10, SMB-3, SMB-2, and SMB-000 (Licensee References 2 and 3) m The Licensee has failed to provide suf ficient documentation to permit evaluation of this equipment item.

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TER-C5417-8 4.5.2.18 Equipment Item No. 19 Motor Control Center Located Outside Containment GE Model IC-7700 (Licensee reference not cited)

No qualification references have been cited for this item. See the

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Licensee's statements and commitments in Sections VII-16 and VII-A.

4.5.2.19 Equipment Item No. 20 Relay Located Outside Containment GE Models CR2811A217Y, CR2810A14AT, CR2811A217Y51, HFA51A49H, CR2810A14AC, CR120A08002AA, and CR2910A14AK2 (Licensee Reference 12)

Licensee Reference 12 is not a qualification test report; therefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and ccamitments in Section VII-A.

4.5.2.20 Equipment Item No. 22 Level Transmitter Located Outside Containment Yarway Model 4418EC (Licensee References 11 and 40)

Licensee References 11 and 40 are not qualification test reports; therefore, qualification documentation is deficient for this item. Regard ing aging, see the Licensee's statements and ccmmitments in Section VII-A.

4.5.2.21 Equipment Item No. 24

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Steam Turbine and Auxiliary Located Outside Containment Terry Steam Turbine Co. Model CCS (Licensee reference not cited)

No qualification references have been cited for this item. See the

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Licensee's statements and commitments in Sections VII-36 and VII-A.

4.f.2.22 Equipment Item No. 25 Motor Located Outside Containment Tuthill Model CD259AT

-e (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-36 and VII-A.

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, of TER-C5417-8 4.5.2.23 Equipment Item No. 28 Thermocouple Located Outside Containment Pyco Model N145C3224-P1 (Licensee References 1, 29, and 30)

Licensee Reference 1 is a qualification test teport. Regarding aging, see the Licensee's statement in Section VII-A and additional comments in Section VII-19.

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

I Licensee References 13 and 21 are not qualification test reports; therefore, qualification documentation is deficient for this item.

4.5.2.25 Equipment Item No. 31 Limit Switch Located Outside Containment

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NAMCO Models EA740-80100 and D2400X-R L

(Licensee References 13, 21, and 56)

Licensee References 13, 21, and 56 are not qualification test reports; i

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therefore, qualification documentation is deficient for this item.

4.5.2.25 Equipment Item No. 33 Pressure Transmitter Located Outside Containment GE Model 552032HKZZ2 j'

(Licensee Reference 50) l-Licensee Reference 50 is not a qualification test report; therefore, qualification documentation is deficient for this ites. Regarding aging, see the Licensee's statements and commitments in Section VII-A and additional comments in Section VII-37.

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4.5.2.27 Equipment Item No. 34 Solenoid Valve Located Inside Containment AVCO Model 5450-5 (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and ccamitments in Sections VII-A and VII-10.

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.o TER-C5417-8 4.5.2.28 Equipment Item No. 35 Flow Switch Located Outside Containment Magnetrol Model F-521 (L1censee Reference 51)

Licensee Reference 51 is not a qualification test report; tnerefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the information supplied by the Licensee, this equipment item is unqualified in the area of aging ef fects.

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

Licensee Reference 52 is not a qualification test report; therefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the t

information supplied by the Licensee, this equipment item has insufficient documentation to permit evaluation of qualification in the area of aging.

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

No qualification references have been cited fre this item. See the Licensee's statements and commitments in Section ',II-40 and VII-A.

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4.5.2.31 Equipment Item No. 40 Control Switch Located Outside Containment GE Model CR2940BM204A i

(Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-41 and VII-A.

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l TER-C5417-8 4.5.2.32 Equipment Item No. 41 Motor Control Located Cutside Countainment Farr Co. Model D51423 (Licensee Reference 55)

Licensee Reference 55 is a qualification test report. Based on the information provided by the Licensee, FRC finds that qualification has not been established for this item.

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4.5.2.33 Equipment Item No. 42 Flow Transmitter Located Outside Containment Bailey Model BQ13221 t3 (Licensee reference not cited)

P' No qualification references have been cited for this item. See the Licensee's statements and comr.itments in Sections VII-33 and VII-A.

y 4.5.2.34 Equipment Item No. 43 Temperature Switch Location outside Centainment m

Barksdale Model T2H-M251S-12 l

(Licensee Reference 58)

Licensee Reference 58 is not a qualification test report; therefore, f,

qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on r

information provided by the Licensee, this item has not been shown to be l~

l qualified.

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f 4.5.2.35 Equipment Item No. 44 l

Time Relay Located Outside Containment I'

Agastat Model 7022AC (Licensee reference not cited) y 1.

No qualification references have been cited for this item. See the y

Licensee's statements and cenniements in Sections VII-28 and VII-A.

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TER-C5417-8 4.5.2.36 Equipment Item No. 45 Solenoid Valve Located Outside Containment Johnson Services Model V-24-2 (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and ccamitments in Sections VII-29 and VII-A.

4.5.2.37 Equipment Item No. 46 Temperature Switch Located Outside Containment Johnson Services Model A19AAC9 (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-29 and VII-A.

4.5.2.38 Equipment Item No. 47 Position Switch Located Outside Containment Johnson Services Model D-251-595 (Licensee reference not cited) 1 No qualification references have been cited for this ites. See the Licensee's statements and ccmmitments in Sections VII-29 and VII-A.

7

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4.5,2.39 Equipment Item No. 48 Motor Located Outside Containment Reliance Models 256T, 23-1/4, and 17-1/2-1750 (Licensee Reference 59)

Licer.see Reference 59 is a qualification document which FRC has not i

previously reviewed. Regarding pressure, see the Licensee's comments in Section VII-30.

Based on the information provided by the Licensee, qualification is not established in the area of post-accident pressure for m

this item.

4.5.2.40 Equipment Item No. 50 Terminal Lug Located Inside/Outside Centainment Tsa Models Sta-Kon-Lug No. Cl3-10, Ring Tongue Nos. G971 and 54108 (Licensee reference not..* ;.)

No qualification references have been cited for this item. See the t

Licensee's statements and commitments in Sections VII-43 and VII-A.

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suum TER-C5417-8 4.5.2.41 Equipment Item No. 51 Terminal Block Located Inside/Outside Containment Curtis Type L (Licensee reference not cited)

No qualifiestion references have been cited for this item. See the Licensee's statements and ccamitments in Sections VII-42 and VII-A.

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4.5.2.42 Equipment Item No. 52 Terminal Block Located Inside/Outside Containment Weidauller Model 6941 (Licensee Reference 61) t1 Licensee Reference 61 is a qualification document which FRC has not

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previously reviewed. Regarding aging, see the Licensee's statements and ccmmitments in Section VII-A.

Based on the information provided by the Licensee, aging qualification has not been established for this item.

4.5.2.43 Equipment Item No. 53 Terminal Block Located Inside/Outside Containment b

GE Models CR151D30 and EB-5 (Licensee reference not cited)

No qualification references have been cited for this item. See the Licensee's statements and commitments in Sections VII-42 and VII-A.

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4.5.2.44 Equipment Item No. 54 Connector Located Inside/Outside Containment Amphenol Model 48-03R18-31 PES I

(Licensee References 62 and 63)

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Licensee Reference 62 and 63 are not qualification test reports; b

therefore, qualification documentation is deficient for this item. Regarding j

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aging, see the Licensee's statements and commitments in Section VII-A.

4.5.2.45 Equipment Item No. 55 Connector Located Outside Containment i;

Pyle-National Model NS2 (Licensee reference not cited)

No qualification references have been c.ed for this itam.

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l TER-C5417-8 4.5.2.46 Equipment Item No. 56 Instrument Cables Located Outside Containment Boston Ins. Wire & Cable Co. Models 1PR416, 3PR$16, and LTR$16 (Licensee References 62 and 64)

Licensee References 62 and 64 are not qualification test reports; therefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

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4.5.2.47 Equipment Item No. 57 Instrument Cables Located Inside Contair. ment 5

Boston Ins. Wire & Cable Co. Model ITR$16 (Licensee References 62 r.nd 64)

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Licensee References 62 and 64 are not qualification test reports; therefore, qualification documentation is deficient for this item. Regarding ag ing, see the Licensee's statements and commitments in Secticn VII-A.

4.5.2.48 Equipment Item No. 58 Instrument Cables Located Inside/Outside Containment Raychem Corp. Model Flam*rol 1PR$16 and ITR$16 LLicensee Reference 65)

Licensee Reference 65 is a qualification document which FRC has not previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the information provided by the Licensee, aging qualification has not been established for this item.

4.5.2.49 Equipment Item No. 59 Thermocouple Cable Located Outside Containment Boston Ins. Wire & Cable Co. Models LPR$16 and SPRil6 (Licensee References 62 and 64)

Licensee References 62 and 64 are not qualification test reports;

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therefore, qualification documentation is deficient for this item. Regarding

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aging, see the Licensee's statements and commitments in Section VII-A.

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I 4.5.2.50 Equipment Item No. 60 Thermocouple Cable Located Outside Containment Samuel Moore & Co. Models Dekoron ECI, 1PR$16, and SPR416 l

(Licensee Reference 66) l Licensee Reference 66 is a qualification document which FRC has not previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the information provided by the l

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Licensee, aging qualification has not been established for this item.

l 4.5.2.51 Equipment Item No. 61 Power Cable 1000 V Located Outside Containment

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Cerro Wire & Cable Co. Models 4/c616, 2/ct8, 4/ct10, 4/c66, l

3/c250, 7/c250, and 3/c500 (Licensee References 67 and 68) l Licensee Reference 67 is a qualification document which FRC has not previou21y reviewed. Regarding aging, see the Licensee's statements and i

commitments in Section VII-A.

Based on the information provided by the Licensee, aging qualification has not been established for this item.

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4.5.2.52 Equipment Item No. 62 l

Power Cable, 1000-5000 V Located outsice Containment Okonite Co. Models 4/0 AWG, 2/ct8, 4/ct10, 4/ct6, 3/c250, 7/c250, and 3/c500 (Licensee Reference 68) l Licensee Reference 68 is not a qualification test report; therefore, I

qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

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4.5.2.53 Equipment Item No. 63 l

Control Cable Located Outside Containment l

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

(Licensee Reference 69) l Licensee Reference 69 is a qualification document which FRC has not

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previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

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TER-C5417-8 4.5.2.54 Equipment Item No. 64 Control Cable Located Inside/Cutside Containment Raychem Models $8-9-10-12 AWG Flastrol (Licensee Reference 65)

Licensee Reference 65 is a qualification document which FRC has not previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the information provided by the Licensee, aging qualification has not been established for this item.

4.5.2.55 Equipment Item No. 65

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Control Cable Located Cutside Containment Rockbestos Co. Models 2/ctl2, 4/ctl2,1/ctl2, and 1/ctl4 (Licensee Reference 70)

Licensee Reference 70 is not a qualification test report; therefore, qualification documentacion is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

'f 4.5.2.56 Equipment Item No. 66 Cable Termination Located Outside Containment Burndy, Ckonite Model 5600 V (Licensee Reference 68)

Licensee Reference 68 is not a qualification test report; therefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

4.5.2.57 Equipment Item No. 67 Power Cable Splice Located Cutside Containment Burndy, Ckonite Model T95 and #35 (Licensee Reference 70)

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l Licensee Refer?cce 70 is not a qualification test report; therefore, qualification docu tation is deficient for this item.

4.5.2.58 Equipment Item No. 68 Heat Shrink Insulation Located Inside/Cutside Containment Pennwalt Corp., Model Not Stated (Licensee reference not cited) t No qualification references have been cited for this item. See the Licensee's statements and ccmmitments in Secticns VII-43 and VII-A.

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TER-C5417-8 4.5.2.59 Equipment Item No. 69 Thermocouple Splice Located Outside Containment AMP, Scotch, Raychem Models 320557, 70, and WCSF-N

{ Licensee References 69 and 71 Licensee References 69 and 71 are qualification cocuments which FRC has r: previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the infor: nation provided by the I

Licensee, aging qualification has not been established for this ites.

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TER-C5417-8 4.6 NRC Category V EQUIPMENT WHICH IL L, QUALIFIED The DCR Guidelines reqsire that cceplete and auditable records reflecting a comprehensive qualification methodology and program be referenced and made available for review of all Class lE equipment.

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

(i) documen-tation reflecting qualification as specified in DOR Guidelines has not been made available for review, (ii) docu entation reflecting qualification has been made available for review and is totally inadequate, or (iii) the documentation indicates that the equipment item has not successfully passed required tests. The following equipment items are therefore cbnsidered unqualified.

4.6.1 Equipment Item No. 1 Selector Switch Located outside Containment Honeywell Micro Switch Models PTSHE202C-B97, PTKSC221CCB99, i

PTSHA202F-B52, PTKBC2221CCC, and PTKBC2221CCF9 (Licensee References 5 and 14)

Licensee References 5 and 14 are not qualification documents for this item. Based on the information provided by the Licensee, this item f ails to meet qualification requirements in the areas of temperature and pressure.

4.6.2 Equipment Ites N;. 18B Motor operator Located Inside Containment Limitorque Models SMB-00-1 and SMB-00 (Lice.tsee Refeionces 2 and 3)

The Licensee has provided documentation which snows this equipment item is deficient in the areas of temperature, pressure, and radiation effects.

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TER-C5417-8 4.6.3 Equipment Ites No. 21 Control Switch Located Cutside Containment Honeywell Micro Switch Models PTSHA201 and PTSHA202F-B52 (Licensee References 5 and 14)

LJcensee References 5 and 14 are not qualification test reports; therefore, qualification documentation is deficient for this item.

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4.6.4 Equipment Item No. 23 L.

Flow Switch Located Outside Containment Barton Model 289 (Licensee References 8, 26, 37, and 38)

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s Licensee References 8 and 26 are qualification test reports for Barton models. Based on informatiott provided by the Licensee, this equipment is deficient in the area of radiation effects.

4.6.5 Equipment Item No. 26 Flow Transmitter Located Outside Containment GE Model 50-555111BDAA3PCH (Licensee Reference 50) a Licensee Reference 50 is not a qualification trat reports therefore, tw I

qualification documentatior. is deficient for this ites. Regarding aging, see the Licensee's statements and commitments in Section VII-A and additional I

comments in Section VII-37.

Based on the information provided by the Licensee, this item is deficient in the area of temperature.

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4.6.5 Equipment Item ::o. 27 m_

. Level Switch Located Outside Containment i

Robertsnaw Model SL-205-A2-Ril-Bil-1 I

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(Licensee References 22 and 49)

Licensee Reference 22 is a qualification documented which FRC has not

,s previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A and additional statements in Section VII-18.

Based on the information provided by the Licensee, this item is deficient in the area of temperature.

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TER-C5417-8 4.6.7 Equipment Item No. 29 Temperature Switch Located Cutside Containment Fenwall Model 17002-40 (Licensee Refere,nces 23 and 28)

Licensee References 23 and 28 are not qualification test reports;

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therefore, qualification documentation is deficient for this item. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on the information provided by the Licensee, this item is deficient in the area of radiation requirement.

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4.6.8 Equipment Item No. 32 Limit Switch Located Inside Containment

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Honeywell Micro Switch Model CP-AR (Licensee References 14 and 17)

The Licensee has provided documentation which shows that this item is unqualified in tts areas of temperature, pressure, and radiation.

4.6.9 Equipment Ites No. 37 3

Position Switch Located Outside Containment Honeywell Micro Switch Model OP-DAR

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(Licensee References 14 and 17)

Licensee Reference 17 is a qualification document which FRC has not previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

Based on information supplied by the Licensee, this equipment item is unqualified in the areas of temperature, pressure, and ag ing.

4.6.10 Equipment Item No. 38 Level Switch Located Outside Containment Magnetrol Model 5.0-751 (Licensee Reference 54) l Licensee Reference 54 is a qualification document which FRC has not

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previously reviewed. Regarding aging, see the Licensee's statements and

-s commitments in Section VII-A.

Based on informatien provided by the Licensee, this equipment is unqualified in the areas of pressure, radiation, and aging.

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TER-C5417-8 4.6.11 Equipment Iter No. 49 i

Terminal Lug Located Inside/outside Containment AMP Special Lug Model PIDG-KYNAR (Licensee Reference 60)

Licensee Referexe 60 is a qualification document which FRC has not 4

previously reviewed. Regarding aging, see the Licensee's statements and commitments in Section VII-A.

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4.6.11 Equipment Itas No. 70 t

Electrical Penetration Assembly Located Inside/outside Containment Westinghouse Model Class B,C C

(Licensee References 63, 72, and 73) 6a Licensee References 72 and 73 are qualification type test reports.

However, the information provided by the Licensee shows this item to be unqualified in the area of post-accident pressure.

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4.7 NRC Category VI EQUIPMENT FCR WHICH QUALIFICATICN IS DEFERRED This section normally includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submissions 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, there are no equipment items that fall into this category.

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i TER-C5417-8 5.

CONCLUSIONS FRC's review of the qualification documentation and other infor: nation submitted by Carolina Power t. Light for these equipment items and their applications in the Brunswick Unit 2 plant has resulted in the following categories:

NPC Compliance With The DOR Quantity Of i'

Categorv Guideline Requirements Equipment Items I.a Equipment Fully Satisfies All Applicable Requirements.for 0

Life of the Plant I.b Equipment Does Not Meet All I

Applicable Requirements for Life of the Plant; However, O

Deviations are Judged Acceptable II.a Equipment Nily Satisfies All

~g Applicable Requirements for Less Than Plant Life O

L-II.b Equipment Fully Satisfies All Applicable Requirements Provided f

That Specific Modifications are i

Made 0

II.c Equipment for Which the Licensee Has i

Not Provided Evidence of Full Compli-t-

ance with the Guidelines, but Which is Judged by FRC To Be Satisfactory I

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for Imss Than Plant Life Based on Total EEQ Program Review 0

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l III Equipment is Exempt from

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Qualification 0

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IV.a Equipment has Qualification l

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Testing Scheduled 0

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IV.b Equipment has High Likelihood of Operability; However, Proper Qualification Documentation is Not Available 59 i

F' V

Equipment is Unqualified 12 t

VI Equipment for Which Qualification 0

is Deferred m

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In general, the ma]or deficiencies that have been identified are shcwn in the summary review sheets at the end of the section.

The conclusions stated herein represent a summary of the results of the equipment environmental qualification evaluation conducted by FRC in

~

accordance with the methodology presented in Section 3.

The evaluation results are largely based on the available qualification documentation provided by the Licensee. The results of the review do not necessarily baply j

that the equipment is unreliable, unsafe, or represents a significant plant safety issue they do imply, however, that qualification documentation is i

inadequate and that additional information is required.

~

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

The following r!

designations are used:

_)

X = A deficiency with respect tv compl'snee with a Guideline

'j requirement. Deficiencies result in equipment items categorized as unqualified or qualification not established.

L = A limiting condition with respect to qualification in that the J

qualified life has noc been established by the Licensee.

O = NRC Qualification Category.

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

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A FRC TASK WCWI PLANT NAME PAGE 00hranidin Research Center 8##'*#" 2

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kDeDMbD PROJECT UTIUTY i

EQUIPMENT ENVIRONMENTAL 02G<.l5417-01 QUAUFICATION

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DCCKET NRCTAC DATEIENGINEER P

IE549 018

SUMMARY

REVIEW EQUIPMENTITEM NUMBER

/ l 2 l3 lV lI! 4 l 7 l 8 l 9 l /ol// l/2 lr3l/9l/Sl/4 l/7l/#M/s)/9 GUIDEUNE RECUIREMENTS, (DESIGNATICNS: X-DEFlC:ENCY,L-UMITING CONDITION) l 4-EVIDENCE OF OUALIFICATION YlI )( XlX k N'X N Y Y X Y X

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1 RELATIONSHIP TO TEST SPECIMEN AGING DEGRADATION EVALUATED Y X N

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CUAUFICATION CATEGORY, O -CATEGCRY DESIGNATICN

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TER-C5417-8 6.

REFERENCES r

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 Cperator 4600198/F-C2232-01/ll.68

+

4 Qualification Test of Limitorque Valve F-C3117/12.71 5

Mikro Switch LTR - 24407 6

FSAR Appendix M Section M7.9 Sept.1972, DRR$12, 3/29/72 7

Reactor Building Environc2ntal Report S

Qualificaticn Test Report for ITT Sarton 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 L

13 Namco Limit Switch Index 14 File Reference No. 6335 of Nuclear Rad. and Switch Application l

15 Evaluation of Asbestos Free Plastics FR 14171/2.21.79 16 Humidity Test of G4neral Purpose Phenolic M. FR 12774/7.15.75 17 Quality Assurance Test FR 13048/2.3.76 18 Material Analysis for Pylo RTO.s H-338-7 7

19 Material Analysis for Barksdale Pr. SW H-338-15 20 Material Analysis for Static 'O' Ring H-33-12 21 Material Analysis for Namco Limit SW H-338-16 l

22 BWR Qualification Summary for R.L.S. WSR-ll6-A-02 23 Material Analysis for F.T.S. H-338-7 l

24 Engineering Evaluation of Motors 10/25/80 15 ITT Barton Eng. Report No. Rl-288S-11 and Qualification Test Procedure 26 BWR Qualification Summary for B. P. S. QSR-029-A-01

~'

27 BWR Qualification Summary for GE Rad Set QSR-015-A-01 28 Viking Laboratory GE Summary NSE79001, #30411 29 Cdgen Technical Laboratory GE Summary NSE 79002, 470822 30 Ccgen Technical Laboratory GE Summary NSE 79003, 970822 s

As

.. 5nklin Research Center 6-1 4 c>

a om. r n -

w~ m

,d"'we M

R

• v

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-ym

>-y

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TER-C5417-8 31 GE Summary NSE 79004 Addendum to TP-199-4; 5/24/71 32 GE Summary NSE 79005 Addendum to TP-199-4; 5/24/71 33 GE Summary NSE 79006 Addendum to TP-199-4; 5/24/71 34 GE Summary NSE 79007 Addendum to TP-199-4; 5/24/71

~

35 GE Summary NSE 79008 Addendum to TP-199-4; 5/24/71 36 GE Summary NSE 79009 Addendum to TP-199-4; 5/24/71 37 GE Summary NSE 79010 Addendum to TP-199-4; 5/24/71

_j 38 GE Summary NSE 79011 Addendum to TP-199-4; 5/24/71

~1 39 GE Summary NSE 79012 2755-4755 8/4/71 i

u.

40 GE Summary NSE 80014 2755-4755 8/4/71 41 GE Summary MSE 80015 2755-4755 8/4/71 42 GE Summary NSE 80021 70526 5/4/71 43 GE Summary NSE 80024 596-0398 8/13/75 44 GE Summary NSE 80025 596-0398 8/13/75 L) 45 GE Summary NSE 80027 596-0398 8/13/75 46 GE Summary NSE 80030 596-0398 8/13/75 47 GE Summary NSE 80031 596-0398 8/13/75 48 GE Summary NSE 80032 12625 6/5/62

~

49 GE Summary NSE 80033 12625 6/5/62 50 GE Summary NSE 80036 4/28/70 51 Material Analysis for Magnetrol Flow Switches, H-338-13 52 Material Analysis for Cherry Electrical Products H-338-9 53 Approved Eng. Test Laboratories GE Summary NSE 80028 54 BWR Equipment Qualification Summary for Magnetrol, QSR030-A-01 55

?arr Co. Environmental Qualification Test Report Class IE Corp. 10/14/80 56 Materiel Analysis for Namco Limit Switch Model D2400X; H-338-17 57 Qualification Type Test Report, Limitorque Valve No. 600376A, 5/13/76 "I

58 Material Analysis for Barksdale Temperature Switch H-338-4

's 59 Reliance & Co. Summary Report NCC-9, 7/1/78 60 Eng. Test Report on AMP Rad. Res. 9110-11516, 3/6/80 61 Qualification Test Program for Tersination Block F-C5205-03,10/79 62 Radiation Testing (4800R16-24 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 6

da a

i..; Franklin Research Center 6-2

= w w 'w. 7.w a in

.5 ' _. -.,[

n, TER-C5417-8 65 FIRL-Final Report, Test of Raychem FL. 0F-C4033-1 66 FIRL-Final Report, Q'2alification Test 9F-C368 67 FIRL-Final Report, Qualification Test 9F-C2857 68 Okonite Co. Engineering Report #141, 2/29/72 69 LOCA Qualification of Kerite 600 Volt HTK 70 Qualification of Firewall III Class "1E" 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-3-16-01 74 Letter from G. Lainas, NRC, to A. Schwencer, NRC.

Subject:

T.lectrical Equipment Environmental Qualification, dated February 19, 198C.

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

Kepoler, K. V. Seyf ritz, R. H. Engelken, NRC.

Subject:

IE Class Supplement No. 2 Bulletin 79-013, Environmental Cualification of Class lE Equipment, dated September 29, 1980.

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

Keppler, K. V. Seyfritz, R. H. Engelken, NRC.

Subject:

IE Supplement No.

3 Bulletin 79-01B, Environmental Qualificacica of Class lE Equipment,

~

dated October 24, 1980.

t' 77 U.S. NRC Memorandum and Order (CLI-80-21) pursuant to the Petition for Emergency and Remedial Relief filed with the NRC on November 14, 1977.

78 T7A Response to NRC IE Bulletin 79-013, Environmental Qualification of Class lE Equipment for Brunswick Steam Electric Plant, Units 1 and 2, dated October 31, 1980.

t 79 NUREG-0588.

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TER-C5417-8 APPENDIX A - ENVIRCNMENTAL SERVICE CCNDITICNS The Licensee has provided information concerning environmental zones and postulated design basis accident conditions. Figures A-1 and A-8 show accident profiles for plant areas subject to transient accident conditions.

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

U Brunswick 2 has a domineralized water spray system rather than a chemical spray-system inside containment. This is considered in the Licensee's analysis. The Licensee's analysis of design basis accidents use the folicwing assumption: In the design of the Brunswick pressure suppression containment (i. e., drywell-torus), flooding is not considered to be a credible accident environment due to the high volume, low hydraulic resistance flow paths from I'

the drywell to the torus which immediately direct IDCA blowdown flow away from the drywell. HELB does not affect environmental conditions insidet containment g-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 due to fluids which are recirculated from inside the primary containment to accomplish long-term cooling following a u

IDCA. The IDCA-induced radiation environment, and the subsequent transport is evaluated in accordance with the guidelines in NUREG-0588. For

process, conservatism, all leakages from drywell are assumed to be leaking into any one j

compartment adjacent to drywell. The leakage outflow from that compartment is l

then assumed to be uniformly mixed in the remainder of the reactor building.

r' The conservatism of this method lies in the conservatively high computed l

values for the concentrations of fission products in each of the engineered safety features compartments.

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TER-C5417-8 Table A-1 ACCIDENT PRESSURE PROFILE TABI2 i

HELB Analysis Per Reactor Building LOCA Environmental Report Area Peak Peak I

Report Profile Area Description Compt.

Table Pressure Pressure No.

(PSIG)

(PSIG)

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

i l

Reactor Bldg.

6 IV 1.0 0.2 F

j 20'-0" & Above 1

q LL HPCI Room 1

IV 2.7 0.2 i

g NN Core Spray Rooms 6

IV 1.0 0.2 PP RWCU Area 1

VIII 6.9 0.2 i

Main Stasm Tunnel 6

IV 1.0 0.2 RR RCIC/HPCI Tunnel 5

IV 3.2 0.2

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TER-C5417-8 Table A-2

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LOCATION OF SUBSTANrI.*.L FISSION PRODUCT INVENTORY

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4 APPROXDfATE PEAK

~

SOURCE LOCATION INVENTORY. Ci 6

Reactor Bitilding (Uniform Dispersal)

Total:

8.1 x 10 6

N.G.:

5.6 x 10 Iodine:

2.5 x 100 SGTS Filters in Reactor Building Iodine:

4. 2 x 105 i'

8 Dryvell Total:

5.5 x 10 8

~

N.G.:

4.0 x 10 Iodine:

1.5 x 108 8

Pressure Suppression Chamber Iodine:

3.0 x 10 i' ~ ~

Typical Small Compartment (Adjacent to drywell in Reactor Building)

Total:

105 I

i Typical I.arge Compartment 6

(Adjacent to drywell in Reactor Building)

Total:

10

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1 TER-C5417-8 APPENDIX B - EQUIPMENT ITEM TABLE This appendix contains the list of safety-related electrical items for Brunswick Unit 2 provided by the Licensee in its October 31 response to IE

{

Bulletin 79-OlB. This listing shows the equipment items by :nanufacturer and model number, plant location, and time required to function as identified by the Licensee.

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TER-C5417-8 PLANT NAME: BRUNSWICK UNIT 2 EQUIPMEN2 LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 1

Selector Switch Outside 1-3,92,94,164, 5,14 Honeywell Micro Containment 168,170,172,179, 5

Switch 189,192,194,230, PTSHE202C-B97 232,235,238,241, PTKBC2221CCC 244,246,248,250, PTKBC 221CCB99 252,254,256,258, PTKBC2221C0F9 260,300 FISHA202F-B5 2 2

Solenoid valve Inside 130,131,135,137, None ASCO Containment 139,141,158 HB-8302C25RV

]

HT-8320A70 3

Level Switch outside 5,6,53,98,150, 11,39,41, Yarway Containment 151,213-216 42 4418C 4

Pressure Switch outside 7,58,75-77,118, 20,42 Static-O-Ring Containment 287,289,290,326, 12N-AA4-X10TT 327 SN-AA3-X95TT 6N-AA21-X9SVTT 5

H2/02 Analyzer Outside 8-10 None Nuclear Measure-Containment ment Corp.

Model Not Stated 6

I4 vel / Pressure Outside 11,14,15,353 Indicator Containment None Emico 35W 7

Imvel Transmitter Outside 12 None Bailey Containment BQ15222 6 l a

8e_.::

B-2

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TER-C5417-8 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION P

NO.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES

~

8 Pressure Switch outside 13,55,57,115-117, 3,8,25,32, Barton Containment 152-154 34 288 288A 289A 9

Pressure Trans-Outside 16,17 None mitter Containment Bailey KQ123 KQ12C 10 Limit Switch outside 18,38,41,49,50, 14,17 Honeywell Micro Containment 159 Switch CP-AR

, ~'

11 Solenoid Valve Outside 19,20,23-29,31, None ASCO Containment 33,35,39,40,42,43, WPHT8321A1 45,47,49,51,143, i_

HT8321A6 145,147,149,100, HT8211833 181,182,281,303-HB834 2A4 311,320-323,325, HB8302C25RV 340,344,373-384 HT8262C71 8262D23 HT8316B15 L

HTX-8320A70 8302C26D JV18 2-084 8302C26RV HV180-414 HT832322 HT8316C37 HVA904052A HT80033 C

8344B5

{

HT8344A5 12 Resistance Inside 21,22 18 y

Temperatuee Containnent Detector Pyco 100-OEM Platinum "W

@h.U Franklin Research C. enter B-3 A w or n. 7.mn e--e-=*

-w-m-

ww.

-w yA--

g-*w.

• N*

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w

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a 2

TER-C5417-8 a

EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION No.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 13 Limit Switch outside 30,32,34,44,46 14,15,16 Bettis Containment RX-34]

RX-41 14 Motor Operator Outside 36,37,63-72, 2-4, 57 Limitorque Containment 103,105-113 SMB-000-5 SMB-0 0 SMB-2, SMB-1, 133,176, SMB-3, SMB-0, 179,180,184,197-SMB-4, SMB-ST, 201,265-280,282-SMB-000-2 283,292,337,338, SMB-00-15 341,342,345-352, 359-363,366-372 15 Radiation Outside 52 27 De tector Containment GE 194X927G m

16 Pressure Switch outside 54,56,119-122, 19,43-46, Barksdale Containment 161,162,204-207, 48,53

{

B2T-M12SS 217,227,228,288, D2T-M18SS 291,301,302,318, PlH-M340SS 319 TC-9622-1

_j P1H-M8 5SS-V D2H-M150SS D2T-M150SS 17 Motor Outside 59,60,263,264, 9,10,24 GE Containment 355-358 SK6 3

SK8 18A Motor Operator Inside 73,74,177, 2, 3 i

Limitorque Containment 219-226,284 SMB-00-10, SMB-3 SMB-000, SMB-2 l

18B Motor Operator Inside 104,132,178, 2,3

(

Limitorque Containment 183,196 SMB-00-1 SMB-0 0 6

l

-A-B-4

.... Franklin R-search C. enter

~

% at ne r==n in

h TER-C5417-8 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION r'

NO.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 1

19 Motor Control Outside 78-90 None Center Containment GE IC-7700 F'

20 Relay Outside 91,163,166,167, 12 GE Containment 174,175,188,191,

~

CR2811A217Y 229,234,237,240, CR2810A14AT 243,362,329-332, CR2811A217YS1 385,337 4

Ii HFA51A49H CR2810A14AC CR120A0800 2AA CR2810A14AK2 21 Control Switch outside 93,165,169,171, 5,14 Honeywell Micro Containment 173,190,193,195, I -*

Switch 231,233,236,239, PTSHA201 242,245,247,249, PTSHA202F-B52 251,253,255,257, 259,261,285

, ^

22 Level Transmitter Outside 95 11, 40 Yarway Containment 4418EC l

23 Flow Switch Outside 61,62,101 8,26,

(,

Barton Containment 37, 38 289 1

r i

24 Steam Turbine Outside 99 None l

and Auxiliary Containment Terry Steam Turbine Co.

l CCS l

25 Motor Outside 100 None Tuthill Containment CD259AT I~

26 Flow Transmitter Outside 102 50 h,

GE Containment I

50-555111BDAA3PDH 4 1 i

l

1. 4 B-5 I

l t.;; Franklin Research Center a

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4 TER-C5417-8 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 27 Level Switch Outside 114 22,49 Robertshaw Containment SL-205-A2-Rll-Bil-1 28 Thermocouple Outside 123,128,129,185, 1,29,30 Pyco Containment 208-210 N145C32224-PL 29 Temperature Outside 124,125,127,156, 23,28 Switch Containment 211,212 Fenwall 17002-40 30 Limit Switch Inside 134,136,138,140, 13, 21 NAMCO Containment 142,312 EA740-80100 31 Limit Switch Outside 144,146,148,313, 13,21,56 NAMCO Containment 339,343 i

EA740-80100 D2400X-R 32 Limit Switch Inside 157 14,17 Honeywell Micro Containment Switch CP-AR 33 Pressure Trans-Outside 286,293 50 mitter Containment GE 552032HKZ22 34 Solenoid valve Inside 4

None AVCO Containment 5450-5 35 Flow Switch Outside 294 51 Magnetrol Containment F-521 36 Position Switch Outside 295,297 52 Cherry Electrical Containment Products Corp.

E23-60H a

1. e B-6

..1 Franklin Research. Center ar - en.7 -

4 ge w

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TER-C5417-8 EQUIPMENT LICENSEE IIEM ITEM SUBMITTAL QUALIFICATION P

NO.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 37 Position Switch Outside 296,298,299 14,17 Honeywell Micro Containment Switch OP-DAR

~

38 Level Switch Outside 324 54 Magnetrol Containment 5.0-751 T*

39 Fuse Panel Outside 328 None

['

GE Containment Model Not Stated 40 Control Switch Outside 333,334 None r-GE Containment t

CR2940BM204A 41 Motor Control Outside 335,336 55 Farr Co.

Containment D51423 l^

42 Flow Transmitter Outside 353 None Bailey Contairunenn

~

BQ13221 43 Temperature Ou tside 364 58 Switch Containment Barksdale f~

T2H-M2515-12 44 Time Relay Outside 386 None Agastat Containment 7022AC I.

45 Solenoid Outside 388,389 None n

Johnson Services Containment V-24-2 46 Tegerature Outside 390-395 None T ,

Switch Containment

{>

Johnson Services v

A19AAC9 r-t.

b d-2--

B-7

..h Franklin Research Center

• on n a# ne r-m an.

,-owmei++-mw' % ' * * * * *

"***N*'WW

TER-C5417-8 EQUIPMENT LICENSEE Im ITEM SUBMITTAL QUALIFICATION NO.

DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 47 Position Switch outside 396,397 None Johnson Services Containment D-251-595 48 Motor Ou tside 398-401 59 Reliance Containment 256T 23-1/4 17-1/2-1750 49 Terminal Lug Inside/Outside 402-406 60 AMP Special Containment Industries PIDG-KYNAR 50 Terminal Lug Inside/outside 426-428 None T&B Containment Sta-lGon Lug C10-10

}

Ring Tbngue

~

G9 71, 54108 51 Terminal Block Inside/outside 410 None Curtis Containment Type L 52 Terminal Block Inside/Outside 431 61 Weidmuller Containment 6941 53 Terminal Block Inside/outside 411-413 None GE Containment CR151D30 ES-5 54 Connector Inside/outside 405 62, 63 Amphenol Containment 48-03R18-31P&S 55 Connector Outside 420 None Pyle-National Containment

~

NS2 4

I 8-O-B-8 a

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TER-C5417-8 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION I

NO.

DESCRIPTICN LOCATION PAGE REFERENCES REFERENCES 56 Instrument Cable Outside 406 64 Boston Ins. Wire Containment

& Cable Co.

IPR $16 3PR$16 I'

1TR916 57 Instrument Cable Inside 407 64 Boston Ins. Wire Containment r

& Cable Co.

1TR$16 58 Instrument Cable Inside/

422 65 Raychem Corp outside Flamtrol Containment IPR $16 1TR$16 59 Thermocouple Outside 408 64 t

Cable Containment I -

Boston Ins. Wire

& Cable Co.

1PR$16 SPR$16 l

1 60 Thermocouple outside 425 66 Cable Containment Samuel Moore &

l Co.

Dekoron ECI 1PR$16 SPR$16 61 Power Cable-Outside 409 67 l

1000 V Containment I

Cerro Wire &

J' Cable Co.

l 4/ct6, 4/ct10,1/cfl2 4/et16, 7/ctl6 iL.

62 Power Cable Outside 415,416 68 1000-5000 V Containment Okonite Co.

4/o AWG, 2/ct8, 4/ct10 l

4/ct 6, 3/c250, 7/c250, 3/c500 1

g-2--

B-9

}

.. Franklin Research Center m o w n m ma.

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O TER-C5417-8 l

E2UIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION

~

NO.

DESCRIPTION I/X*ATION PAGE REFERENCES REFERENCES 63 Control Cable outside 414 69 Kerite Co.

Containment 2/c412 4/c412 64 Control Cable Inside/outside 421 65 Raychem Containment

$8-9-10-12 AWG Flastrol 9

65 Control cable Outside 424 70 Rockbestos Co.

Containment 2/c412, 4/ctl2, 1/c612, 1/c414 66 Cable Termination Outside 417 68 Burndy, Okonite Containment

]

5000 V a

67 Power Cable Outside 418 None Splice Containment Burndy, Okonite 1J 79.;

635 68 Heat Shrink Inside/Outside 419 None Insulation Containment Pennwalt Corp.

Model Not Stated 69 Thermocouple Outside 423 69,71 Splice Containment AMP, Scotch, Raychem

320557, 7 0, WCSF-N a

70 Electrical Inside/Outside 429 63,72,73 Pene tration Containment Assembly Westingnouse Class B,C 6

Q B-10

.. 0 Frankkn Researc.h Center

• N.an or N r== m.

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TER-C5417-8 i ~~

APPENDIX C - SAFETY SYSTEMS AND EQUIPMENT FOR WHICH ENVIRONMENTAL QUALIFICATION IS IV BE ADDRESSED The Licensee has submitted.a list of safety-related systems that must function in order to mitigate the consequences of a design basic accident.

This information was submitted in the response to IE Bulletin 79-OlB and was t

included in the Licensee's October 31 response.

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TER-C5417-8 e Autossatic Depressurization System (ADS) - 321 e Containment At:nospheric Control System (CAC)

~

e Core Spray System (CS) - E21 e Electrical Distribution System (ED) e High Pressure Coolant Injection System (HPCI) - E41 e Nuclear Steam Supply Shutoff System (NSSS) - A71 e Reactor Core Isolation Cooling System (acIC) - E51 a

i e Residual Heat Removal System (MIR) - Ell e Reactor Instrument Penetration System (RIP) i e Reactor Protection System (RPS) - C72

~'

e Standby Gas Treat:nent System (SBGT) e Service Water System (SW) e Ventilating Air System (VA) 9 f

.a 1

i

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43 C-2 4

..L Franklin Research. Center

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a c=.on w th. Fr n j

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TER-C5417-8 APPENDIX D - EQUIPMENT ITEM CROSS-REFERENCE LIST EQUIPMENT FINAL TECHICAL ITEM EVALUATION REPORT SECTION 6

1 4.6.1 2

4.5.2.1 3

4.5.2.2 4

4.5.2.3 5

4.5.2.4 6

4.5.2.5 7

4.5.2.6 8

4.5.2.7 9

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