ML18025B527

Equipment Environ Qualification,Browns Ferry Unit 1, Technical Evaluation Rept

ML18025B527
Person / Time
Site:	Browns Ferry
Issue date:	01/31/1981
From:	Crane C FRANKLIN INSTITUTE
To:
Shared Package
ML18025B526	List: ML18025B527 ML20004D222 ML20004D223
References
IEB-79-01B, IEB-79-1B, TER-C5417-004, TER-C5417-004-DRFT, TER-C5417-4, TER-C5417-4-DRFT, NUDOCS 8106090008
Download: ML18025B527 (185)

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TECHNICAL EVALUATIONREPORT FINAL DRAFT EQUlpMENT ENVlRONMENTALQUALlFlCATlON TEIIESSEE VPU i=Y AUTHORITY BRO>IS FERRY NUCLEAR PCI'ER STATION 0IIT 1 NRC DOCKET NO. - 50-259 NRC TAC NO. 42~81 FRC PROJECT C5417 EG6iG IDAHO, INC. SUBCONTRACT NO. K-7615 FRC TASK 4 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 account of v.ork performed under a subcontract from EGBG Idaho. Inc.a prime contractor to the United States Department of Energy. Neither EG8G nor the United States Government nor any agency thereof. or any of their employees.

makes any warranty. expressed or implied, or assumes any legal liability or responsibility for any third party's use. or the results of such use. or any information, apparatus. produc; or process disclosed in this report, or represents that Its use by such third party would not infringe privately owned rights.

NOTE THIS IS A DRAFT Because of schedule limitations. this report draft has not gene through the complete review cycle of FRC. While the overall conclusion is expected to remain the same. the reader is cautioned that some details of the report may change as the review is completed.

Tl)IS DOCUMENT CONTAINS POOR QUALITY'PAGES t! lJ'uL'ranklin Research Center A Division of The Franklin Institute r!03 r 2 I '5i >48. I 000

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TECHNICAL EVALUATIONREPORT FINAL ORAFT EQ U I PM ENT ENVl RON M ENTAL Q UALlF I CATlON TBSESSEE YOLKED AUTHORITY BROl'INS FERRY NUCLEAR FSIER STATION UNIT 1 NRC DOCKET NO. 50-259 NRC TAC NO. 42481 FRC PROJECT C5417 EGieiG IDAHO, INC. SUBCONTRACT NO. K-761 5 FRC TASK 4 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 account of work performed under a subcontract trom EG8,G Idaho. Inc.. a prime contractor to the United States Depar:n;ent ot Energy. Neither EG8G nor the United States Government nor any agency thereot, or any of their employees.

makes any warranty. expressed or implied, or assumes any legal liability or responsibility for any third party's use. or the results of such use. or ariy intormation. apparatus. product or process disclosed in this report, or represents that its use by such third party would not intringe privately owned rights.

NOTE THIS IS A DRAFT Because of schedule limitations. this report draft has not gone through the complete review cycle of FRC. While the overall conclusion is expected to remain the same. the reader is cautioned that some details of the report may change as the review is completed.

L1I41 Franklin Research Center A Division of The Franklin Institute 11ie Benjamin Fpanhiin Pariiway. Phile. Pa ! 9l03 '2l5> aa8 F000

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TER-C5417-4 CONTENTS Section Title Pa<ac 1 INTRODUCTION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-1

1. 1 Purpose of the Review .

1.2 Generic Issue Background . . . . . . . . . 1-1 1.3 Specific Zssue Background . . . . ~ . ~ ~ . 1-6 1.4 Scope of the Review 1-7 QUALIFICATION......

2 NRC 2.1 2.2 CRITERIA FOR EValZRO%KNTAL Criteria Provided by the Staff Positions and Supplemental NRC........

Criteria.....

2-1.

2-1 2-1 2.2.1 Service Conditions Inside Containment for a Lossmf-Coolant Accident. 2-1 2.2.2 Submergence........... 2-2 2.2.3 Equipment Located in Areas Normally Maintained at Rcom Conditions 2-2 2.2.4 2.2.5 2.2.6 Deferment Test Sequence of Qualif ication Review ..

Simulated Service Conditions and Test Duration

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2-3 2-3 2-4 2.2.7 Radiation . . . . . . ,

. . . . . 2-4 3 METHODOLOGY USED BY FRC . ~ ~ ~ . ~ ~ ~ ~ ~ . 3-1 4 TECHNICAL EVALUATION. ~ ~ . . . . . . . . . 4-1 4.1 Methodology Used by the Licensee 4.1.1 4.1.2 Completeness of Equipment List......

Definition of Equipment Operating Time Requirements.

. 4-1 4-1 4-2 4.1.3 Qualified Life 4-4 4.1.4 Licensee Event Reports (LER) 4-6 4.1. 5 Licensee's Generic Postions With Respect to the DOR Guidelines

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TERM5417-4 CONTENTS Section Title Pacae 4.1. 6 Required Signatures. 4-9 4.1.7 Chemical Spray 4-10 4.1.8 Description of Qualification/Replacement. Plan ~ . 4-10

4. 2 Equipment Qual ified for Plant Life. 4-12 4.2.1 NRC Category Z.a Equipment That Pully Satisfies All Applicable Requirements of the DOR Guidelines 4-12 4.2.2 NRC Category Z.b Equipment for Which Deviations Prom the DOR Guide-lines Are Judged Acceptable. 4<<12 4.3 Equipment Qualified With Restrictions 4-13 4 '-1 NRC Category ZI.a Equipment That Pully Satisfies All Applicable Requirements of the DOR Guidelines and Has a Service Life Less Than Plant Life. 4-13 4 '.2 NRC Category ZI.b Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines Provided That Specific Modifications Are Made. 4-14 4.3.3 NRC, Category II.c Equipment for Which Deviations From the DOR Guidelines Are Judged Acceptable 4-14 4.4 NRC Category ZZZ Equipment That Is Exempt From Qualification 4-15 4.5 Equipment for Which Documentation Contains Deviations Prom the Guidelines That Are Judged Unresolved. 4-16 4.5.1 NRC Category ZV.a Equipment. Which Has Qualification Testing Scheduled but Not Completed. 4-16

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TER-C5417-4 CONTENTS Section Ti tie ~Pa e 4.5.2 NRC Category IV.b Equipment for Which a Qualification Documentation in Accordance With the Guidelines Has Not Been Es tablished. 4-16 4.6 NRC Category V Equipment Which Is Unqualified.. 4-34 4.7 NRC Category VI Equipment for Which Qualification is Deferred 4-44 5 CONCLUS ZONS ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-1 6 REFERENCES ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-1 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS APPENDIX B EQUIPMENT ITEM TABLE APPENDZX C - SAFETY SYSTEMS FOR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED APPENDZ~ CABLE MANUFACTURERS LIST APPENDIX E - EQUIPMENT ITEM CROSS-REFERENCE l a ij

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TERM5 417-4

1. INTRODUCTION 1.1 PURPOSE OP THE REVIEW The NRC Office of Inspection and Enforcement (ZE) issued Bulletin 79-01B, "Environmental Qualification of Class 1E Equipraent" in January 1980. This Bulletin required the Licensee to perform a detailed evaluation of the environmental qualification of Class 1E electrical equipment required to function under postulated accident conditions and to submit a report on this action.

The objectives of the NRC Equipment Environmental Qualification Review program are to evaluate nuclear power plant safety-related electrical equipment in accordance with criteria 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 equipmerrt 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 submittals to determine if the Licensee reviewed its safety-related electrical equipment for environmental qualification in accordance with the DOR Guidelines and NUREG-0588 as required by ZE Bulletin 79-01B. The NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. Zf discrepancies are found, the audit will be extended.

l. 2 GENERIC ISSUE BACKGROUND Safety-related electrical equipment must be capable of performing design safety functions under all normal, abnormal, and accident conditions. Of particular concern is the assurance that equipment will remain operable during 00 Franklin Research Center A Dlvleion el The Fcenicrin lncecuce

TERM5 417-4 and following exposure to the harsh environmental conditions (i.e.,

temperature, pressure, humidity (steam), chemical sprays, radiation, and submergence) imposed as a result of a design basis accident. These harsh environments are generally defined by the limiting conditions resulting from the complete spectrum of postulated break sizes, break locations> and 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 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 the design of reactor systems has changed and as regulatory and operating experience has accumulated. Examples of such standards are IEEE Standards 279-71, 323-74, 383-74, 317-76, 334-74, 382-72, and 381-77. NRC NUREG documents 0413 and 0588 have been developed to address this topic. In particular, NUREG-0588 (published for comment in December 1979) formally presented the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment in the resolution of General Technical Activity A-24, "Qualification of Class lE Safety Related Equipment." The positions documented therein are applicable to plants that are or will be in the construction permit or operating license review process.

Although qualification standards and regulatory requirements have undergone considerable development, all of the currently operating nuclear power plants are required to comply with 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, maintenance, testing, and postulated accidents, including loss-of-coolant accidents."

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TERM5417-4 Zn addition, qualification requirements are also embodied in 10CFR50 Appendix A, General Design Criteria 1, 2, and 23 and Appendix 8, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Criteria III and XI. These requirements are applicable to safety-related equipment located inside as well as outside of containment.

The NRC staff has evaluated the Licensee's equipment qualification program by reviewing the qualification documentation of selected safety-related equipment as part of the operating license review for each plant. The NRC staff has also used a variety of methods to assure that these general requirements are met for electrical safety-related equipment. In the oldest plants, qualification was based on the fact that electrical components were of high industrial quality. After 1971, qualification was judged on the basis of IEEE 323-71; however, no regulatory guide was issued adopting the 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 respects adopted the most recent standard, ZEEE 323-74.

In 1977, the NBC staff instituted the Systematic Evaluation Program (SEP) to determine the degree to which the older operating nuclear plants deviated from current licensing criteria. The subject of electrical equipment environ>>

mental qualification (SEP Topic ZZZ-12) was selected for accelerated evalua-tion as part of this pLogram. Seismic qualification of equipment was to be addressed as a separate SEP topic. Zn December 1977, the NRC issued a generic letter to all SEP plant Licensees requesting that they initiate reviews to determine the adequacy of existing equipment qualification documentation.

Preliminary NRC review of Licensee responses led to the preparation of NUREG-0458, an interim NRC assessment of the environmental qualification of electrical equipment. This document concluded that "no significant safety deficiencies requiring immediate remedial actions were identified." However, it was recommended that additional effort should be devoted to examining the installation and environmental qualification documentation of specific electrical equipment in all operating reactors.

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TERM5 417-4 On May 31, 1978, the NRC Office of Inspection and Enforcement issued ZE 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 ZE 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 ZE 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. Zt became apparent that generic criteria were needed to evaluate the electrical equipment environmental qualification for both SEP and non-SEP operating plants. Therefore, during the second half of 1979, the Division of Operating Reactors (DOR) of the NRC issued internally a document entitled- "Guidelines for Evaluating Environmental Qualification of Class 1E 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.

Zn October 1979, the NRC awarded Franklin Research Center (FRC) a contract to provide assistance in the "Review and Evaluation of Licensing Actions for Operating Reactors," which included an assignment for review of equipment environmental qualification under SEP Topic ZII-12. FRC was given the assignment to review equipment environmental qualification documentation 1-4 It'll Franklin Research Center A Glvoion d lhe Fraetin Insotu(e

TER-C5417-4 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 ZE Bulletin 79-01 and requested additional information on environmental qualification of safety-related electrical equipment at opezating facilities, excluding the ll facilities undergoing the SEP review. This Bulletin stated that the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification are the DOR Guidelines. The scope of the review was expanded to include high energy line breaks (inside and outside containment) in addition to equipment aging and submergence. The NRC advised the Licensees that the criteria contained in the DOR Guidelines would be used in its review of Licensee submittals; problems arising from this review would be resolved using NUREG-0588 as a guide.

In early February 1980, the NRC decided that Indian Point Units 2 and 3 and Zion Units 1 and 2 should be included within SEP Topic IZZ-12 foz the purpose of equipment environmental qualification review.

On February 21, 1980, the NRC and representatives of the SEP Plant Owners Group held an open meeting at NRC headquarters to discuss an accelerated review program in accordance with the DOR screening guidelines. 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 [64)* which included a second document, "Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Zs To Be Addressed," [64]

together with the request that the Licensees zeview their plant systems and provide additional equipment environmental qualification information to the NRC on an accelerated schedule.

For non-SEP plants, the NRC Office of Inspection and Enforcement formed a task force including a principal reviewer in each region and a task leader from headquarters. The regional members are re'sponsible for the technical

• For References, see Section 6.

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TERMS 41 7-4 review of the Licensees'esponses to IE Bulletin 79-01B, and the task leader is responsible for the overall coordination of the review effort with NRC to assure overall consistency. The regional reviewers held meetings with the Licensees in their respective regions which-resulted in staff positions being, issued in a supplement to IE Bulletin 79-01B dated February 29, 1980.

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

On May 27, 1980, the NRC issued Memorandum and Order CLI-80-21r [67]

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 79-01B. FRC was given the assignment to evaluate the Licensee's equipment environmental qualification submittal and to present the results in the form of a Technical Evaluation Report for each plant.

1,3 SPECIFIC ISSUE BACKGROUND The staff held regional meetings with the Licensees and interested parties during the week of July 13, 1980 in various locations. The staff issued a second supplement to IE Bulletin 79-01B, a response to significant questions raised during the public meetings, and two Orders. The Order dated May 30, 1980 required the Licensees to comply with the previously issued Commission Memorandum and Order of May 27, 1980 (CLI-80-21) . The above Orders 1-6 ll0ll Franklin Research Center A Division ot The Frank)in Insame

TERM5417-4 required the Licensees to complete the tasks identified in IE Bulletin 79-01B no later than November 1, 1980 to allow the staff to comply with the February 1, 1981 date imposed by the Commission Order. The responses to the questions were issued on February 29< 1980; and the second and third supplements to IE Bulletin 79-01B, highlighting the staff positions affecting the October 24, 1980, respectively.

Licensees'esponses, were issued September 29 and 1.4 SCOPE OF THE REVIEW Environmental qualif ication 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 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 end (ii) radiation from fluids which are recirculated from inside containment to accomplish long-term cooling subsequent to an accident. Qualification aspects not included within the scope of this evaluation are:

~ seismic qualification

~ equipment protection against natural phenomena

~ equipment operational service conditions (e.g., vibration, voltage, and frequency deviations)

~ equipment located where it is sub)ect to outdoor environments

~ equipment protection against fire hazards

~ equipment protection against missiles.

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2. NnC CnI>rnIA ron ENVIIIONMF.NTAL QUALIF.ICATION

TERMS 417-4

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

~ "Guidelines for Evaluating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors" [64]

~ "Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Is To Be Addressed" [64]

~ NUREG-0588, "Interim Staff Position on Environmental Qualification of Saf ety-Related Electrical Equipment. " [69]

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

2~2 STAFF POSITIONS AND SUPPLEMENTAL CRITERIA The NRC identified the following staff positions and supplemental criteria to be used in conjunction with the referenced DOR screening guidelines.

2 '.1 SERVICE CONDITIONS INSIDE CONTAINMENT FOR A LOSS-OF-COOLANT ACCIDENT (DOR GUIDELINES SECTION 4.1)

For Pressurized Water Reactors (PWRs), the DOR Guidelines state that the containment temperature and pressure conditions as a function of time should be based on the most recent NRC-approved service conditions specified in the Final Safety Analysis Report (FSAR) or other Licensee documentation. In the specific case of pressure-suppression type containments, the following minimum high temperature conditions may be used: (1) Boiling Water Reactor (BWR)

Drywells 340'F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and (2) PWR Ice Condenser Lower Compartments 340'F for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. As stated in Supplement 2 to IE Bulletin 79-01B, [65]

"these values are a screening device, per the Guidelines, and can be used in 2-1 0(ill Franidin Research Center A Damson d The Fani4n Insatute

TER-C5 417-4 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 uncertainties. The 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 profiles were developed. The DOR Guidelines and NUREG-0588 provide guidance and considerations required to determine if the calculated plant-specific temperature/pressure profiles encompass the LOCA and HELB accidents inside containment.

2~ 2~ 2 SUBMERGENCE (DOR GUIDELINES SECTZON 4 1 g SUBITEM 3 and SECTION 4 ~ 3 ~ 2g 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

[65] provides the following additional criterion: If the equipment satisfies the guidance and other requirements of the DOR Guidelines or NUREG-0588 for the LOCA and HELB accidents, and the Licensee demonstrates that its failure will not adversely affect any safety-related function or mislead the operator after submergence, the equipment can be considered exempt from the submergence portion of the qualification requirements.

2~2 3 EQUIPMENT LOCATED IN AREAS NORMALLY MAINTAINED AT ROOM CONDITIONS (DOR GUIDELINES SECTION 4 ~ 3 ~ 3)

Supplement 2 of IE Bulletin 79-01B [65] permits deferment of the review of environmental qualification for all safety-related equipment items located in plant areas where the equipment is not exposed to the direct effects of a HELB or to nuclear radiation emanating from circulation of fluids containing radioactive substances. At the Licensee's option, the review may be deferred until after February 1, 1981.

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TERMS 417-4 By June 30, 1982, all safety-related electrical equipment potentially exposed to a harsh environment in nuclear generating stations licensed to operate on or before'une 30, 1982 shall be qualified to either the DOR Guidelines or NUREG-0588 (as applicable) . Safety-related electrical equipment is that required to bring the plant to a cold shutdown condition and to mitigate the consequences of the accident; It is the responsibility of the Licensee to evaluate the qualification of safety-related electrical equipment to function in environmental extremes not asscciated with accident conditions and to document it in a form that will be available for the NRC to audit.

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

2. 2. 4 SZMULATED SERVICE CONDZTZONS AND TEST DURATION (DOR GUIDELINES SECTION 5.2.1)

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

Supplement 2 to IE Bulletin 79-01B [65] provides the following additional criterion: "Equipment designed to perform its safety-related function within a short time into an event must be qualified for a period of at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in excess of the time assumed in the accident analysis. The staff has indicated that time is the most significant factor in terms of the margins required to provide an acceptable confidence level that a safety-related function will be completed. The 1-hour qualification requirement is based on the acceptance of a type test for a single unit and the spectrum of accidents (small and large breaks) bounded by the single test."

2.2.5 DEFERMENT OF QUALIFICATION REVIEW Supplement 3 to IE Bulletin 79-01B [66] permits the submittal of qualification documentation regarding the TMZ Action Plan equipment and the equipment required to achieve and maintain a cold shutdown condition to be delayed as follows:

a Qualification information for installed TMZ Action Plan equipment must be submitted by February 1, 1981.

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TER-CS 417-4

~ Qualification information for future TMI Action Plan equipment (reference NUREG-0737, when issued), which requires NRC pre-implementation review, must be submitted with the pre-implementation review data.

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

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

~ Qualification information for equipment required to achieve and maintain a cold shutdown condition should not be submitted later than February 1< 1981.

2 2.6 TEST SEQUENCE (DOR GUIDELINES SECTION 5. 2 ~ 3)

Supplement 2 to IE Bulletin 79-01B (65] provides the following additional criteria:

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

l. Zf the test has been completed without aging in sequence>

justification for such a deviation must be submitted.

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

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

2.2 7 RADIATION (DOR GUIDELINES SECTIONS 4.1.2, 4.2.2, and 4.3.2, SUBITEM 2)

Supplement 2 to IE Bulletin 79-01B [65] provides the following additional criteria:

"Both the DOR Guidelines and NUREG-0588 are similar in- that they provide the met:hods for determining the radiation source term when considering LOCA events inside containment (100% noble gases/50% iodine/1% partic-

.ulates) . These methods consider the radiation source term resulting from an event which completely depressurizes the primary system and releases the source term inventory to the containment.

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TERM5417-4 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 out:side containment as a result of LOCA. This method considers a LOCA event in which the primary system may not depressurize and the source term inventory remains in the coolant.

NUREG-0588 also provides the radiation source term to be used for qualifying equipment following non-LOCA events both inside and outside containment (10% noble gases/10% iodine/0% particulates) .

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

LOCA Non-LCCA HELB Outside Containment NUREG-0578 NUREG-0588 (100/50/1 (10/10/0 in RCS) in RCS)

Inside Containment ~Laz er or NUREG-0 588 NUREG-0588 (100/50/1 (10/10/0 in Containment) in RCS) or NUREG-0578 (100/50/1 in RCS)

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

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METHOOOLOG Y U.".l!O BY FAG

TER-C5 417-4 3 METHODOLOGY USED BY FRC IE Bulletin 79-01B required the Licensee to:

~ provide a master list which identifies the systems and electrical equipment required to function during and subsequent to an accident and to maintain the plant in a safe condition

~ provide the environmental service conditions

~ identify the submergence levels

~ provide written evidence of the qualification of the equipment identified

~ evaluate the qualification documentation using the DOR Guidelines and NUREG-0588

~ submit a Licensee Event Report (LER) for electrical equipment determined not to be environmentally qualified.

The requirements of ZE Bulletin 79-01B were requested under provisions of 10CFR50.54(f) > "Conditions of Licenses," which requires the Licensee to submit written statements, signed under oath or affirmation, to enable the Commission to determine whether or not a license should be modified, suspended, or revoked.

To provide assurance that the Licensee implemented the requirements of ZE Bulletin 79-01B and to provide a basis for the NRC Safety Evaluation Report (SER), FRC developed this Technical Evaluation Report (TER) by:

~ assessing the Licensee's responses in relation to the general requirements of the DOR Guidelines as augmented by the supplements to the 79-01B Bulletin

~ using NUREG-0588 to resolve open issues.

The results and conclusions contained in this report are valid assuming that the Licensee's analyses of test reports referenced in the Licensee submittal are correct. Review of test reports was not within the scope of FRC's assignment. However> the NRC staff will audit selected analyses and 3-1 llllll FranMin Research Center A Din~ ot The Frsnl4n Insomte

TERMS 417-4 test reports, incorporating the results of the reviews with the conclusions of the TERs, when developing the plant-specific SERs.

The Licensee, Tennessee Valley Authority, identified an extensive list of safety-related electrical equipment items in various locations of, the Browns Ferry Nuclear Power Station Unit 1 in its submittals to the NRC. FRC analyzed the Licensee's listing and grouped together all identical equipment items located within plant areas that are exposed to the same environmental service conditions. This analysis resulted in a reduced listing containing 140 different equipment items that formed the basis for the review. Appendix A contains the environmental service conditions for each location, Appendix B contains a tabulation of the equipment items and locations (the tabulation does not include equipment covered by the evaluation deferment described in Section 2.2.3 of this report), and Appendix C lists the plant systems identified by the Licensee and the NRC as being essential to safety.

Using the listing of safety-related electrical equipment items,* each equipment item was reviewed by FRC in relation to:

~ NRC DOR Guidelines, as modified by NRC staff interpretations

~ Licensee definition of harsh service environraents (Appendix A)

~ analysis and/or justification of qualification

~ Licensee-proposed remedies for qualification deficiencies.

Topics not within the scope of FRC evaluation are:

~ completeness of the Licensee's listing of safety-related equipment

~ acceptability of Licensee-provided environmental service conditions

~ acceptability of Licensee-stated position concerning safety system or component function

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

• In this report, the term "safety-related electrical equipment" refers to the'quipment defined by the two NRC Guidelines referenced in Section 2.1.

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TER-CS 417-4 Upon completion of the final review for each equipment item, FRC developed an overall evaluation of the component and a specific conclusion with respect to its qualification. Based on the FRC conclusion, each equipment item was assigned to one of the generic qualification categories provided by the NRC. NRC categories are described below.

All equipment item numbers discussed in Section 4 of this report are associated with Reference 68.

The NRC Office of Inspection and Enforcement conducted an on-site verification inspection of selected lE equipment to verify proper installation of equipment, overall interface integrity, location with respect to flood level for equipment inside the containment, and manufacturer's nameplate data. The manufacturer and model number from the nameplate data were compared to information given in the System Component Evaluation Work Sheets (SCEWS) of the Licensee's report. The details of this site inpection are documented in the ZE Inspection Report Number 50-259/80-41 and will be addressed by the NRC.

NRC QUALIFICATION CATEGORIES AND DEFINITIONS

~ NRC Category Z.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES This category includes equipment items which are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment has been found to be qualified for the life of the plant.

~ NRC Category I.b EQUIPMENT FOR WHICH DEVIATIONS FROM 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, sufficient information has been presented to determine that the specific deviations are acceptable.

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TERM5 417-4

~ NRC Category IZ.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUZREMENTS OF THE DOR GUIDELXNES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE This category includes equipment items that are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life.

~ NRC Category II.b EQUXPMENT THAT FULZY SATISFIES ALL APPLICABLE REQUXREMENTS OF THE DOR GUIDELINES PROVIDED THAT SPECIFIC MODIFICATIONS ARE MADE This category includes equipment items which will be fully acceptable and will satisfy all.applicable criteria defined in the DOR Guidelines provided that specific modifications are made on or before th'e designated date. When the modifications are complete, the equipment can be considered qualified.

~ NRC Category ZI.c EQUIPMENT FOR WHICH DEVIATIONS FROM 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 the specific deviations are judged by FRC to be acceptable for less than plant 0

life based on review of the applicable qualification documentation associated with the general equipment environmental qualification program.

~ NRC Category ZII EQUIPMENT THAT IS EXEMPT FROM QUALIFICATION 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), (i.i) the specific safety-related function of the component can be accomplished by some other designated component which is fully qualified, or (iii) the equipment is not subject to a potentially adverse environment as a result of accidents for which proper operation of the equipment is -required. In addition, any failure of the exempt component must not degrade the ability of a qualified component to perform its required safety<<related function.

~ NRC Category IV.a EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPXETED The qualification of equipment items in this category has been judged deficient or inadequate based upon review of the documentation provided by the Licensee. However, the Licensee has stated that the equipment item is 3-4 Ij AFranklinot Research CNnrron Center The Frank5n rnaarure

TERM5 417-4 scheduled to be tested by a designated date. The results of the testing will dictate the specific qualification category of the equipment item. Specific justification for interim plant operation prior to testing should be provided for each item.

~ NRC Category IV.b EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION ZN ACCORDANCE WITH THE GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of equipment items in this category is deficient or inconclusive based upon review of the documentation provided by the Licensee.

This equipment is judged to have a high likelihood of operability for the specified environmental service conditions; however, complete and auditable records reflecting comprehensive qualification documentation have not been made available for review. Specific justification for interim plant operation should be provided for each item.

~ NRC Category V EQUIPMENT WHICH IS UNQUALIFIED The DOR Guidelines require that complete and auditable records reflecting a comprehensive qualification methodology and program be referenced and made available for review of l

all Class 1E equipment.

The qualification of equipment items in this category has been judged to be deficient or inadequate, based upon review of the documentation provided by the Licensee. The extent to which the equipment items fail to satisfy the criteria of the 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 available for review is inadequate, or (iii) the documentation indicates that the equipment item has not passed the required tests.

~ NRC Category VI EQUIPHENT FOR WHICH QUALIFICATION ZS DEFERRED This category includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittals; however, the qualification review of this equipment has been deferred by the NRC in accordance with criteria presented in Sections 2.2.3 and 2.2.5 of this report.

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l I

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S. TECIINICAL EVALUATION

TER-C5417-4 4~ TECHNICAL EVALUATION 4.1 METHODOLOGY USED BY THE LICENSEE The Licensee has submitted for Browns Perry Units 1, 2, and 3 a rather voluminous equipment environmental qualification report (20 large volumes in total) dated October 31, 1980, in response to the January 14, 1980 NRC IE Bulletin-79-01B and Memorandum and Order CLI-80-21 dated May 23, 1980. All previous responses to IE Bulletin 79-01B (April 30 and July 18, 1980) are said to be superseded by this latest submittal. The final submittal (68] contained a general introductory section which described the Licensee's basic approach to qualification and evaluation methodology. A review by PRC has generated the following observations and comments.

4.F 1 COMPLETENESS OF EQUIPMENT LIST The Licensee discussed the approach used in selecting the equipment for which qualification must be demonstrated. For example, the Licensee stated:

~ As directed, TVA has evaluated the environmental qualification of the safety-related electrical components which experience the harsh environment due to Loss of Coolant Accidents (LOCA's) and High Energy Line Break (HELB) accidents. Only that equipment either required to function for accident mitigation (Category a, as defined in NUREG-0588, Appendix E) or required not to fail (Category b, as defined in NUREG-0588, Appendix E) during accident mitigation, including those required for cold shutdown, are contained in this report.

e The Evaluation Work Sheets (EWS) in Appendix C [68] and their supporting appendices provide documentation of qualification as defined by the DOR Guidelines.

~ Browns Perry Nuclear Emergency Operating Instructions were also used to identify safety functions, safety systems, and components.

~ If a safety-related component's location in the plant was found to be outside the harsh areas, the item was deleted from the equipment list Illl FranMin Research Center 4-1 A Division oi The FnsnsSn Insonne

TERMS 417-4 (although it still is required to be qualified for its nonaccident service environments) . Before an item could be deleted, all associated items, especially cabling, were identified and their locations reviewed against the harsh areas. This assured that input and output associated with the original item was fully reviewed for qualification.

FRC notes that IE Bulletin 79-01B Supplement 2 requires that qualification documentation for all operating reactors (as of May 23, 1980) be evaluated using the DOR Guidelines. Nhen sufficient detail is not provided by the DOR Guidelines, NUREG-0588 Category IZ can be used. 1n addition, criteria to be used for. evaluation of replacement components for these plants will be derived using NUREG-0588 Category I. NUREG-0588 Category I criteria will be applied to documentation associated with reactor facilities whose construction permit safety evaluation reports were issued after July 1, 1974. For facilities whose construction permits were issued prior to July 1, 1974, NUREG-0588 Category II will be applied. (NUREG-0588 Categories I and ZZ refer to applicable criteria referenced to ZEEE Standards 323-1974 and 1971<

respectively.)

PRC notes that the DOR Guidelines require the Licensee to review its emergency operating procedures to determine the electrical components needed or relied upon to perform safety functions or provide safety-related display information to the operator. PRC concludes that the Licensee methodology for identification, of safety-related equipment is consistent with NRC requirements.

4 1~2 DEFINITION OP EQUIPMENT OPERATING TIME REQUIREMENTS The Licensee has defined the equipment operating time as follows:

Operating time was defined as the time period during which a component must be available to perform its function. Zt was not considered to be the time actually required to perform an action (i.e., actual time required for a valve to close) .

An operating tirae category was defined as specified time period starting at the accident initiation during which a component must be available to perform its function. This specified time period was given sufficient scope to incorporate all reasonable operating times required for the components in the category.

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TERMS 417-4 The following operating time categories were used:

W One hour following accident initiation X One day following accident initiation Y Thirty days following accident initiation Z One year following accident initiation W-Z Items marked as "W-Z" are components that fit into operating category A for the first hour following accident initiation and then fit into operating category B for the duration of the event and recovery (taken to be one year for this report) . Isolation valves fall into this situation. They are required to close and then to remain closed.

X-Z Items marked as "X-Z" are components that fit into operating category A for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and then fit into operating category B for the year following the accident.

Y-Z Items marked as "Y-Z" are components that fit into operating category A for the first 30 days and then fit into operating category B for the remainder of the year following the accident.

Operating time categories were assigned based upon the review of components'unctions. For components that perform multiple functions, each function was considered and the worst-case time requirement used for the components. General functions were defined as having the following operating times categories:

W & W-Z Primary and secondry containment isolation (including SCIS initiation) folowing a LOCA or HELB inside primary containment; isolation for a HELB outside primary containment (i.e., the specific line that breaks); scram initiation (RPS), and scram following a LOCA or HELB inside primary containment or a HELB in the main steam line valve vault.

X a X-Z - Primary and secondary containment isolation for HELB's outside primary containment (except for the line broken);

scram initiation (RPS) and scram for HELB's outside primary containment (except for a main stream line break in the valve vault) .

Y a Y-Z - High Pressure ECCS Z - All other functions 4-3

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TERM5417-4 PRC EVALUATIONS FRC concludes that the Licensee's approach to operating time is acceptable.

4 1 3 QUALIFIED LIFE The Licensee has not adequately addressed the topic of qualified life for any of the safety-related equipment identified by the, Licensee as essential for safe shutdown of the plant. The DOR Guidelines required that equipment with components susceptible to degradation caused by thermal or radiation environmental conditions are to have an established qualified life.

The Licensee should maintain detailed maintenance records to demonstrate that those components which can be degraded are replaced on a scheduled basis in order to restore the equipment and minimize the likelihood of equipment failure to perform a safety-related function.

Qualified life is the maximum period of normal service under specified conditions for which it can be demonstrated that the functional capability of the equipment at the end of the period is still adequate for it to perform its specified safety function for an applicable accident and to remain functional as long as required after the accident. The qualified life may depend on-carrying out a specificed maintenance program. The qualified life of some elements of an equipment assembly may be less than the qualified life of the assembly provided a program for replacement of such elements at intervals not exceeding their qualified lifetimes is specified and fulfilled. The qualified life of.a particular equipment item may be changed during its installed life where justified by new information that permits a reanalysis of the qualification program.

It is necessary to establish a qualified life for every type of safety-related equipment that requires environmental qualification. A conservative choice of qualified life must be made to account for the assumptions and approximations made in the qualification program.

A

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TER-C5417-4 The Licensee stated:

At the time of procurement of the equipment, documented evidence of aging effects was not a requirement; however, TVA intends to meet the

~ ~

DOR Guidelines in Section 7.0. If the equipment contains material subject to aging degradation (the guidelines require that this determination be made), an analysis was done to determine the maintenance or change out interval. When there was insufficient documentation to determine the thermal or radiation aging effects on a piece of equipment, a program of either further analysis of materials (when a detailed list of materials is obtained), or type testing was instituted. If neither of these options were available, a replacement or relocation plan was established. In general, the procureraent specification required equipment whose intended, service, determined either by repairs or replacements, was for the design life of the plant for 40 years; therefore, in our engineering judgment the device will be able to perform its safety function in the interim time period required for completely documenting qualificat:ion.

PRC notes that the salient points of the Licensee's methodology are:

e If equipment contains materials subject to aging degradation an analysis was conducted to determine the maintenance or change out inter va1.

~ When insufficient documentation existed to allow determination of aging effects, an analysis program or type testing was instituted.

~ An equipment replacement or relocation program was established in lieu of analysis or type where appropriate.

~ Procurement specifications required 40 years design life; therefore, the equipment will be able to perform safety functions in this interim period while complete documentation is being completed.

FRC concludes (i) that the procurement specifications requiring a 40-year design life provide absolutely no assurance that the degradation effects due to aging-related s'tresses on equipment have been reduced, accounted for, or eliminated and (ii) that the Licensee's basic approach to aging is acceptable; however, PRC has found no substantive evidence of the use of the stated methodology and the subsequent Licensee conclusions and action relative to the actual evaluation of the individual equipment items in the EWS data.

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TER-C5417-4 4.1.4 LICENSEE EVENT REPORTS (LER)

The Licensee has stated:

Item 6 of the bulletin required that "Licenses Event Reports" (LER) be issued when a component is found not capable of performing its intended safety function. Section 5.2 of the report orovides a Summary of Equipment Qualification Status which included the LER number issued when the above determination has been made.

FRC notes, however, that the Licensee has left the LER column blank in Section 5.2 of the report. It is not clear whether there are no LERs or the Licensee has not completed their listing.

4.1.5 LICENSEE'S GENERIC POSITIONS WITH RESPECT TO THE DOR GUIDELINES A. MARGIN The Licensee states:

In Section 6.0 of the DOR guidelines it is stated that margin only applies to type testing and that the guidelines in Section 4.0 for establishing service conditions include conservatisms which assure margins between the service conditions specificed and the actual conditions which could realistically be expected in a design basis event. Based upon the above statements and the fact that all calculations for establishing service conditions meet or exceed the DOR Guidelines given in Section 4.0, no additional margin was considered for qualification by analysis. As stated in DOR Guidelines, Section 6.0, additional margin for the service conditions for type testing needs to be considered only if Section 4.0 and Section 5.2 of the DOR Guidelines are not met; since the guidelines of Section 4.0 are met, margin was considered only if Section 5.2 was not met.

FRC concludes that this position is acceptable.

B~ ACCURACY The Licensee states:

As stated in Enclosure 3 to IE Bulletin 79-01B, specificed and demonstrated accuracies of all instruments for their trip functions and/or post-accident requirement must be provided. When the documentation did not clearly demonstrate the specified accuracy during the environmental extremes resulting from a DBE, a program of either further search for documentation that address accuracy or t! II!l Frankiin Research Center 4-6 A bbnsion ef %he FnuASn Insutute

TER-C5417-4 type testing was instituted. In our engineering judgement, the following two statements provide justification for continued operation during the interim time period required to obtain completely documented qualifications: (1) in general, the procurement specifications required and the vendor's demonstrated accuracies are much more stringent than system requirements, (2) surveillance tests are conducted periodly as required by the technical specifications to confirm the validity of the manufacturer's stated accuracy.

FRC concludes that the Licensee's position is acceptable for interim operation until full qualification can be obtained.

C OPERATING DATA The Licensee states:

Substantial percentages of the systems components installed in plant locations other than inside primary containment, have well established industrial rating at or above the limits required for operation during and/or after the required DBE's. In cases where operating data is used as a justification for interim qualification. This qualification will be supplemented at a later date by either type testing and/or further analysis. If neither of these options are available, a replacement plant was instituted.

FRC notes that NRC required a definitive resolution by November 1980 from the Licensee on all qualification issues.

The Licensee's position is in variance with this requirement.

D RELATIVE HUMIDITY The Licensee states:

The humidity ranges from 30 to 80 percent for areas outside primary containment. The values given in Section 3.0, Table 1, note E of this report are peak values and probability of occurence is extremely low. There are redundant fans servicing areas where there is essential equipment. Most industrial grade electrical equipment can function properly in the reactor zone building ambient humidity.

FRC concludes that this generic position is (i) not clear and (ii) does not alleviate the need for humidity to be addressed by the Licensee as an environmental service condition.

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TER-C5417-4 E. TYPE TESTING The Licensee states:

In Section 5.1 of the DOR Guidelines, type testing is preferred but not required for equipment subjected to severe temperature, pressure, and steam service condition. However, analysis is acceptable if supported by test data, for the other service conditions. At the time of equipment procurement, type testing was not a required method of proving qualification. To the extent that an analysis is not conclusive to verify qualification per the DOR guidelines, a type testing program or a replacement plan was initiated. TVA will provide justification for the interim operation until adequate qualification information is available to meet the DOR Guidelines.

FRC notes that the DOR Guidelines state:

Type Testing is the preferred method of qualification for electrical equipment located inside containment required to mitigate the consequences of design basis events, i.e., Class IE equipment (see Section 3.0 above). As a minimum, the qualification for severe temperature, pressure, and steara service conditions for Class IE equipment should be based on type testing. Qualification for other service conditions such as radiation and chemical sprays may be by analysis (evalaution) supported by test data.

FRC concludes that type testing is required, and that the Licensee's generic position regarding analysis and fux'ther search for qualification documentation is not in accordance with NRC requirements.

F. RADIATION The Licensee states:

~ Beta Radiation According to Section 4.1 of the DOR Guidelines, beta radiation has low penetrating power in comparison to gamma rays of equivalent energy. Of the genexal classes of electrical equipment in the plant containment (e.g., cables, instrument transmitters, valve operators, containment penetrations) r electrical cable is considered the most vulnex'able to damage from beta radiation. For other equipment whose enclosure provides adequat:e shielding, beta radiation need not be considered. For any equipment that is determined unshielded (e.g., cable) or is shielded by sheet metal of 20 gauge or less, an analysis of the qualification of the equipment related to beta radiation was included as attachments to the EWS's.

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TER-C5417-4

~ Gamma Radiation - From Table C-1 in Appendix C in the DOR Guidelines and reference 1 and 2 below, there is substantial test data available to demonstrate that most conventional material used in electrical equipment has a gamma radiation threshold exceeding 10 rads; the exception is solid-state devices containing N-MOS integrated circuits which have a threshold of 10 rads (see Table C-1) . Teflon has a threshold for'amage of approximately 3.5 x 10 rads (for 20 percent decreases in elongation) . Electrical properties (e.g., resistivity) of these materials are sufficiently conserative initially, such that substantial changes can be tolerated without causing equipment failures or malfunction.

Threshold is defined from the above referenced table as the radiation exposure required to change at least one physical property of the material. The threshold is not a point of failure or end of useful life, therefore, there is a band of tolerance from the threshold point to the failure point which may vary by an order of magnitude or more.

On the above basis and the existing test data, it necessary to perform qualifications test or analysis on electrical is not considered equipment for radiation of less than 104 rads which degrade the safety function of the equipment.

FRC agrees with the Licensee's position.

4. l. 6 REQUIRED SIGNATURES The Licensee has stated:

~ To ensure completeness and accuracy of the EWS signatures of a preparer, reviewer, and quality assurance engineer are required on each of the EWS. Any appendixes for which the preparer or reviewer of EWS was not directly responsible will also contain preparer and reviewer signatures.

~ The most significant changes to the EWS were as follows: 1) use of appendixes, 2) use of permanent notes, 3) required signatures, and 4) use of unique numbering system for the EWS and their appendixes.

FRC notes that none of the sheets appears to be signed by a quality assurance engineer.

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TERM5417-4 4.1.7 CHEMICAL SPRAY The Licensee states:

Chemical spray is not applicable for this report since no chemical injection is used. (This is a permanent note N/A on all EWS sheets.)

FRC notes that the DOR Guidelines require demineralized water sprays to be addressed. In addition, the effects of in-leakage must be considered. The Licensee has not complied with this requirement.

4.1,8 DESCRIPTION OF QUALIFICATION/REPLACEMENT PLAN The Licensee states:

It is TVA's intention to comply fully with the requirements of Bulletin 79-01B. This section addresses the requirements stated in item 4 of the bulletin for "outstanding items." It is not possible to submit a detailed qualification/replacement plan at this time.

The following items have a great impact on our inability to supply a detailed schedule at this time:

a. Limitations on industry's capability for testing large numbers of components.

b. Availability of qualified replacement equipment.

c. Unit outage schedules.

TVA has a contract with Wyle Laboratories to do any testing that is required to prove qualification of any questionable equipment. Wyle will also provide TVA a detailed schedule of all tests they plan to conduct for TVA.

When we receive schedules of testing from Wyle Lab, we will inform the NRC as stated in your letter dated October 1, 1980, from D. G. Eisenhut to licensees of operating plants. TVA will make a best faith effort to test equipment as soon as possible. However, if problems are encountered with either the testing or qualificability of the equipment, the justification for continued operation will be reviewed as well as a safety review. Zt is our plan to schedule first the items that have the greatest impact on safety.

The qualification status of all equipment is listed in Table 5.2. The status of all items falls into one of four categories as listed below.

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TER-C5417-4 Category I- Components qualified to DOR guidelines.

Category II - Components for which analysis indicating qualification but that lack documentation to prove qualification to DOR quidelines.

Category III - Items that will be qualified by either analysis or type testing or a combination of these methods.

Category IV Equipment to be replaced.

For Category IV equipment checks were made to determine the availability of qualified equipment on the market. In general, even if qualified equipment is available the delivery has a long and indefinite lead time.

TVA will submit a detailed schedule for qualifying or replacing all open items by February 1, 1981. This schedule will be developed in conjunction with Wyle Labs.

FRC concludes that the Licensee has not complied with the NRC requirement that the Licensee must submit all qualification information to NRC by November 1, 1980. With this information, an exact schedule for equipment replacement and specific justification for interim operation must be provided for any item which does not conform to Guidelines requirements.

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TERM5417-4 4.2 EQUIPMENT QUALIFIED FOR PLANT LIFE This section includes equipment items which are fully acceptable on the basis that (i) all criteria defined in Section 2 of the report are satisfied or (ii) sufficient data exist to determine acceptability by judgment.

4.2.1 NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIRElKNTS OF THE DOR GUIDELINES This section normally includes equipment items which are fully acceptable 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 Browns Ferry Unit 1, no equipment items fall into this category.

4.2.2 NRC Category I.b EQUIPMENT FOR WHICH DEVIATIONS FROM THE DOR GUIDELINES ARE JUDGED ACCEPTABLE This section normally includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelines; however, sufficient information has been presented to determine that the specific deviations are acceptable. For Browns Ferry Unit 1, no equipment items fall into this category.

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TERM5417-4 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 equipraent is qualified for a time interval less than plant life, or (iii) the equipment 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 GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE The following equipment items are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life.

4.3.1.1 Equipment Item No. 26 Solenoid Valve Target Rock Model 73FF-005 (Licensee Reference 34)

The Licensee has shown that this equipment is qualified to function in a post-accident environment, and that the equipment is qualified for a specific time interval less than plant life.

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TER-C5417-4 4.3.1.2 Equipment Item No. 136 Electrical Penetration GE Model NS04 (Licensee Reference 23)

The Licensee has provided documentation that shows this equipment is qualified to function in a post-accident environment, and that it is qualified for a time interval less than plant life.

4.3.1.3 Equipment Item No. 138 Electrial Penetration Assembly Physical Sciences Corp. Model PSC P/N 2022C (Licensee Reference 21)

The Licensee has provided documentation that shows this equipment to be unqualified in the area of aging effects and qualified for a specfic time interval less than plant life.

4.3.2 NRC Category ZI.b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES PROVIDED THAT SPECIFIC MODIFICATIONS ARE MADE 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 completed, the equipment can be considered qualified. For Browns Ferry Unit 1, no equipment items fall into this category.

4.3.'3 NRC Category II.c EQUIPMENT FOR WHICH DEVIATIONS FROM THE DOR GUIDELINES ARE JUDGED ACCEPTABLE This section 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 the specific deviations are judged by FRC to be acceptable for less than plant, life based on review of other applicable qualification documentation associated with the general equipment environmental qualification program.

For Browns Ferry Unit 1, no equipment items fall into this category.

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TER-C5417-4

4. 4 NRC Category III EQUIPMENT THAT IS EXEMPT FROM QUALIFICATION The equipment items in this cateogory 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 component can be accomplished by some other designated component which is fully qualified, or (iii) the equipment is not subjected to a potentially adverse environment as a result of accidents for which proper operation of the equipment is required.

In addition, any failure of the exempt component must not degrade the ability of a qualified component to perform its required safety-related function. For Browns Ferry Unit 1, no equipment items fall in this cateory.

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TER-C5417-4 4.5 EQUIPMENT FOR WHICH DOCUMENTATION CONTAINS DEVIATIONS FROM THE GUIDELINES THAT ARE JUDGED UNRESOLVED 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 EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLETED The qualification of equipment items in this category has been judged deficient or inadequate based upon review of the documentation provided by the Licensee. However, the Licensee has stated that the equipment item 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 justification for interim plant operation prior to testing should be provided for each item. For Browns Perry Unit 1, no equipment items fall in this category.

4.5.2 NRC Category IV.b EQUIPMENT POR WHICH QUALIPICATION DOCUMENTATION IN ACCORDANCE WITH.,

THE GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of the following equipment items is deficient or inconclusive based upon PRC's review of the documentation provided by the Licensee. This equipment is judged to have a high likelihood of operability for the specified environmental service conditions; however, complete and auditable records reflecting comprehensive qualification documentation has not been made available for review. Specific justification for interim plant operation should be provided for each item.

4-16 0

(Ij Franklin Research Center A Division of The frank5n Inseam

TERM5417-4 4.5.2.1 Equipment Item Nos. 1 and 2 Solenoid Valves 1: Atkomatic Model 15830WP-VPI.

2: AAA Model S02 (Licensee reference not cited)

The Licensee has not provided qualification information for this equipment item and requests permission for continued use of the solenoid valve based on the contention that similar solenoid-operated valves have successfully operated in the environment specified for this equipment item. The Licensee will type test this item or replace it with qualified equipment during the next refueling outage.

4.5.2.2 Equipment Item No. 3 Flow Indicating Switch Fischer & Porter Model 10A2235A-55AR1011 (Licensee reference not cited)

This equipment item has not been qualifiedr but the manufacturer's specifications indicate that this type switch has been tested and found to operate successfully at temperatures of 250'F and atmospheric pressure. TVA states that it will type test or replace this equipment (no date specified).

4.5.2.3 Equipment Item No. 4 Differential Pressure Switch Dwyer Model 3302 (Licensee reference not cited)

This equipment item has not been qualified to operate in a post-accident environment. The Licensee will replace this item with qualified equipment during the next refueling outage that follows delivery of qualified equipment.

4.5.2.4 Equipment Item No. 5 Solenoid Valve ASCO Model HB830281RU (Licensee reference not cited)

The Licensee failed to submit qualification documentation for this equipment item, but bases justification for continued operation on tests of similar valves from the same manufacturer. The Licensee will type test this item or replace it with qualified equipment during the next refueling outage.

000 Franklin Research Center 4-17 h Cfrrrron of 'The Frenrdfn Ineorore

TER-C5417-4 4.5.2.5 Equipment Item No. 6 Pressure Differential Modifier Honeywell Model: Relay Assembly R7165-1078 Terminal Assembly 122700 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification information for this equipment item, but will type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.6 Equipment Item No. 7 Pressure Differential Indicating Controller Pischer & Porter Model 53EL3311BB1B ESL-01 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification information for this equipment, but will type test the device or replace it with qualified equipment during the next refueling outage.

4.5.2.7 Equipment Item No. 8 Pressure Differential Transmitter Pischer & Porter Model 10B2494TBAB (Licensee Reference 62)

The Licensee has provided documentation that shows this item to be qualified for radiation dose after an accident. Other environmental conditions have not been evaluated, however, and the Licensee will either type test this equipment or replace it with a qualified device during the next refueling outage.

4.5.2.8 Equipment Item Nos. 9 and 10 Temperature Element Weed Model SP6011AA3C275SN42 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation for these equipment items, but will type test the items or replace them with qualified equipment during the next refueling outage.

III)ll FranM!n Research Center 4-18 A 0%sion of The FrankSn Insotuie

TER-C5417-4 4.5.2.9 Equipment Item Nos. 11, 12, and 14 Solenoid Valve ASCO Models HB830081RU, HV200-924-1P, and HT8262A203A (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation for this item, but will either type test this item or replace it with qualified equipment during the next refueling outage.

4.5.2.10 Equipment Item No. 13 Plow Transmitter GE/MAC Model 50-554212BKZZ3 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation, but will either type test this item or replace it with qualified equipment during the next refueling outage.

4.5.2.11 Equipment Item No. 15 Solenoid Valve ASCO Model HT8262A203A (Licensee reference not cited)

The Licensee states that qualification documentation is unnecessary for this equipment since the system will be replaced during the next refueling outage.

4.5.2.12 Equipment Item No. 16 Pressure Transmitter Bailey Model 551 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation for this equipment and will either type test this item or replace it during the next refueling outage.

I)( Franklin Research Center 4-19 A johnson af The Frank5n Institute

TER-C5417-4 4.5.2.13 Equipment Item'No. 17 Plow Transmitter GE/MAC Model 555 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.14 Equipment Item No. 18 Temperature Switch Penwal Model 18002-27 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.15 Equipment Item No. 19 Solenoid Valve ASCO Model HTX8300B61U (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5. 2. 16 Equipment Item No. 20 Solenoid Valve ASCO Model 8300C61U (Licensee reference not cited)

The Licensee has failed to submit sufficient qualification documentation for this equipment and does not state the intention to replace or type test it.

Ijll Franklin Research Center 4-20 A DMsion ol The Frech5n lruotu(e

TER-C5417-4 4.5.2.17 Equipment Item No. 21 Solenoid Valve ASCO Model HTX8300C61U (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.18 Equipment Item No. 25 Solenoid Valve ASCO Model HB830081RP (Licensee reference not cited)

The Licensee has failed to submit sufficient qualification documentation for this equipment and does not state the intention to replace or type test it.

4.5.2.19 Equipment Item No. 27 Solenoid Valve ASCO Model T8210C87 (Licensee reference not cited)

The Licensee has failed to submit sufficient qualification documentation for this equipment and does not state the intention to replace or type test it.

4.5.2.20 Equipment Item No. 28 Solenoid Valve ASCO Model HT8211C94 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

I) I) Franklin Research Center 4-21 h Dhttion ol The Ftenttmn tneotttte

TERM5 4 17-4 4.5.2.21 Equipment Item No. 29 Indicator Pressure Converter Fisher Controls Model 546 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage..

4.5.2.22 Equipment Item No. 30 Pressure Switch Custom Components Model 630GH (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item wilL successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.23 Equipment Item No. 31 Solenoid Valve ASCO Model NPHT8316E36 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.24 Equipment Item Nos. 33 and 35 Thermostat Honeywell Models T675A1508 and T675A1540 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage, by June 1982.

0 (lj FranMin Research Center 4-22 A Otntion ot The FtenkSn Intatote

TERM5417-4 4.5.2.25 Equipment Item No..34 Damper Motor Honeywell Model M445A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage, by June 1982.

4.5.2.26 Equipment Item Nos. 39 and 40 Motor GE Models 5K6226XJ3000A and 5K4254XL2 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this itera will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2. 27 Equipment I tern No. 51 Level Indicator Switch Yarway Model 4418C (Licensee Reference 46)

The Licensee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee will retest this equipment.

4.5.2.28 Equipment Item No. 56 Temperature Element Calmatic Model 158B7061P016 (Licensee reference not cited)

The I icensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment, and states that they will either type test or replace it with qualified equipment during the next refueling outage.

00 FranMln Research Center 4-23 A Otvisicn of Thc Frank5n tnsatutc

TERM5417-4 4.5.2.29 Equipment Item Nos. 61 and 62 Plow Transmitter GE/MAC Model 50-555111BOAA3AAA (Licensee reference not cited) .

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.30" Equipment Item No. 67 Limit Switch Micro Switch Models OPD-AR and OPD-AR30 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.31 Equipment Item No. 69 Temperature Switch Fenwal Model 40-104014-103 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item'will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.32 Equipment Item No. 70 Temperature Element Penwal Model 28-232106-304 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

(I) Franidin Research Center 4-24 A Dhisen d The Frssldin hsaanc

TER-C5417-4 The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.33 Equipment Item No. 76 Limit Switches NAMCO Model D1200G (Licensee reference not cited)

The Licensee has failed to obtain qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.34 Equipment Item No. 79 Pressure Transmitter GE/MAC Model Series 50 and 55 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.5.2.35 Equipment Item No. 80 Power Supply GE Models 570012FAAC1 and 583001AAGKl (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

4.5.2.36 Equipment Item No. 82 Temperature Element American Standard Model 158B7079P051 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee will either type test the item or replace it with qualified equipment.

llllll FranMin Research Center 4-25 A Dtnnon of The FrenCn huaone

TERM5417-4 4.5.2.37 Equipment Item Nos. 88 and 89 Temperature Element Scam Model S51-1 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post>>accident environment.

The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.38 Equipment Item Nos. 93 and 99 Turbine Control Valve Terry Turbines Types GS and CCS (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

4.5.2.39 Equipment Item No. 95 Pressure Switch Mercoid Models DA-7043-804 and DA-23-804 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.40 Equipment Item No. 97 Square Root Converter GE Model 565100AAACl (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee will either type test the item or replace it with qualified equipment.

(Il Franklin Research Center 4-26 A Olvision ot The Frsnk5n lnsatute

TER-C5417-4 4.5.2.41 Equipment Item No. 102 Level Switch Robertshaw Model SL-202-A2X (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.42 Equipment Item No. 108 Pump Motor GE Model SK6348XC23A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will perform further tests to verify qualification of this equipment.

4.5.2.43 Equipment Item No. 110 Pump Motor GE Model SK6336XC198A (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation to show that this item will successfully function in a post-accident environment, and states that further evaluation is necessary to determine qualification of this equipment item.

4.5.2.44 Equipment Item No. 112 Hydrogen Element GE Model 47E226428G2 (Licensee reference not cited)

The Licensee has failed to provide sufficient qualification documentation to show that this item will successfully function in a post-accident environment, and states that further evaluation is necessary to determine qualification of this equipment item.

()Il Franklin Research Center 4-27 A(&zen d The frena5n Insatiate

TER-C5417-4 0 4.5.2.45 Equipment Item No. 113 Level Switch GEMS Model XH-36425 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2. 46 Equipment Item No. 114 Solenoid Valve Versa Model VSG-3521 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.47 Equipment Item No. 115 I imit Switch Micro Switch Model BZE6-2RN (Licensee reference not cited)

The Licensee has failed to provide qualificat:ion documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.48 Equipment Item No. 116 Level Switch Autocon Model M-4 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

ll(l FranMin Research Center 4-28 A Division ol The Frentdtn Instrtute

TER-C5417-4 4.5.2.49 Equipment Item No. 117 Temperature Element Thermo-Elect Model B7582-1 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.50 Equipment Item No. 118 Level 'Switch Meletron Model 9241-6SS10A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.51 Equipment Item No. 120 Solenoid Valve ASCO Model HVA86-030 (Licensee reference not citied)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.52 Equipment Item No. 121 Position Switch Micro Switch Model BZE6-2RN (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

00 Franklin Research Center 4-29 A Oiivi4on of The Fronton hsaete

TER-C5 417-4 4.5.2.53 Equipment Item No. 122 CRD Scram Inlet Valve ASCO Model HVA-90-405-2A (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test-the item or replace it with qualified equipment.

4.5.2.54 Equipment Item No. 123 Level Switch Robertshaw Model SL-305-E3-X (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.55 Equipment Item No. 124 Ion Chamber GE Model 237X731G001 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test or replace it with qualified equipment.

4.5.2.56 Equipment Item No. 125 Sensor and Converter GE Model 194X927G014,12 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test or replace it with qualified equipment.

ill 4-30 ull Franklin Research Center A Dinsen d The Frank5n Insoate

TER-C5417-4 4.5.2.57 Equipment Item No. 126 Fission Product Monitor GE Model Number Not Stated (License reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.58 Equipment Item No. 127 TIP System Valve Assembly GE Model 136B1302G2 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

4.5.2.59 Equipment Item No. 128 Motor Control Center International Switchboard Corp., Model Number Not Stated (Licensse reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee is pursuing the acquisition of the appropriate qualification 1

information.

4.5.2.60 Equipment Item No. 129 Motor Control Center GE Model 7700 Series (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee is pursuing the acquisition of the appropriate qualification documentation.

000 FranMin Research Center 4-31 A Division af Thc Frank5n hsetu(t

TER-C5417-4 4.5.2.61 Equipment Item No. 131 Transformer GE Model Number Not Stated (License reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

4.5.2.62 Equipment Item No. 132 Solenoid Valve Target Rock Model 1/2 SMS-A-Ol-l (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment.

4.5.2.63 Equipment Item No. 36 Motor-Operated Valve Limitorque Model,SMB-OOO (Licensee Reference 40)

The Licensee has provided documentation that shows this item to be qualified in all areas except operating time. However, the Licensee states that substantial aging tests have been conducted, and that, in its judgment, this more than satisfies the requirements of the DOR Guidelines. ERC finds this evidence to be inconclusive and neccessitates further testing.

4.5.2.64 Equipment Item No. 44 Differential Pressure Indicator Switch Barton Model 278 (Licensee reference not cited)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment.

The Licensee requests approval for interim operation based on the post-accident information provided by redundant low pressure instrumentation for 'MSIVs.

U00 Franidin Research Center 4-32 A Divisen d The FranCn Insane

TER-C5417-4 4.5.2. 65 Equipment Item Nos. 45 and 46 Pressure Solenoid Operator Automatic Valve Corp. C5497 (Licensee Reference 42)

The Licensee has provided insufficient documentation to enable evaluation of qualification for this equipment item.

4.5.2.66 Equipment Item No. 71 Pump Motor GE Model 5K326PK-234A (Licensee reference not cited)

The Licensee states that redundant equipment is available to mitigate the accident and consequently suggests that this equipment item need not be qualified. No qualification information is presently available to the Licensee or PRC. The Licensee should pursue qualification of this equipment.

4.5.2.67 Equipment Item Nos. 23 and 24 Solenoid Valve Valcor Model 526D (Licensee Reference 33)

The Licensee has provided documentation that shows this device to be qualified to function in a post-accident environment. However, in view of IE Bulletin 80-23, validity of the testing should be verified.

4.5.2.68 Equipment Item No. 135 Penetration Assembly GE Series 100 (Licensee Reference 22)

The Licensee has provided documentation that shows this equipment to be qualified to function in a post-accident environment. However, in view of IE Bulletin 77-06, the qualification status should be verified.

'ltlll Franklin Research Center 4-33 A Session ot Tbe Franl4n tnsatute

TER-C5417-4 4.6 NRC Catgory V EQUIPMENT WHICH IS UNQUALIPIED The DOR Guidelines require that complete and auditable records reflecting a comprehensive qualification methodology and program be referenced and made available for review of all Class 1E equipment.

The qualification of the following equipment items has been judged to be deficient or inadequate, based upon PRC'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) documentation 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 considered unqualified.

4.6. 1 Equipment Item No. 22 Solenoid Valve e

ASCO Model HB830081P (Licensee Reference 32)

The Licensee has provided documentation that shows this equipment to be unqualified. The Licensee will retest the item or replace it with qualified equipment.

4.6.2 Equipment Item No. 32 Component Assembly Nuclear Measurement Corp., Model Not Stated (Licensee References 35, 36, and 37)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, humidity, and radiation dose. The Licensee will retest these monitors to determine if they will function in the post-accident environment specified in this area of the plant.

0 fill Franklin Research Center 4-34 A M~an d The Franklin Iroctute

TER-C5417-4 4.6.3 Equipment I tern Nos. 37 and 38 Motor-Operated Valve Limitorque Model SMB-000 (Licensee Reference 40)

The Licensee has failed to provide qualification documentation to show that this item will successfully function in a post-accident environment. The Licensee will either type test the item or replace it with qualified equipment during the next refueling outage.

4.6.4 Equipment Item No. 42 Pressure Solenoid Operator Target Rock Model 1/2 SMS-A-01 (Licensee Reference 41)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for radiation dose, aging, and operating time. The Licensee will either retest this equipment or replace it with qualified equipment.

4.6.5 Equipment Item Nos. 47 and 48 Temperature Switch Penwal Model 17002-40 (Licensee Reference 43)

The Licensee has provided documentation that shows this equipment to be qualified in all areas except radiation and aging. The Licensee will retest this equipment or replace it with qualified items.

4.6.6 Equipment Item Nos. 49 and 50 Pressure Switch Barksdale Model B2T-A12SS (Licensee References 44 and 45)

The Licensee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment.

l)ll franklin Research Center 4-35 A Orson d The Franklin Insecure

TER-C5417-4 4.6.7 Equipment Item Nos. 52 and 53 Pressure Switch Barton Model 288 (Licensee References 47 and 48)

The Licensee has failed to provide adequate qualification documentation to show that this item will successfully function in a post-accident environment.

4.6.8 Equipment Item Nos. 54 and 55 Level Indicator Switch Barton Model 288A (Licensee References 47 and 48)

The documentation provided by the Licensee shows this equipment to be unqualified to successfully function in a post-accident environment.

4.6.9 Equipment Item Nos. 58, 59 64'5r 84 85, 86, 87, and 98 Motorized Valve Actuators Limitorque Models SMB-2, SMB-OO, SMB-3, SMB-O,-and SMB-1 (Licensee Reference 49)

The documentation provided by the Licensee fails to show this equipment item is qualified to meet post-accident environmental specifications. The Licensee will subject this equipment to a retest to establish possible qualification.

4.6.10 Equipment Item Nos. 57, 60, and 63 Motorized Valve Actuator Limitorque Models SMB-2 and SMB-00 (Licensee Reference 49)

The Licensee has failed to provide adequate aging documentation for this equipment item, but argues for its permanent exemption from the DOR Guidelines based on Limitorque Test Reports B0003g B 0027r and 600198, which show that this equipment performed successfully at temperatures higher than post-accident temperatures, although for a shorter time period.

In response to the Licensee's position, PRC finds this equipment unqualified.

ill) Franklin Research Center 4>>36 A lXnson ot The Fronklln lnscarte

TER-C5417-4 4.6.11 Equipment Item No. 68 Solenoid Valve ASCO Model X8300-B61P (Licensee Reference 42)

The Licensee has provided documentation from ASCO Test Report A@5-21678/TR that shows this equipment to be unqualified in the areas of aging

'and test duration.

4.6.12 Equipment Item No. 73 Solenoid Valve ASCO Model NPHTX8300B45P,R (Licensee Reference 42)

The Licensee has provided test report documentation that shows this item to be unqualified in the area of test duration. Aging effects for this valve have not been evaluated.

4. 6. 13 Equipment Item No. 78 Plow Switch Barton Model 289 (Licensee References 53-55)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements exposure for radiation, test duration, and aging. The Licensee will sub)ect this equipment to further qualification testing or replace it with qualified equipment.

4.6. 14 Equipment Item No. 81 Level Transmitter Rosemount Model 1151 Series (Licensee References 56 and 57)

The Licensee has<<provided documentation that shows this equipment does not fulfill Guidelines requirements for operating time and radiation exposure. Aging qualification has not been documented.

I'll Franklin Research Center 4-37 A Onssesn er The FtenkSn hsetuse

TER-C5417-4

4. 6. 15 l Equipment tern Nos. 91 and 92 Temperature Switch Fenwal Model 17023-6 (Licensee References 3 and 43)

The Licensee has provided documentation that shows this item does not fulfill Guidelines requirements for radiation and aging. The Licensee considers the effects of aging due to the normal environmental conditions negligible.

FRC finds that this equipment is unqualified.

4. 6. 16 Equipment 1 tern No. 94 Pressure Switch Barksdale Model PZH-M85SSV (Licensee References 44 and 45)

.The Licensee has provided documentation that shows this equipment does not fulfillGuidelines requirements for temperature, radiation exposure, and operating time. The Licensee will retest this equipment or replace it with qualified devices.

4.6.17 Equipment Etem No. 96 Pressure Switch Static-0-Ring Models 6N-AA21 and 6N-AA21-V (Licensee Reference 58)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, radiation exposure, and operating time. The Licensee will retest this equipment and replace it if it proves to be unqualified to suitably function in a post-accident environment.

0ll Franklin Research Center 4-38 A Division d The Fronl4n Insaetc

TER-C5417-4 4.6.18 Equipment Item No. 100 Pressure Switch Barksdale Model D2H-M150SS (Licensee References 44 and 45)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, operating time, and aging effects. The Licensee will retest this equipment to verify qualification or replace it with qualified equipment.

4.6.19 Equipment Item No. 101 Motor Operator Limitorque Model SMB-4T (Licensee Reference 49)

The Licensee has provided test data that shows this equipment does not fulfill Guidelines requirements for temperature and operation duration.

4.6.20 Equipment Item No. 103 Pressure Switch Static-0-Ring Model 5N-AA3 (Licensee Reference 58)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for radiation exposure, temperature, operating time, and aging effects. The Licensee will either retest the equipment or replace it with qualified equipment.

4.6.21 Equipment Item Nos. 104 and 106 Motor Operator Limitorque Models SMB-5T and SMB-4 (Licensee Reference 49)

The Licensee has provided documentation from Limitorque Test Reports 600197, B-0027, and B-0003 that shows this equipment does not fulfill Guidelines requirements for temperature, operating time, and radiation effects. The Licensee will continue testing to verify conclusions of the previously referenced test reports.

00 FranMin Research Center 4-39 A Dion at The fank5n hsotutc

TER-C5417-4 4.6.22 Equipment Item No. 105 Motor Operator Limitorque Model SMB-4 (Licensee Reference 49)

The Licensee has provided documentation that shows this equipment is unqualified in the area of operating time. Aging criteria have not been addressed.

4.6.23 Equipment Item No. 107 Differential Pressure Indication Switch Barton Model 289A (Licensee References 48 and 53)

The Licensee has provided documentation that shows this equipment does not fulfill Guidelines requirements for temperature, radiation exposure, and operation time.

4.6.24 Equipment Item No. 109 Flow Switch Barton Model 289 (Licensee References 53 and 54)

The Licensee has provided documentation that shows this equipment does not fulfillGuidelines requirements for radiation exposure, operating time, and aging effects. The Licensee will either provide further qualification documentation or replace the item with qualified equipment.

4.6.25 Equipment It:em No. 111 Solenoid Valve ASCO Models X8315 and C28 (Licensee Reference 42)

The Licensee has referenced ASCO qualification test Report AQ5-21678/TR covering the 8300 series ASCO valves and finds them qualified in all areas except operation time and aging effects. In TVA's judgment, this equipment is of sufficient quality to function successfully in a design based post-accident environment.

judges this equipment item unqualified until further 4

FRC documentation can be provided to verify qualification.

Franklin Research Center 4-40 A Ovlelan at The Franklin tneatute

TERM5417-4 4.6.26 Equipment Item No. 119 Level Switch Barksdale Model D2H-M18SS (Licensee References 44 and 45)

The Licensee has provided documentation that shows this equipment is unqualified in the areas of operating time and aging requirements.

4.6.27 Equipment Item No. 130 Motor Generator Louis Allis Model 8-127033 (Licensee References 4 and 59)

The Licensee has provided documentation that shows this equipment is unqualified in the areas of operating time and aging effects.

4.6.28 Equipment Item No. 134 Terminal Block GE Models EB-5 and CR15182 (Licensee References 24, 25, and 26)

The Licensee has provided documentation that shows this equipment is unqualified in the area of radiation effects.

4.6.29 Equipment Item No. 137 Electrical Penetration Assembly Physical Sciences Corp. Model PSC P/N 2019C (Licensee Reference 14)

The Licensee has provided documentation that shows this equipment is unqualified in the areas of operating time and aging effects.

4.6.30 Equipment Item No. 139 Switches GE and Cutler Hammer Models GE-CR2940 and CH-10250T (License Reference 61)

The Licensee has provided qualification documentation that shows this item is unqualified in the- areas of operating time and radiation. The Licensee will continue equipment testing to determine the ultimate qualification of this equipment item.

lltl(l Franklin Research Center 4-41 A Dnteion of The Fsaneln Ineotute

TER-C5417-4 4.6.31 Equipment Item No. 41 Motorized Valve Actuators Rotork Model 14A (Licensee Reference 63)

The Licensee has provided documentation that shows this item is qualified in all areas except operating time and temperature.

4.6.32 Equipment Item Nos. 43 and 66 Pressure Solenoid Operator ASCO WPHTX8300B68F (Licensee Reference 42)

The Licensee has provided documentation that shows this equipment is unqualified in the areas of radiation, aging, and operating time. Further testing is necessary to show that this equipment is qualified to adequately ooerate in a post-accident environment.

4.6.33 Equipment Item No. 72 Explosive Valve Conax Model 1832-117 (Licensee References 50 and 51)

The Licensee provides data from test report References 50 and 51 that show this equipment is unqualified in the areas of radiation and aging effects. The Licensee suggests that specification for radiation level is unnecessarily conservative and that this valve is qualified to operate successfully for up to 30 days in a post-accident environment. However, this information has not resolved qualification of this equipment item.

4.6.34 Equipment Item No. 77 Pressure Switch Barton Model 289 (Licensee References 53, 54, and 55)

The Licensee provided documentation that shows this device is unqualified in the areas of test duration and aging.

Illll) Franklin Research Center 4-42 h Din>ion d The Fisnk6n Insane

TERM 5 4 17-4 4.6.35 Equipment Item No. 83 Pressure Switch Static-0-Ring Model 12N/AA4 (Licensee Reference 58)

The Licensee has provided. documentation that shows this equipment is unqualified in the areas of operating time, radiation, and aging.

4.6.36 Equipment Item Nos. 74 and 75 Limit Switch NAMCO Model EA740-50100 (Licensee Reference 52)

The Licensee has provided documentation from Reference 52 (Acme-Cleveland Development Co. Test Report 2/20/78) that shows this equipment to be qualified in all areas for up to 7 years. However, the report notes that the Licensee must use a qualified method for sealing the switch, the seal has not been addressed.

4.6.37 Equipment Item No. 90 Temperature Element Scam Model S51-1 (Licensee reference not cited)

The Licensee has provided documentation which shows this equipment to be unqualified in the areas of aging and temperature requirements.

Ilail Franklin Research Center 4-43 A Msion d The Franklin In'(u(c

TER-C5417-4 4.7 NRC Category VI EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED This section normally includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittal; however, the qualification review of this equipment has been deferred by the NRC in accordance with criteria presented in Sections 2.2.3 and 2.2.5 of this report.

4.7.1 Equipment Item No. 133 Junction Boxes Various Model Numbers (Licensee References 19 and 20)

FRC judges junction boxes to be non-electrical equipment and, hence, chooses not to evaluate their longevity or reaction to post-accident environmental conditions in this TER.

4.7.2 Equipment Item No. 140 Cable - See Manufacturers List The Licensee has failed to provide documentation that correlates cable type with its respective manufacturer and location to enable a oroper evaluation of its environmental qualification. FRC, therefore, defers qualification until substantive documentation has been provided by TVA.

I Franklin Research Center A blvlslon el The FrankKn kame 4-44

5. CONCLUSIONS TER-C5417-4 5~ CONCLUSIONS FRC's review of the qualification documentation and other information submitted by the Tennessee Valley Authority for these equipment items and their applications in the Browns Ferry Unit 1 plant has resulted in the following categories:

NRC Compliance With The DOR Quantity Of catecaoCrr Guideline Re uirements Ecrui ment Items Z.a Equipment Fully Satisfies All Applicable Requirements for Life of the Plant 1.b Equipment Does Not Meet All Applicable Requirements for Life of the Plant; However, Deviations are Judged Acceptable ZI,a Equipment Fully Satisfies All Applicable Requirements for Less Than Plant Life IZ.b Equipment Fully Satisfies All Applicable Requirements Provided That Specific Modifications are Made ZI.c Equipment for Which the Licensee Has Not Provided Evidence of Full Compli-ance with the Guidelines, but which is Judged by FRC To Be Satisfactory for Less Than Plant Life Based on Total EEQ Program Review IIZ Equipment is Exempt from Qualification ZV. a Equipment has Qualification Testing Scheduled IV.b Equipment has High Likelihood of Operability; However, Proper Qualification Documentation is Not Available 79 Equipment is Unqualified 56 VI Equipment for Which Qualification is Deferred l (ll Franklin Research Center 5-1 A Divoion ot The Franklin huuetc

TERM5417-4 In gen'eral, the major deficiencies that have been identified are shown in the summary review sheets at the end of= the section.

The conclusions stated herein represent a summary of the results of the equipment environmental qualification evaluation conducted by FRC in accordance with the methodology presented in Section 3. The evaluation results are largely based on the available qualification documentation provided by the Licensee. The results of the review do not necessarily imply that the equipment is unreliable, unsafe, or represents a significant plant safety issue; they do imply, however, that qualification documentation is inadequate and that additional information is required.

The Equipment Environmental Qualification Summary Form presented on the following pages shows the overall results of the PRC review. The entries on this. form delineate the overall status of each specific equipment item with respect to compliance with the Guideline criteria defined in Section 2.0 and the resultant qualification categories defined in Section 3.0. The following designations are used:

A deficiency with respect to compliance with a Guideline requirement. Deficiencies result in equipment items categorized as unqualified or qualification not established.

L ~ A limiting condition with respect to qualification in that the qualified life has not been established by the Licensee.

0 NRC Qualification Category.

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

!ill Franklin Research Center A Division el The Fsenl4n >nsenne 5-2

FRC TASK REACTOR PLANT NAME, PAG i ')ll TYPE

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SUMMARY

REVIEW EQUIPMFNT ITEM NUMBER 2 3 9 5 6 7 8 9 /0 /I lg r'3 '/P I 14!I7 JP GUIDFLINE REQUIREMc, 17 X DEFICIENCY, L LIMITINGCONDITION)

~942'DESIGNATIONS:

EVIDENCE OF QUAL!FICATIOiV RELATIONSHIP TO TEST SPEC!M N AGING DEGRADATION EVALUATED QUALiFIEO LIFE STABLISHED PROGRAM TO IOE'ITiFY AGING

(

QUAL. FOR STEAi41 EXPOSURE PEAK TF i' P ERA TU RE ADEQUATE Pc'K PRESSURc ADEQUATE TEST DURATION ADEQUATE REQUIRED PROFILE ENVELOPED QUAL. FOR SUB'IERGEIICF QUAL FOR CH ~ RICA'PRAY QUAL. FOR RADIATIOi~l BETA RADIATICNCONSIDERED TEST ScGUcNCE TEST DURATIOV (1 HOUR + FUNCTION)

QUANTITYOF EQUIPMENT EQUIP~'iIENT INSPECTED AT SITE

~la slain ~la 3  ! I> 9gp pl~i<:

QUALIFICATIONCATEGORY, 0 CATEGORY DESIGNiATION I-A. QUAL. FOR PLAiVT LIFE I-B. QUAL. BY JUDGEM=NT If-A. QUAL. FOR < PLAi'IT LIFE II B QUAL PcNOI,'lG MODIFICATION II-C. QUAL. < PLAiVT LIFEiiRC REVIEW III. ~'(EMPT FROM QUAL.

IY-A. QUAL. TEST SCHEOULc lV-B. QUAL. NOT ESTA" LISHED 0 0 o!oio O!o O 0!OO oIc Otn o!a! a;O:

i V EGU P NOT CU.:l IFIED

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DOCKET RSVP'TILITY 41 7-01 NRC TAC T'VA DATE/ EiVC iiVc"- w IE8-7941 8

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SUMMARY

R VIEVI EQUIPMENT ITEM NUMBER J.l goE 23 2'I Z~ M r'7 ~~8 e"9 30 3 j ~ ~~"-

P - ~ "r" ~<'

GUIDELINE REQUIP.EMcNTS (DESIGNATIONS: X DEFiCIENCY, L LIMITINGCONDITION)

EVIDENCF OF QUALIFICATiON RELATIONSHIP TO TEST SPECIMEN AGING DEGRAOAT!ON EVALUATED QUALIFIEDLIFE FSTABLISHED PROGRAM TO IDENTIFYAGING QUAL. FOR STH' EXPOSURE PEAK TEMPERATURE AOcQUATE PcAK PRcSSURE ADEQUATE TEST OURATiOiV ADEQUATE REQUIRED PROFILE E<VVELOPED UAL cOR S! 'BYE G QUAL. FOR CHE."rIICALSPRAY QUAL. FOR RADIATION BETA RADIATIONCONSiOERHD TFST ScQUHiVCc TES < DURATION (1 HOUR  : FUNCTION)

QUANTITYOF EQUI?M NT

'EQUIPMcNT INSPHCTEO AT SITE QUALIFICATIONCATEGORY, 0 CATHGOR YO HSIGNATIO I-A. QUAL. FOR?LANT LIFE I-8. QUAL. BY JUOGElv1ENT II-A. QUAL. FOR < PLANT LiF" II 8 'QUAL PENDING-MODlcICATION II-C. QUAL. < PLAi 4T LIFHiFRC REVIHV(

III. EXEMPT FROM QUAL.

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SUMMARY

REVIEW EQUIPMENT ITEM NUMBER Vl VA V3 ~. V4 VC 7 VP <9ZQZ/ y Z3~gF <<z~~, -n PI GUIDELINE REQUIREtV ENTS, (DESIGNATIONS: X DEFICIENCY, L LIMITINGCONDITION)

EVIDENCE OF QUALIFICATiON RELATIONSHIP TO TEST SPECLMEN AGING DEGRADATIOi'I EVALUATED QUALIFIED LIFE ESTABLISHED PROGRAM TO ID NTIFY AGING QUAL. FOR STEAt~rI EXPOSURE PEAK TFMPERATURE ADEQUATE PEAK PRESSURE A DEQUATF TEST DURATION ADEQUATE REQUIRED PROFILE ENVELOPED QUAL. FOR SUBr'rIERGENCE QUAL. FOR CHEMICALSPRAY QUAL. FOR RADIATIGihl BETA RADIATIONCONSIDERED TEST SFQUEihICE TEST DURATION (1 HGUR + FUir!CTIOlr!)

QUANTITYOF EOUIPMEihIT

! 3 I g' I c-.

EQUIPMFNT INSPECTED AT SITE QUALIFICATIGNCATFGORY, CATEGOR D-S IGihlATIO I A. QUAL FOR PLANT LIF I-B. QUAL. BY JUGGcMENT II-A. QUAL. FOR < PLAi4T LIFE II-B. QUAL. PENDING rvlODIFirCATION II-C.QUAL. <. LANTLIFEirRC REVIEW III. EXFMPT FROM QUAL.

IV-A. QUAL. T ST SCHEDULE I'/-B. QUAL. h GT "STABLISHED 0 0 V. ECU!P, NGTC CLIF!ED iO'QIO! O 'O,'OlOIC, '0 O:0 O-Vl. QUAL. IS D=."-ERr,=D, REPLAC 'rIErRT SCHEDULE I I  !

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.$ 0- ~S~ IS/)61 Si

SUMMARY

REVIEW EQUIPMENT tTEM NUMBcR

(,I 43 (,= H ieZ~og 07 t'= '-'I 70 7i 7+ r ~'+ r> 7w 7/l7+l ~'r+r GUIDELINE RcQUIREMcNTS (DESIGNATIONS: X DEr.lCIENCY, L L!MITING CONDIT!ON>

EVIDENCc OF QUALIFICATION RELATIONSHIP TO TcST SPECIMEN AGING DEGRADATION EVALUATED QUALIFIED LIFE ESTABLISHED PFIOGRAM TO IDENTIFY AG)NG QUAL. FOR ST~AM EYPOSURE PEAK TEt'.IPERATUr RE AGcQUATc PEAK PRFSSURE ADEQUATE TEST DURATION ADEQUATE REQUIRED PROFILE eiVVELOPED QUAL FOR SUBttrIERGENCE QUAL. FOR CHEMICALSPRAY QUAL. FOR RADIATION BETA RADIATIONCONSIDcRED TEST S cQUEiVCE TEST DURATION (1 HOUR + FUtVC1iON)

QUANTITYOF FCUIPMENT l Is.l~ u, y)

I>,'QUIPMENT INSPECTED AT SITF QUALIFICATION,CATEGORY, 0 CAT"GORY DFSIGNATION I-A. QUAL. FOR PLANT LIFE

~ i I-B. QUAL. BY JUDGEi'CLIENT I ll-A. QUAL. FOP<fl~~iti LIFE II-B. QUAL. PEN Cf4'."-jUQDIFICATION It-C. QUAL. < PLAiVT LIFclFRC REVIBV III. cYEMPT FROM QUAL.

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SUMMARY

REVIEW EQUIPMENT ITcM NUMBER

'8I Pk F3 Z0 V iC 27 7PP, I0",I 9< 97'.,- ..~ 77 'P .';> '.>>

GUIDELINE REQUIREMENTS, (DESIGt tATIOiVS: X DEFICIENCY, L LIMITINGCON DI7ION)

EVIDENCE OF QUAL!FICATION RELATIONSHIP TO TEST SPECIMEN AGING DEGRADATION EVALUATED QUALIFIEDLIFE FSTABLISHED PROGRAM TO IDENTIFYAGING QUAL. FOR STEAM EXPOSURE PEAK TEMPERATURE ADEQUATE PEAK PRESSURc ADEQUATE TEST DURATION ADEQUATE REQUIRcD PROFILE ENVELOPcD QUAL. FOR SU BMERGEiNCF QUAL. FOR CHEMICALSPRAY QUAL. FOR RADIA7ION B TA RADIATION CONSIDERED TEST ScGUEiVCE TEST DURATIGN (1 HOUR + FUNCTION)

QUANTITYOF EQUIPMENT 7 /

EQUIPMENT INSPECT" D AT SITE I s i QUAL!FICATIGNCATEGORY. 0 CATEGORY DESIGiVAT!ON I.A QUAL FOR?LANT LIFc I-B. QUAL. BY JUCGcMcNT lf-A. QUAL. FOR < PLANT LIFE II-B. QUAL. PENDING MODIFICATiON II-C. QUAL. < PLANT LIFEiFRC REVIEW III. cEXEMPT F ROI'r! QUAL.

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SUMMARY

REVIEW EQUIPMENT ITEM NUM BER lf1 lO2lo l8 la./OG.:J7 Ia~i-/ lid Ill .i '= ii'H'l J~G)ll7 ll ll7*'I~

GUIDELINE REQUIREMENTS, (DESIGiVATIONS: X DEFICIENCY, L LIMITINGCONDITION)

EVIDENCE OF QUALIFICATION RELATIONSHIP TO TEST SPECIMEN AGING DEGRADATION EVALUATED QUALIFIEDLIFE eSTABLISHED PROGRAivl TO IDENTIFY AGING rY QUAL. FOR STcAM EXPOSURE PEAK TEMPERATURE ADEQUATE PEAK PRESSURE ADEQUATE TEST DURATION ADEQUATF REQUIRcD PROFILc cNV'LOPED QUAL.."OR SUBMERGENCE UAL. FOR CHFMICALSPRAY UAL. FOR RADIATION BETA RADIATIONCONS IDEREO TESTS QUENCc TEST DURATION (1 HOUR + FUNCTION)

QUANTITYOf EQUIPivIEiVT EQUIPMENT INSPcCTED AT SITE QUALIFiCATIONCATEGORY, 0 CATcGOR YO CC,' IGiVATIO I

I-A. QUAL. FOR PLANT LIFE I-B. QUAL. BY JUDGEMENT II-A. QUAL. FOR < PLANT LIFF

)

II-B. QUAL. PENDING MODIFICATION l  !

II-C. QUAL. < PLANT LIF"iFRC REVIEW l i III. EXEMPT FROisI QUAL.

V-A. QUAL. TcST SCHcDULc IV-B. QUAL. NOT ESTABLISHED ol oO O)CI IO) Ol ';O:

V. EQUIP. NOT QUALIFIFO O,'QIQ a Oi la) I ( i 0

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The beennvn Frervnn penreey. 9tvte pe t91SS PROJECT UTILITY EQUIP MENT ENVIRONMENTAL 02G &5@1 7<1 QUALIFICATION OOCKFT NRC TAC DATE/ENGINEER IEB-79-01 B

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SUMMARY

REVIEV/ EQUIPMENT ITEM NUMBER IA/ gg /wo I>'//>-" />f )~j /~ )-'9 rr3o /3/ /3y:< ",' ."r gr g'"irllj'9 GUIDELINE REQUIRE.".IENTS, (DESIGNATIONS: X DEFICIENCY, L I.IMITINGCONOITIOil)

EVIDENCE OF QUALIFICATION RELATIONSHIP TO TFSTSP CIMEN AG ING DFG RA DATION EVALUATED QUALIFIED LIFE ESTABLISHED PROGRAitvI TO IDENTIFY AGING i !C QUAL. FOR STEAM EXPOSURE P AK TEi'v1PERATUR ADEQUATE PEAK PRcSSURc ADEQUATE TEST DURATION ADEQUATE REQUIRED PROFILc ENVELOPED QUAL FCR SUBMERGENCE UAL. FOR CHE."rIICALSPRAY UAL. FOR 9AOIATION BcTA RADIATIONCONSIOEREO TFST ScQUEi~lCE TEST DURATION (1 HOUP. + FUNCTION)

QUANTITYOF EQUIPMEi~lT s zlx g /g gl EQUIPMENT INSPECTEO AT SITE QUALIFICATIONCATEGORY, 0CATEGOPY 0 ESIGiVATION I-A. QUAL. FOR PLANT LIFE I-B. QUAL. BY JUOGcMENT ol II-A. QUAL. FO9 < PLANT LlcE o iol l II-B. QUAL. PENDING MODIFICATION II-C. QUAL. < PLANT LIFE/FRC REVIEiN III. EXEMPT FROM QUAL.

!V-A. QUAL. TEST SCHEDULE IV-8. QUAL. NOT cSTABLISHED o)o oo0 O~olol 0 DI I I

V. EQUIP. i'IOT ~ U.'IFIEO i lg~ (+1 Vl QUA( IS Oc "c-RcO ,o REPLACE."<IEN SCHEDULE I i  !.

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TERMS 417-4 6~ REPERENCES

1. IPECA S-61-402 Paragraph 3.9 and Appendix D.

2- TVA Engineering Report No. 1943.

3. Wyle Laboratory Report No. 43854-3.

4. NUREG-0588 Material List.

5 ~ TVA Engineering Report No. 1946.

6. TVA Engineering Report No. 1944.

7. Parkinson and sisman, October 1970.

8. Blodgett and Pisher, June 1968.

9. Asaka and Yamamoto, 1973.

10. Anaconda-Continental Test Report No. 79117.

ll. Pranklin Institute Test Reports P-C4113 and PC-5120.

12. Rockbestos Test Report, dated. July 1977, amended 1979.

13. TVA Engineering Report 1942.

14. TVA Engineering Report 1928.

15. TVA Engineering Report 1923.

16. TVA Engineering Report 1945.

17. TVA Engineering Report 1947.

18. Pranklin Institute Test Report P-C2935.

19. TVA Engineering Report 1950A.

20. TVA Engineering Report 1950B.

21.- TVA Engineering Report 1925.

22. TVA Engineering Report 1926.

23. TVA Engineering Report 1921.

24. GE Letter dated Pebruary 3, 1978 to H. J. Green.

25. Westinghouse letter dated March 9, 1978 to P. W. Chandler.

26. BWR Owners Group Report 081-A-01 dated September 23, 1980.

27. MILM-49142.

28. GE Report EPAQ-57.

29. GE Report EPAQ-60.

6-1 Ill( Franklin Research Center A Oinsion d The Frsnk5n Instate

TERM5417-4

30. GE Report EPAQ-10.

31. GE Prototype Test Data Epoxy Life Tests.

32. ASCO Report No. AQ5-21678/TR.

33. Valcor Doc. No. QR-526 dated February 15, 1979.

34. Target Rock Report No. 1827A dated November 4, 1976.

35. TVA Specif ication 3350.

36. NMC Test Report NMC-PT-7630 Rev. O.

37. NMC Drawing 0082445 Rev. D, February 9, 1978.

38. Appendix I to Sheet MEB-63-01.

39. Appendix II to Sheet MEB-64-02.

40. Appendix II to Sheet MEB-67-01.

41. Target Rock Test Report 2199A.

42. ASCO Report AQ5-21678/TR.

43. Fenwal Engineering Report 6350.

44. Wyle Laboratories Report QSR018A012.

45. Barksdale Qualification Procedure 9993.

46. Lockheed Test Report-3232-3155 dated March 22, 1973.

47. Barton Engineering Report R3288A-l.

48. Wyle Summary Report QSR-027-A-02.

49. Limitorque Test Reports B003, B0027, and No. 600198.

50. Conax Test Report TR-39

51. Wyle Summary Report QSR-146-A-01

52. Acme Cleveland Devel Co. Test Report, dated 2/20/78

53. Barton Engineering Report R3-288A-1

54. Wyle Summary Report QSR-029-A-01

55. Wyle Summary Reports E12-3 and E12-N010

56. Rosemount Test Reports 37327B and 127227

57. Wyle Report QSR-048-A-Ol

58. Viking Lab Report 30203-2

59. Louis Allis Document S40EJ4-099-630 of 10/10/79

60. TVA Engineering Report 1927

61. Wyle Lab Report QSR-002-A-02

62. Franklin Institute F-C2815 Final Report

~

llll Frankiin Research Center A Civison d The FNnl4n Institute

TERM5 417-4

63. Rotork Report, "A" Range Nuclear Qualification

64. Letter from G. Lainas, NRC, to A. Schwencer, NRC.

Subject:

Electrical Equipment Environmental Qualification, dated February 19, 1980.

65. Letter from Norman C. Moseley, NRC, to B. H. Grier, J. P.

O'Reilly, J. G. Keppler, K. V. Sezfrit, R. H. Engelken, NRC.

Subjects IE Supplement No. 2 to Bulletin 79-01B, Environmental Qualification of Class 1E Equipment, dated September 29, 1980.

66. Letter from Norman C. Moseley, NRC, to B. H. Grier, J. P.

O'Reilly, J. G. Keppler, K.V. Sezfrit, R. H. Engelken, NRC.

Subject:

IE Supplement No. 3 to Bulletin 79-01B, Environmental Qualification of Class lE Equipment, dated October 24, 1980.

67. U.S. NRC Memorandum and Order (CLI-80-21) pursuant to the Petition for Emergency and Remedial Relief filed with the NRC on November 4> 1977.

68. TVA response to NRC IE Bulletin 79-01B Environmental Qualification of Class 1E Equipment for Browns Ferry 1, 2< and 3, dated October 31, 1980.

69. NUREG 0588 ~

6-3 (ll Franklin Research Center A Glen ot The Fran&n Insecure

TER-C5417-4 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS The Licensee has provided detailed information concerning environmental zones and expecting environmental service indicators in all locations within the plant. Tables and figures contained in this appendix show these environmental service conditions as follows:

Table B.O 1,2,3 Room Number, Name and Plant Location This table relates the room number to a room name and to a specific plant location (See attached sheets 1-6 for plant locations).

Table B.OO 1,2,3) Environmental Tem erature/Pressures Curves Room Number Desi nation This table relates to various room numbers to figures or Table B.l (1,2,3) which are in this appendix for temperature and pressure.

Table B.l (1,2,3 - Tem erature/Pressure Selected Areas)

This table gives selected temperature-pressure values for selected areas that are not contained in a profile.

Table B.2 1.2,3 Summar of Operational Conditions This table gives a tabulated listing of environmental service conditions.

000 FranMln Research Center A-1 A Boson ol The Frenk5n Institute

TER-C5417-4 TABLE B.O (1R2,3)

Room Number Name, and Plant Location Plant Location Room No. Room Name Inside Primary Containment (Drywell) Sheet 2 00 Inside Primary Containment (Wetwell) Wetwell HPCI Pump elevation 519.0'heet (or Turbine) Room; 1

S. W.

519.0'heet RHR Pump Room; elevation 1 elevation 519.0'heet N. W. RICE and Core Spray Pump Room; 1

elevation 519.0'heet N. E. Core Spray Pump Room; 1

S. E.

elevation 519.0'heet RHR Pump Room; Pressure Suppression Chamber (HPCI 1

Torus Room); elevation 1 519.0'ain Steam Vault Room Sheet 2 Open Area; elevation 565.0'pen 593.0'heet Sheet 3 Areas; elevation Sheet 3 593.0'WCU 10 Pump Room; elevation Sheet 3 RWCW Heat Exchange Room; elevation 593'heet 3 12 Open Areas; elevation 621.25 4 13 South Open Areas; elevation 639.0'heet Sheet 5 Unit 1 locations same as Unit 3.

Ij0 Franklin Research Center A-2 A OiVISiOn d The Franidin IRRRRNR

TER-C5417-4 Plant Location*

Room No. Room Name North Area; elevation 639.0'heet 664.0'heet Open 5 15 Units 1-3 Refueling Floor; elevation 6

16 Unit 1-3; elevation 593; RWCU BW receiving tank rm Sheet 3 17A Unit 1-3; elevation 639; RWCU Demineralizer A Sheet 5 17B Unit 1-3; elevation 639; RWCU Demineralizer B Sheet 5 18 Unit 1-3; elevation 621.25; Cleanup Demin Vlv Rm Sheet 4

• Unit 1 locations same as Unit 3.

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FIGU.iE SUi'-'c..!"- 9

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TABLE 8.00 (1>2 3) ev rv:- ucEh.";EE Q.D ENVIRONNEHTAL TEHPERATURE PRESSURE CURVES - ROON NIMER DESIGNATIONS>>

a cD D Ct>

fn Room No.

oA 8

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>>*Same as room 9 for units 1, 2, and 3

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oD TABLE 8.00 (1,2,3)

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~a NVIRONMENTAL TEMPERATURE PRESSURE CURYES - ROON NUMBER DESIQiATIONS'Continued) na Room No.

~Oesl nation Unit 1 Units 2 and 3

~em nra re ressure emaeratnrn ressure 11A Table 8.1 (1.2,3) Table B.l (1,2,3) Table B.l (1,2,3) Table B.l (1,2,3) 178 18 Qt 0 nation:

I V *F1 ure Desi Designation applicable only for room 00, pressure curve only V

0 0 Figure .()Y ~l 2 3 Appendix 8 Room (umber Unit signation

~Table Desi nation:

T ble number 1 (not unit designation)

Table B.T 1 2 3 Appen ix 8, Unit designation g

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TER-C5417-4 TABLE 8.1 0,2,3)

TEMPERATURE - PRESSURE (Selected Areas)

Unit 1 Unit 2 Ec Time Co artment (1) Time Compart "ent 2 sec 1.3 psig 5 II 1 1 Same as tor unit 1 11 .8 30 II 50 Q~ II Comsat t"ent (10) Ti e All Remainin Area

~ 02 sec 2.4 psig 1 sec ~1 psig a a 3Q 5 e 5 le3 45 w ~5 45 e 1 ~3 5Q e 1 e ~ 2 120 0 e Time Cosoartment ( 1 1) 1 sec 2.4 psig 10 3 4 a All Units Comoartrent 7 45 ~

3 B e 47 ~ ~ 4 e Steam Valve Vault 55 N ol 120 Q I ~ 1 sec 1.7 psig 3 7.1 N

5 a Ti e All Recainfn Areas 5 a 7 e e 2+0

~ 1 psig lQ a s 30 tl ~ 5 150 1.8 45 1 .6 5Q II ~ 2 120 Qo Temperature-Pressure Compartment 15 17A 178 18 - All Units Room Ho.

15 120 15. 0 17A 105 Atm.

17B 105 Atm.

18 110 Atm.

Table B.l g~GUe-t. cUppt ~f.o I) tL Franklin Research Center A-12 i~r a'rs>r

),,i t,4L/'JD A Onnson d The FmnkLn hsatum

TABLE 1 BRONNS FERRT HUCLEAR PLANT SUINARZ OF OPERATIONAL ENVIRONIKHTAL COHDITIONS Total 40-Zr Integrated Plant Building Operational Pressure Peak Peak Integrated Accident Loca l.ion Elevation Location D diti ~E*I PSIR P t I PI ~II idit ~DR d D ttddt 2

Outside AT)I 96-100 100 5 x 10

11. 4 NA Hh HA 8

Reactor 541.5 Dryuell 15.6 140 100 1 x 108 NA Building 15 ~ 6 150 100 1x)0 NA 69.4 325 100 NA Center 8

) x 109 2 x 10 Edge 4x10 4x)0 NA HA HA HA HA 15.6 NA NA NA NA 519.0 Metwell AT)I 95 IOO HA HA AT)I )05 IOO NA NA 43.2 158 100 HA 2x)0 HA NA NA Hh HS ATH NA NA NA HA 519.0 NPCI Roocs ATND 95 98 2x)04 NA AT)ID 105 98 2 x )0 Nh ATND 150 100 HA 3x10

)5.7 300 100 Nh HS 11.4 HA NA HA NA 519.0 SH Pucsp AT)ID 95DD ~ 98 2x 1044 HA Roocs AT)I~ )05D ~ I 98 2x10 NA AT)I~ )60 100 Nh 3x)0

)5.0 292(U)) 100 Hh NS 158(02A3) 11.4 HA Nh HA FlGURE Q.l f"PLtEQ BY Tl-C'= L)CENSEE

TABLE 1 BROWS PERRY NUCLEAR PLAHT Q.D SUHHAR'I OP OPERATIONAL ENVIROttltgttTAL CONDITIONS (s

Total 40-Yr Integrated fn BA B

H>

(s Plant Location Reactor Elevation 519.0 Building Location NM Pump Operational Condition Pressure Extreme (PSIA)

ATHi T ~tF 95 Peak

~ll Peak Idtt 98

(

Integrated I ~D(R d 2 x 104 HA Accident td (II d*t Building Room ATHa 105 98 2 x 10 HA ATHa 160 100 NA 3 x 10 15.0 297 100 HA NS 11.4 HA NA HA NA 519.0 HE Pump ATHe 95 98 2 x 104 tlA Room ATHi 105 98 2x 10 NA ATHi 160 100 NA 3 x 10 15.0 171(U1) 100 HA NS 160(U2A3)

NA HA HA NA 4

519.0 SE Pump ATHe 95 98 2x 104 HA Room ATH~ 105 98 2x10 tlA ATH 160 100 HA 3x10

15. 0 139(U1) 100 NA )IS 294(U2A3)

HA NA HA 5

519.0 Pressure ATHe 95e ~~ 98 1 ~ 5 x 105 lN Suppression ATH~ 105% e ~ 98 1.5 x 10 HA Chamber ATH 170 100 NA 3 x 10 15d0 217(U1) 100 Nh ttS 220(U2A3)

Hh Nh HA 6

565 -Hain Steam ATHi 140 98 2x 106 NA Valve Vault ATHi 160 98 2x to NA ATH 140 100 HA 3x10 21.5 308 100 HA NS 11.4 NA NA HA HA FlQOP."-. SUPP'ED BY THE LlCEN.".,EE

TABI.E 1 D BROMHS FERN'I NUCLEAR PLANT R

SVNIVIRY OF OPERATIONAL ENVIROIRHENTAL COHDITIONS Pi n)

Total 40>>Tr Integrated Pier.t Building Operational Pressure Peak Peak Integrated Accident Location El tl Ld tl E,dlti ~Et (FS)d I t ( F) ~R(dlt ) ~RR d ) ~ l((hd

~R Reactor 565 General Floor ATHi 90 98 I x 105 NA Building Area ATHi 100 98 I x 10 HA ATH 140 100 NA 2.1x IOa ~

15. 0 147(U I ) 100 NA HS 157(02& 3)

11. 4 HA NA NA 593 General Floor ATIIi 90 98 2 x 104 HA Area ATII~ 100 98 2x10 HA ATH 135 100 d HA 2.1 x IO a ~

15.0 214(UI) 100 HA NS 211(02&3) 11.4 NA HA HA HA I 593 . Reactor Mater ATII~ 120 98 1.4 x 10 HA I n0 Cleanup Pump &TIP 130 98 1.4 x 10 HA Rooms ATH 135 100 NA 3x10 rr 15.9 220 100 HA NS 11.4 HA HA HA NA C

0 593 Iieet- Exchanger ATII> 125 98 1.4 x 10 NA Room ATII~ 135 98 1.4 x 10 NA ATH 135 100 HA 3 x 10 18.2 227(UI) 100 NA HS 221(02&3)

NA NA HA NA 621 General Floor ATH& 90 98 I x10 HA Area ATII~ 100 98 Ix10 HA ATII 185 100 HA 3x10 15.0 174(UI) 100 HA HS 199(02&3) 11.4 HA HA NA FIGURE .Ut'PLIED BV T',!E Ut.";.t';.-.:EE

TABLE I BROMNS FERRY NUCLEAR PI.ANT SUHHARY OF OPERATIONAL ENVIRONHENTAL CONDITIONS Total 40-Yr Integrated Plant Building Operational Pressure Peak Peak Integrated Accident Location Elevation Location Reactor os9 General Floor ATHi 90 98 1 x '.03 NA Building Area (South) ATHv 100 98 I x 10 NA ATH 130 100 NA 3x10

15. 0 135(UI) 100 RA NS ITS(U2A3) 11.4 NA NA NA 639 General Floor ATH~ 90 g8 I x10 NA Area (North) ATHi 100 g8 I x 10 NA ATH 130 100 NA 3x10 15.0 153(UI) 100 Ni NS

'174(U2A3)

>>.4 Nh NA NA 664 Refueling Floor I ATHi 90 98 Ix10 NA 2 ATH 100 98 I x 103 NA 3 15.0 120 100 NA 3 x 10 4 NA NA NA llh NS 5 >>.4 NA NA llh NA 593.0 RllCU Bll ATHv 95 g8 5.3 x 10 NA Receiving Tank ATHN 105 gg 5.3 x 10 NA Roon ATH 135 100 Nh 3x10 15.0 214(ul) 100 Nh NS 2>>(UIA2)

>>.II NA NA NA 63g.o RNCU ATHi 8 90 90 2.1 x 108 NA Decaineralixer ATHi 100 90 2.1 x 10 NA A ATH 100 90 NR 3x10 ATH 105 90 NA NS

>>.4 NA NA NA NA

g 2r Q.D RR ni TABLE I BRONIIS FERRT tlUCLEAR PLANT SUHHARY OF GPERATIOttAL ENVIROIIHENTAL COtlDITIOtlS kn Rg Total 40-Yr Integrated gD Plant Operational Pressure Peak Peak Integrated Accident Building Locat,ion Elevation Location R dltt R t (PRIR) T t ( f) ~ll id( t ( 0 (R d*) R (R d*)

8 Reactor 639.0 RMCU I ATH>> 90 90 2.1 x 108 tlA Building De(aineralixer 2 ATH>> 100 90 2.1 x 10 NA B 3 ATH 100 90 NA 3 x 10 4 ATH 105 90 NA ttS 5 NA tlA NA NA 621.5 Cleanup ATH>> 95 90 1.7 x 105 IIA De(>>incralizer ATH>> 105 90 1.7 x 10 NA Valve Roo(>> ATH 105 90 NA 3x10 ATH 110 90 NA NS 11.4 NA NA NA NA

A. Operational condition dcfinftfonsf

1. Normal average day.

2. Abnormal corditions, outside temperature 96-100 0 F and maximum river water temperature exists. duration For this conditfon is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> dur)ng a 24-hour period but may occur on a daily basis f'r a The2- maximum or 3-week period.

(Outs(dc design temperature is 95 F.)

3~ LOCA/HELB fnside primary containment.

4. HELB out.side primary containmenl,.

5. Tornado (sudden pressure drop oF 3.0 pounds per square inch).

B. ATII indicates a pressure equal to atmospheric pressure will bc present. Normal atmospheric pressure at the Browne Ferry site is 14.4 pounds per square inch.

C. ATH'ndfcates a pressure slightly below atmospheric.

Di All dose rates and integrated dose rates shown are upper llmfts for the summatfon of'he gamma and beta contributions unless otherwise indicated. All dose rates are for LOCA; HELB is not signiyicant (denoted HS). Maximum dose rates For thcsc elevations are indicated by ~ ~

. Actual valves may vary significantly dependfng on location. Total radiation dose rates can bc obtained by adding the 40-year integrated and accident dose rates.

E. Hormal humidity is 30 to 80 percent.

F. For operational condition 3, the drywell and wetwell pressure and temperature values are peak values. For transient conditions, see attachment 1.

0. For operational condition 4, temperatures shown are peak values for transient conditions (see attaclueent 2).

H. Pressure, humidity, and radiation parameters apply to units 1-3. Temperatures are applicable to all units unless otherwise indicated. ~ ~ ~ indicates space temperatures may reach 150 0 F during normal shutdown mode.

I. Primary containment areas arc not subJect to a chemical spray.

Reactor building equipment is not subJect to submergence.

K. HA indicates not applcfable tor this operating condition.

E40298.20

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W g CONPRRTNEHT NO. 0 10 20 30 40 SO 60 70 80 90 100 110 120 TINE (SEC)

TER-C5417-4 With respect to environmental service conditions, the Licensee has statedt A. Service Conditions The environmental conditions present in plant areas that can affect safety-related equipment have been established. The following categories were used to bound anticipated plant conditions.

1. Normal The temperature, pressure, humidity, and radiation ranges that are expected to be present when the plant is in any of the technical specification modes of operation.

2. Abnormal- Conditions that could exist for all areas for a short period of time that may occur once or more a year.

3. Accident- Environmental conditions that would be experienced as a result of high energy pipe breaks outside containment, or a large, intermediate or small LOCA or main stream line break inside containment.

All analyses performed to determine the service conditions were performed consistent with the guidelines of IE Bulletin 79-01B and NUREG-0588 and in accordance with either TVA quality assurance procedure EP 3.03 or General Electric's internal quality assurance program. B. Temperature and Pressure Inside Containment The controlling breaks for the pressure response of the drywell and wetwell and the temperature response of the wetwell are the large LOCA Design Basis Accident'DBA) and the Intermediate Break Accident (IBA) . The DBA and a 0.5 ft steam leak produce the most severe temperature transient in the drywell. The containment pressure and temperature response for all breaks were evaluated by the methods discussed in General Electric Report No. NEDO-20533, June 1974. Mass and energy releases were calculated using the methods also discussed in the above General Electric report. Details of the analyses are provided in PSAR, section 14 and General Electric Report NEDO-24580. 0(l Franklin Research Center A-54 h DivlSiOn ct The Fronton tnsututc

TER-C5417-4 C. Outside Containment High Energy Line Breaks Plant areas outside containment were reviewed to determine areas where high energy piping was located and could potentially produce effects that would impact safety-related equipment. The areas affected by high energy line breaks are the reactor building and the main steam valve vaults. Reactor Building The high energy lines located in the reactor building are: (1) High Pressure Coolant Injection (HPCI) steam supply to the pump turbine 547 F, 1020 psia, quality - 1. (2) Reactor Core Isolation Cooling (RCIC) supply to the RCIC pump turbine 547'F, 1020 psia, quality - l. (3) Reactor Water Cleanup (RECU) system - 547'F, 1020 psia, r quality - 0. Single-ended circumferential ruptures at the fluid conditions listed above were postulated. Mass and energy releases for all steam supply lines except one break of the RWCU were generated using the Moody critical flow correlation assuming an fL/D equal to zero. Upstream pressure and temperature, and therefore mass flow rates, were assumed to remain constant until the line was isolated. These steam supply lines isolate automatically on high temperature in the reactor building.. Temperature sensors are located in the vicinity of the line to assure rapid detection and isolation. Isolation times include signal process time, valve stroke time, and break detection time. The sensors used are redundant, class lE, and electrically trained. Mass and energy release of the remaining RWCU break was generated using the RETRAN computer code. Only this break requires operator action for isolation. Isolation was assumed to occur 10 minutes after the break. Detection is based on high fluid temperature at the discharge of the nonregenerative heat exchangers. The steam valve vault was modeled using three nodes and were input into the COMPARE-MOD1 computer code. No heat sinks were considered. ~ 00 Franklin Research Center A-55 A DI4sen or 1he Fcsnk5n Insatu(c

TER-C5417-4 The valve vaults at Browns Ferry were constructed with large blowout panels to provide pressure relief to the turbine building in the event of a pipe break. These paths were included in the model.

2. Radiation Environment The radiation environments inside the drywell and in the reactor building after a design basis LOCA were calculated consistent with the requirements of IE Bulletin 79-01B and NUREG-0588.

Initial airborne sources in the drywell were calculated assuming an instantaneous release of 100 percent of the core inventory of iodine. Transfer of iodine from the drywell free volume to the water in the torus was conservatively calculated as a function of time until the airborne concentration was reduced by a factor of 200 (considered to be at equilibrium) . Sources in the water in the torus were calculated assuming an instantaneous release, of 1 percent of the core inventory of the solid fission products and the iodine transferred from the drywell. Airborne activity in the reactor building was calculated based on a design basis leak rate from the primary containment and design flow of the SGTs. Source terms were calculated at various time after an accident allowing for decay and dose rates were calculated with a point-kernel-with-buildup computer code. Radiation exposures in the reactor building due to recirculation of the torus water through the RHR and containment spray- systems were also calculated. These dose rates were then integrated over the duration of the accident. 3 ~ Main Steam Valve Vaults The high energy lines in the valve vaults are the main steam lines and the main feedwater lines. Breaks in the main steam line are controlled from an environmental standpoint due to the large line size and the high energy associated with the steam. Conditions of the main steam are 550'F, 1050 psia, quality l. A double-ended rupture of the main steam coincident with a break of the 4-inch RCIC steam line was evaluated. Mass and energy releases were provided by General Electric. Break flow was terminated by isolation of the main steam lines based on signals from safety-related sensors. Il(l Franklin Research Center p;56 A Division of riie Frenkbn Inseosie

TER-C5417-4 4 ~ Operation Environmental Conditions An environmental listing of service conditions are tabulated in Table 1. The service conditions considered were pressure, temperature, humidity, and radiation. Normal and abnormal space ambient temperatures for nonaccident conditions were obtained from information used in the initial design phase of the plant in conjunction with data accumulated at the plant site in various spaces, for all units, under extreme outside temperature conditions (100'F outside atmosphere). Pressures and temperatures for accident conditions were obtained from transient curves and analysis which studied the effects of a LOCA on reactor zone spaces. Environmental service and conditions were only considered in the reactor, zone and primary containment. The control bay and electrical board room were not considered since their atmospheres did not interface with the reactor zone environment. The environmental table of service conditions was developed for various plant conditions including the following: normal average day, abnormal cohditions (outside temperature 96-100'nd maximum river water temperature exists), LOCA/HELB inside primary containment, HELB outside primary containment, and tornado (sudden pressure drop by 3 pounds per square inch) . Ill)ll FranMin Research Center A-57 A DMslen d The Franl4n lnscaute

I tl

TER-C5417-4 APPENDIX B EQUIPMENT ITEM TABLE This appendix contains the list of safety-related electrical items for Browns Ferry Nuclear Plant Unit 1 provided by the Licensee in the October 31 response to IE Bulletin 79-01B. This listing shows the equipment items by manufacturer and model number, plant locations, and time required to function as determined by the Licensee. Ill! Franklin Research Center B-1 A D&sion or The frankin Insiitute

TERM5417-4 PLANT NAME: BROWNS FERRY 1 EQUIPMENT LZCENSEE ITEM ITEM SUBMITTAL QUALZF ICATION NO DESCRIPTION LOCATION PAGE REFERENCES REFERENCES Solenoid Valve EEB-23-1001 None Atkoma tie 15830WP-VPZ Solenoid Valve EEB-32-1001 None AAA EEB-3 2-100 2 None SO2 Flow Indicating Switch 12 EEB-4 3-10 01 None Fischer & Porter 12 EEB-43-1002 None 10A2235A-55AR1011 Differential Pressure 14 EEB-64-1001 None Switch 14 EEB-64-1002 None Dwyer 14 EEB-64-1003 None 3302 14 EEB-64-1004 None

14. EEB-64-1005'EB-64-1006 None 15 None 15 EEB-64-1007 None 15 EEB-64-1008 None 15 EEB-64-1009 None 15 EEB-64-1010 None 15 EEB-64-1011 None 15 EEB-64-1012 None 14 EEB-64-1026 None 14 EEB-64-1041 None 15 EEB-64-1042 None Solenoid Valve 15 EEB-64-1013 None ASCO 15 EEB-64-1023 None HB830281RU 12 EEB-64-1024 None 14 EEB-64-1025 None 14 EEB-64-1028 None B-2 (ill Franklin Research Center A Ontrron of The frenkKn Inrettrte

TERM5 417-4 EQUIPMENT LICENSEE ITEN ITEN SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES Differential Pressure 14 EEB-64-1014 None Modifier 15 EEB-64-1015 None Honeywell 15 EEB-64-1038 None R7165-1078 Relay Assm. 122700 Terminal Assm. Differential Pressure 14 EEB-64-1016 None Indicator Controller 15 EEB-64-1017 None Fischer t'orter 15 EEB-64-1018 None 53EL3311BB1B ESL-01 Differential Pressure 14 EEB>>64-1019 None Transmitter 15 EEB-64-1020 None Fischer a Porter 15 EEB-64-1021 None 10B2494TBAB Temperature Element EEB-64-1027 None Weed SP6011AA3C275SN42 10 Temperature Element EEB-64-1039 None Weed EEB-64-1040 None SP6011AA3C275SN42 Solenoid Valve 13 EEB-64-1029 None ASCO 13 EEB-64-1030 None HB830081RU 15 EEB-64-1031 None 15 EEB-64-1037 None 12 Solenoid Valve EEB-64-1033 None ASCO EEB-64-1036 None HV200-924-1F EEB-64-1037 None 13 Plow Transmitter EEB-6 5-10 01 None GE/MAC 50-554212BKZZ3 Solenoid Valve EEB-67-1001 None ASCO EEB-67-1002 None HT8262A203A EEB-67-1003 None 15 Solenoid Valve EEB-76-1014 ASCO EEB-76-1015 None HT8262A203A EEB-76-1016 None B-3 (III Franklin Research Center A Ovation or The Ffankln hsoone

TERMS 417-4 0 EQUIPMENT LICENSEE ITEM . IT%4 SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 15 Cont. EEB-76-1017 None EEB-76-1018 None EEB-76-1019 None EEB-76-1020 None EEB-76-1021 None 16 Pressure Transmitter EEB-6 7-100 6 None Bailey EEB-67-1011 None 551 17 Flow Transmitter 8 EEB-67-1014 None GE/MAC 12 EEB-8 4-1007 None 555 12 EEB-84-1008 None 18 Temperature Switch 12 EEB-69-1001 None Fenwal 12 EEB-69-1002 None 18002-27 12 EEB-69-1003 None 12 EEB-69-1004 None 16 EEB-69-1005 None 16 EEB-69-1006 None 16 EEB-69-1007 None 16 EEB-69-1008 None 19 Solenoid Valve EEB-71-10 01 None ASCO EEB-71-1002 None HTX8300B61U 20 Solenoid Valve EEB-74-1001 None ASCO EEB-74-1002 None 8300C61U EEB-74-1003 None EEB-74-1004 None 21 Solenoid Valve EEB-75-1001 None ASCO EEB-75-1003 None HTX8300C61U 22 Solenoid Valve NEB-64-053A 32 ASCO HB830081F '3 Solenoid. Valve 6 EEB-76-1001 33 Valcor 6 EEB-76-1002 33 5 26D 6 EEB-76-1003 33 6 EEB-76-1004 33 6 EEB-76-1005 33 6 EEB-7 6-1006 33 B-4 ll!) FranMin Research Center A Divison of The Franklin Insrnutc

TERMS 417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REPERENCZS REFERENCES 23 Cont. 6 EEB-76-1007 33 6 EEB-76-1012 33 6 EEB-76-1013 33 Solenoid Valve EEB-76-1008 33 Valcor EEB-76-1009 33 526D EEB-76-1010 33 EEB-76-1011 33 25 Solenoid Valve EEB-77-1004 None ASCO HB830081RP 26 Solenoid Valve EEB-84-1001 34 Target Rock EEB-84-1002 34 73FF-005 EEB-84-1003 34 EEB-84-1013 34 27 Solenoid Valve 12 EEB-84-1004 None ASCO T8210C87 28 Solenoid Valve 12 EEB-84-1006 None ASCO HT8211C94 29 Indicator Pressure 12 EEB-84-1009 None Converter 12 EEB-84-1010 None Fisher Controls 546 30 Pressure Switch 12 EEB-84-1011 None Custom Components 12 EEB-84-1012 None 630GH 31 Solenoid Valve EEB-85-1001 None ASCO EEB-85-1002 None WPHT8316E36 32 Component Assembly 9r R2g S EEB-90-0001 35, 36~ 37 Nuclear Measurements 8r R2g U EEB 90 0004 35, 36~ 37 Corp. 8g R2g U EEB 90 0007 35, 36~ 37 No Model No. B>>S IlIl Franklin Research Center A Division ot %ho Frankln Insotute

TERM5 417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAI QUALIFICATION NO ~ DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 33 Thermostat 14 MEB-63-01 38 Honeywell T675A1508 34 Damper Motor Or 6r 8g MEB 64 01 None Honeywell 15 M445A 35 Thermostat 2g 3r 4g MEB 64 02 39 Honeywell 5 T675A1540 36 Motor-Operated Valve MEB-67-01 40 Limitorque NEB-1-013 40 SMB-000 NEB-23-029 40 37 Motor-Operated Valve MEB-67-02 40 Limitorque NEB-1-012 40 SMB-000 38 Motor-Operated Valve MEB-73-02 40 Limitorque MEB-74-01 40 '9 SMB-000 MEB-71-02 40 Motor MEB-77-01 None GE 5K6226XJ3000A 40 Motor MEB-77-04 None GE MEB-77-06 None 5K4 254XL2 41 Motor-Operated Valve 12g 13 MEB-78-01 None Rotork 14A 42 Pressure Solenoid NEB-1-002 41 Operator Target Rock 1/2 SMS-A-01 43 Pressure Solenoid NEB-1-002A 42 Operator NEB-43-030 42 ASCO WPHTX8300B68F B-6 Ill Franklin Research Center A DMsion d The f'rsnkSn Insotu(e

TERM5 417-4 EQUZ PMENT LICENSEE ITEM ITEN SUBMITTAL QUALIFICATION NO ~ DESCRIPTION LOCATION PAGE REFERENCES REFERENCES Differential Pressure 4 NEB-1-003 None Indicator Switch Barton 278 Solenoid Operator NEB-1-005 None Automatic Valve Corp. C-5497 46- Solenoid Operator NEB-1-007 None Automatic Valve Corp. C-5497 Temperature Switch NEB-1-008 43 Fenwal 17002&0 48 Temperature Switch NEB-69-81 43 Fenwal 17002%0 49 Pressure Switch NEB-3-015 44'5 Barksdale NEB-11-018 44, 45 B2T-A12SS NEB-11-021 44'5 50 Pressure Switch NEB-71-84 44I 45 Barksdale NEB-73-128 44, 45 B2T-A12SS 51 Level Indicator NEB-3-016 46 Switch NEB-3-017 46 Yarway NEB-3-019 46 4418C NEB-3-0 21 46 NEB-3-022 46 52 Pressure Switch NEB-3-021A 47, 48 Barton NEB-75-226 47'8 288 53 Pressure Switch NEB-68-7 2A 47'8 Barton NEB-71-83 47'8 288 B-7 l!9 Franklin Research Center A GMaan d The Frsnk5n hsau(e

TERM5 417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 54 Level Indicator 9 NEB-3-0 23 47'8 Switch Barton 288A 55 Level Indicator NEB-7 3-129 47, 48 Switch Barton 288A 56 Temperature Element NEB-23-025 None

           ,Calmatic                                    NEB-23-027             None 158B7061P016                                NEB-74-209             None 57           Motor-Operated Valve                        NEB-23-026             49 Limitorque                                  NEB-74-205             49 SMB-2                                       NEB-75-222             49 NEB-75-224             49 NEB-74-196             49 NEB-74-196A            49 NEB-74-197             49 NEB-7 4-19 7A          49 NEB-75-235             49 NEB-75-237             49 NEB-74-206             49 58          Motor-Operated Valve                        NEB-68-069             49 Limitorque                                  NEB-73-130             49 SMB-2 59          Motor-Operated Valve                        NEB-73-149             49 Limitorque                                  NEB-75-217             49 SMB-2                                       NEB-75-234             49 60          Motor-Operated Valve                        NEB-73-168             49 Limitorque                                  NEB-73-147             49 SMB-2                                       NEB-74-204             49 NEB-74-193             49 NEB-74-195             49 61          Flow Transraitters                          NEB-23-028             None GE 50-555111BOAA3AAA B-8'
     !l!j FranMin Research Center h Division oi The Frsnirln Insottrte

TERMS 417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 62 Flow Transmitters . NEB-71-116 None GE 50-555111BOAA3AAA 3 NEB-75-220 None 1 NEB-7 3-16 5 None 2 NEB-74-189 None 2 NEB-74-190A None 4 NEB-75-223 None 5 NEB-74-199 None 5 NEB-74-203 None 63 Motor-Operated Valve 8 NEB-23-029 49 Limitorque 6 NEB-71-126 49 SMB-0 0 6 NEB-70-82 49 7 NEB-71-96 49 12 NEB-74-207 49 6 NEB-74-194 49 64 Motor-Operated, Valve NEB-71-85 49 Limitorque NEB-74-208 49 SMB-00 65 Motor-Operated Valve NEB-71-10 7 49 Limitorque NEB;71-108 49 SMB-00 NEB<<71-109 49 NEB-74-230 49 66 Solenoid Valve 0, NEB-43-030 42 ASCO

           'WPHTX8300B68F 67           Limit Switch                               NEB-43-031             None Micro Switch                               NEB-43-033             None OPD-AR OPD-AR30 68           Solenoid Valve                    12       NEB-43-032             42 ASCO X8300-B61F 69           Temperature Switch                14       NEB>>63-034             None Fenwal 40-104014-103 B-9

()Il Franklin Research Center A trnision or The Ffank5n insotu<e

TERM5 417-4 EQUI PMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 70 Temperature Element 14 NEB-63-0 35 None Fenwal 28-232106-304 ,71 Pump Motor 14 NEB-63-037 None GE 5K326PK-234A 72 Explosive Valve 14 NEB-6 3-0 38 50, 51

                                          'onax 1832-117 73          Solenoid Valve                      8        NEB-64-039             42 ASCO                                8        NEB-64-040             42 WPHTX8300B45Fg R                    12       NEB-64-047             42 8        NEB-64-053             42 8        NEB-7 6-24 2           42 74         Limit Switch                                 EEB-1-1007             52 NAMCO                                        EEB-1-1009             52 EA740-50100                                  EEB-1-1004             52 EEB-1-1005             52 75         Limit Switch                                 EEB-1-1008             52 NAMCO                                        EEB-1-1010             52 EA740-50100                                  EEB-1-1003             52 EEB-1-1006             52 76         Limit Switch                        12       NEB-64-052             None NAbKO                               8        NEB-64-054             None D1200G                              8        NEB-64-056             None 8        NEB-64-056A            None 8,       NEB-76-239             None 8        NEB-64-041             None 8        NEB-64-043             None 8        NEB-64-045             None 12       NEB-64-048             None 8        NEB-64-050             None 8       NEB-76-239A            None 8        NEB-76-239B            None 8        NEB-76-239C            None 8        NEB-85-268A            None 77          Pressure         Switch                     NEB-64-046             53'4,     55 Barton 289 B-10 Ill FranMin     Research Center A Glvbion d The F(aalu Insututc

TERM5417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 78 Pressure Switch NEB-71-115 53, 54, 55 Barton NEB-73-164 53, 54, 55 289 NEB-74-188 53, 54, 55 NEB-75-219 53, 54, 55 79 Pressure Transmitter NEB-64-058 None GE/hRC NEB-64-059 None 5 510 32CAAEl NEB-64-068 None 552032KAAT1 NEB-73.-097 None 556220BAAAl NEB-71-105 None 50-551032EAAE1 NEB-71-110 None 50-551032CAAY1 NEB-73-157 None 50-551032EAAK1 NEB-73-163 None 50-551032GAAN1 NEB-74-190 None NEB-74-200 None NEB-74-210 None 80 Power Supply 12 NEB-64-060 None GE 12 NEB-71-098 None 583001AAGK1 570012FAAC1 81 Level Transmi tter NEB-64-063. 56, 57 Rosemount NEB-64-067 56, 57 1151 Series 82 Temperature Element NEB-64-062 None American Standard NEB-64-063 None 158B7079P051 83 Pressure Switch NEB-64-064 58 Static-0-Ring NEB-64-065 58 12N/AA4 NEB-64-066 58 84 Motor-Operated Valve NEB-64-070 49 Limitorque NEB-74-186 49 SMB-3 85 Motor-Operated Valve NEB-69-073 49 Limitorque SMB-0 86 MotorMperated Valve NEB-69-074 49 Limitorque SMBW B-ll (II Franklin Research Center A Dvlaon d The ftaudln Insane

TERMS 417-4 EQUIPMENT LICENSEE ITEM ITEN SUBMITTAL QUALZF ICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 87 Motor-Operated Valve NEB-71-10 0 49 Limitorque NEB-73-160 49 SMB-0 NEB-73-169 49 NEB-75-214 49 NEB-73-161 49 NEB-75-227 49 88 Temperature Element NEB-74-213 None Scam NEB-74-213A S51-1 NEB-73-174 NEB-71-120 89 Temperature Element '8 NEB-74-213B None Scam 12 NEB-74-213C None S51-1 17A NEB-69-76 None 17B NEB-69-77 None 18 NEB-69-78 None ll 10 NEB-69-79 NEB-69-80 None None 8 NEB-74-181 None 90 Temperature Element 6 NEB-74-213D None Scam 6 NEB-71-121 None S51-1 6 NEB-73-175 None 91 Temperature Switch -3 NEB-71-089 3g 43 Fenwal 1 NEB-71-089A 3g 43 17023-6 1 NEB-71-131 3g 43 1 NEB-71-132 3, 43 1 NEB-71-136 3, 43 92 Temperature Switch NEB-71-090 3, 43 Fenwal NEB-73-135 3g 43 17023-6 NEB-73-141 3g 43 NEB-73-142 3g 43 93 Valve NEB-71-101 None Terry Turbines NEB-71-102 None Type GS NEB-71-103 None NEB-71-122 None NEB-71-123 None NEB-71-124 None NBB-71-125 None B-12

     !![i Franklin Research Center A ~son or The Frsnksn Insatutc

TER-C5 417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIP ICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 94 Pressure Switch 3 NEB-71-104 44'5 Barksdale PIH-M85SSV 95 Pressure Switch NEB-71-10 6 None Mercoid NEB-73-158 None DA-7043-804 NEB-75-216 None DA-23-804 NEB-75-229 None 96 Pressure Switch NEB-71-112 58 Static-0-Ring NEB-73-162 58 6N-AA21 6N-AA21-V 97 Square Root Converter 12 NEB-71-114 None GE 5 6510 OAAACl 98 Motor-Operated Valve NEB-71-117 49 Limitorque NEB-71-118 49 SMB-1 NEB-71-119 49 NEB-75-221 49 NEB-74-179 49 99 Turbine Controls NEB-73-148 None Terry Turbines NEB-73-154 None Type CCS NEB-73-151 None NEB-73-155 None NEB-73-171 None NEB-73-172 None NEB-73-173 None NEB-73-173A None 100 Pressure Switch NEB-73-156 44'5 Barksdale D2H-M150SS 101 Motor-Operated Valve NEB-73-167 49 Limitorque NEB-73-166 49 SMB-4T NEB-73-170 49 102 Level Switch NEB-73-176 None Robertshaw SL-20 2-A2X B-13 000 FranMln Research Center A DQsion nt The FtanM[n Institute

TERM5 417-4 EQUI PMENT LICENSEE ITEM ITEM SUBMITTAL QUALIPICATION NO ~ DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 103 Pressure Switch 2 NEB-73-180 58 Static-0-Ring 2 NEB-73-180A 58 5N-AA3 5 NEB-73-184 58 5 NEB-73-184A 58 104 Motor-Operated Valve NEB-74-191 49 Limitorque SMB-5T 105 Motor-Operated Valve NEB-74-19 2 49 Limitorque SMB-4 106 Motor-Operated Valve NEB-74-202 49 Limitorque SMB-4 107 Differential Pressure NEB-74-198 48, 53 Indicator Switch Barton 289A 108 Pump Motor NEB-74-211 None GE NEB-74-212 5K6348XC23A 109 Plow Switch NEB-75-232 53, 54 Barton 289 110 Pump Motor NEB-75-238 None GE 5K6336XC198A NEB-75-238A None Solenoid Valve NEB-76-240 42 ASCO NEB-76-241 42 X8315 C28 112 Hydrogen Element NEB-76-243 None GE 47E226428G2 113 Level Switch NEB-77-244 None GEMS XM-36425 B-14 009 Franklin Research Center A almsman Ol The F~ank5n Insatute

TER-C5417-4 EQUI PMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 114 Solenoid Valve 6 NEB-77-249 None Versa VSG-35 21 115 Limit Switch NEB 77-249A None Micro Switch NEB-77-249B None BZE6-2RN 116 Level Switch 2 NEB-77-250 None Autocon 5 NEB-77-251 None M-4 4 NEB-77-260 None 4 NEB-77-261 None 117 Temperature Element NEB-77-252 None Thermo-Elec t NEB-77-259 None Bj 582-1 118 Level Switch 13 ,

                                                       = NEB-78-262             None Meltron 9 241-6S S10A 119          Level Switch                    13           NEB-78-265             44r 45 Barksdale D2H-M18SS 120          Solenoid Valve                               NEB-85-267             None ASCO                                         NEB-85-268             None HVA86-030 121         Position Switch                              NEB-85-272             None Micro Switch                                 NEB-85-273             None BZE6-2RN 122'olenoid                     Valve                    NEB-85-274             None ASCO HVA-90-405-2A 123         Level Switch                                 NEB-85-276             None Robertshaw SL-305-E3-X B-15 0II Franklin Research Center A Division ot The FfenMin Insstvte

TERM5417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALZFZCATZON NO ~ DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 124 Zon Chamber NEB-90-279 None GE NEB"90-280 None 2 37X7 31G001 NEB-90-281 None NEB-90-282 None 125 Sensor and Converter 15 NEB-90-283 None GE 15 NEB-90-284 None

          =194X927G014,12 126         Fission Product                           NEB-90-286            None Monitor                                 NEB-90-286A           None GE No      Model No.

127 TIP Valve Assembly NEB-NM-287 None GE 136B1302G2 128 Motor Control Center 12 EEB-APS-0009 None International Switchboard Corp. No Model No. 129 Motor Control Center EEB-APS-0007 None GE EEB-APS-0209 None 7700 Series 130 Motor Generator 12 EEB-APS-0191 59 Louis Allis Co. 12 EEB-APS-0192 59 8-127033 13 EEB-APS-0193 59 13 EEB-APS-0194 59 131 Transformer 12 EEB-APS-0203 None GE 12 EEB-APS-0204 None No Model No. 13 EEB-APS-0207 None 132 Solenoid Valve EEB-1-10 01 None Target Rock EEB-1-1002 None 1/2 SMS-A>>01-1 133 Junction Box Various Numerous 19'0 B-16 000 Franklin Research Center A Division ot Tba Ftonk5n Inset(c

TERM5 417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. OESCRZPTION LOCATION PAGE REFERENCES REFERENCES 134 Terminal Block 6 EEB-77-0064 24r 25r 26 GE 12 EEB-78-0060 24, 25r 26 EB-5 and CR15182 12 EEB-84-0056 24, 25'6 12 EEB-84-0059 24, 25, 26 6 EEB-76-0077 24, 25, 26 8 EEB-90-0160 24, 25, 26 Various EEB-67-0042 EEB-01-0101 24'5'6 0 24, 25, 26 7 EEB-01-0102 24'5g 16 8 .EEB-23-0037 24r 25'6 0 EEB-32-0013 EEB-4 3-00 31 24'5'6 12 24, 25, 26 0 EEB-43-0032 24, 25, 26 0 EEB-74-0391 24, 25, 26 Various EEB-74-0392 24, 25'6 Various EEB-73-0127 24, 25, 26 Various EEB-75-0145 24'5, 26 Various EEB-69-0106 24, 25r 26 Various EEB-71-0250 24'5'6 12 EEB-63-0067 24, 25'6 Various EEB-64-0039 24r 25'6 135 Electrical Penetration EEB-74-0239 22 Assembly EEB-76-0022 22 GE EEB-76-0023 22 Series 100 EEB-01-0090 22 EEB-68-0026 22 EEB-68-0029 22 EEB-64-0025 22 EEB-71-0082 22 EEB-73-0135 22 136 Electrical Penetration 00 EEB-76-0024 50 Assembly GE NS04 137 Electrical Penetration 0 EEB-Ã4-0004 14 Assembly 0 EEB-NM-000 5 Physical Sciences Corp. 0 EEB-NM-0006 PSC P/N 2019C 0 .,EEB-NM-0007 0 EEB-NM-0008 0 EEB-NM-0009 franklin 0 EEB-NM-0010 0 EEB-NM&011 B-17 ll!j Franklin Research Center A 0%sion or The Inseam(c

TERM5417-4 EQUIPMENT LICENSEE ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 138 Electrical Penetration EEB-74-0240 21 Assembly EEB-01-0087 21 Physical Sciences Corp. EEB-01-0088 21 PSC P/N 2022C EEB-01-0089 21 EEB-43-0003 21 EEB-76-0019 21 EEB-64-0058 21 EEB-73-0134 21 EEB-71-0083 21 EEB-68-0027 21 EEB-68-0028 21 EEB-69-0030 21 EEB-69-0031 21 139 Switches 4 EEB-77-0067 61 GE and Cutler Hammer 0 EEB-74-0400 61 GE-CR294 0 8 EEB-23-0040 61 CH-10 250T 7 EEB-01-0107 61 Various EEB-75-0148 61 Various EEB-73-0136 61 Various EEB-74-0397 61 Various EEB-71-0253 61 140 Cable (See Manu- Various Numerous facturers List) B-18 llll Franklin Research Center A Olvlson at Thc Freedman Insotute

TER-C5417-4 APPENDIX C SAFETY SYSTEMS FOR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED The Licensee has submitted a list of safety-related systems which must function in order to mitigate the consequences of a design basis accident. This information was submitted in response to 1E Bulletin 79-01B and was included, in the Licensee's October 31, 1980 response.

     !Ill Franklin Research Center A Division ot The Franrcrrn Insrrrure

TER-C5417-4 ~ Main Steam ~ Feedwater ~ Fuel Oil ~ Residual Heat Removal Service Water ~ Raw Cooling Water ~ Ventilating ~ Air Conditioning ~ Control Air ~ Sampling ~ Standby Liquid Control Primary Containment Standby Gas Treatment Emergency Equipment Cooling Water Reactor Recirculation Reactor Water Cleanup Reactor Building Closed Cooling Water Reactor Core Isolation Cooling High Pressure Coolant Injection Residual Heat Removal Core Spray Containment Inerting Radwaste Fuel Pool Cooling Containment Atmosphere Dilution Control Rod Drive Neutron Monitoring Radiation Monitoring Auxiliary Power (Il Franklin Research Center C-2 A Snsion ol The Fnnk5n Insolate

TERM5417-4 APPENDIX D - CABLE MANUFACTURERS LIST

1. Brand-Rex

2. Rome Cable

3. Cyprus

4. American Insulated Wire 5~ Plastic Wire a Cable Corp.

6. General Cable

7. Continental Wire a Cable

8. PWC

9. Tamaqua

10. Boston Insulated Wire

11. Okonite

12. Rockbestos

13. Belden Corp.

14. ITT Surp.

15. Sumitomo Sho)i

16. Essex

17. Phelps Dodge

18. Triangle Conduit & Cable

19. GE Cable Corp.

20. Sies Electric

21. Graybar

22. Simplex Wire a Cable

23. Times Wire a Cable

24. Dearborn Wire

25. Alpha Wire Corp

26. Belden

27. Consolidated Wire

28. Anaconda

29. Collyer Insulated Wire

!)tl Franklin Research Center A Olvlsian of The Fiau4n Insatuie

I k I i

TERMS 417-4 APPENDIX E EQUIPMENT ITEM CROSS-REFERENCE FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM SECTION 1 4 '.2.1 2 4 '.2.1 3 4.5.2.2 4 4.5.2.3 5 4 '.2.4 6 4 '.2.5 7 4 '.2.6 8 4 '.2.7 9 4 '.2.8 10 4.5.2.8 11 4.5.2.9 12 4.5.2 ' 13 4 '.2.10 14 4.5.2.9 15 4.5.2.11 16 4.5.2.12 17 4 '.2.3.3 18 4.5.2.14 19 4.5.2.15 20 4.5.2.16 21 4.5.2.17 22 4.6.1 23 4.5.2.67 24 4.5.2.67 25 4.5.2.18 26 4 '.1.1 27 4.5.2.19 28 4.5.2.20 29- 4.5.2.21 30 4.5.2.22 31 4.5.2.23 32 4.6.2 33 4.5.2.24 34 4 '.2.25 35 4.5.2.24 36 4.5.2.63 37 4 '.3 38 4 '.3 39 4 '.2.26 40 4 ' '.26 llllll Franklin Research Center h Onrrron of Thc Frsnrrln rnrorrrre

TER-C5417-4 FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM SECTION 41 4 '.31 42 4.6.4 43 4.6.32 44 4.5.2-64 45 4 '.2.65 46 4.5.2.65 47 4.6.5 48 4.6.5 49 4.6.6 50 4 '.6 51 4.5.2 '7 52 4.6.7 53 4.6.7 54 4 '.8 55 4.6.8 56 4.5.2.28 57 4 '.10 58 4.6.9 59 4 '.9 60 4 '.10 61 4 '.2.29 62 4 '.2.29 63 4 '.10 64 4.6.9 65 4' 9 66 4.6.32 67 4.5.2.30 68 4.6.11 69 4.5.2.31 70 4. 5.2. 32 71 4.5.2.66 72 4 '.33 73 4.6.12 74 4.6.36 75 4 ' '6 76 4 '.2.33 77 4.6.34 78 4.6.13 79 4.5.2.34 80 4 '.2 35 81 4 '.14 82 4 '.2.36 83 4.6.35 84 4.6.9 85 4.6.9 86 4.6.9 87 4.6.9 E-2 00 Franklin Research Center A Ovtsen of The Frank5n Iroatutc

TER-C5417-4 FINAL TECHNICAL EQUI PMENT EVALUATION REPORT ITEN SECTION 88 4 '.2.37 89 4.5.2.37 90 4 '.37 91 4.6.15 92 4.6.15 93 4.5.2-38 94 4.6.16 95 4.5.2 39 96 4.6.17 97 4.5.2.40 98 4.6.9 99 4.5.2.38 100 4.6.18 101 4.6.19 102 4.5.2.41 103 4.6.20 104 4.6.21 105 4.6.22 106 4.6 '1 107 4.6.23 108 4.5.2.42 109 4.6.24 110 4 '.2.43 ill 112 4 ' '5 4.5.2.44 113 4.5.2.45 114 4.5.2.46 115 4.5.2.47 116 4.5.2.48 117 4.5.2.49 118 4.5.2.50 119 4.6 26 120 4.5.2.51 121 4.5.2.52 122 4.5.2.53 123 4.5.2.54 124 4.5.2.55 125 4.5.2.56 126 4.5.2.57 127 4.5.2.58 128 4.5.2.59 129 4.5.2.60 130 4.6.27 131 4.5.2.61 132 4.5.2.62 133 4.7.1 I E-3 Il() Franklin Research Center A Civisen et The Fsenhin Insetute

TERM5417-4 FINAL TECHNICAL EQUIPMENT EVALUATION REPORT ITEM SECTION 134 4. 6.28 135 4. 5. 2. 68 136 4.3.1.2 137 4.6.29 138 4.3.1.3 139 4 '.30 140 4 '.2 (l) Franklin Research Center A Ohssion d The Fssnldin Institute}}