ML20004D981

Equipment Environ Qualification, Final Draft Technical Evaluation Rept

ML20004D981
Person / Time
Site:	Quad Cities
Issue date:	01/31/1981
From:	Crane C FRANKLIN INSTITUTE
To:
Shared Package
ML20004D978	List: ML20004D980 ML20004D981
References
IEB-79-01B, IEB-79-1B, TER-C5417-013, TER-C5417-13, TER-C5417-13-DRFT, NUDOCS 8106100439
Download: ML20004D981 (150)

Text

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O TECHNICAL EVALUATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION C0m0NWEALTH EDISON CCMPANY QUAD CITIES NUCLEAR POWER STATION UNIT 2 NRC DOCKET NO. 50-265 NRC TAC NO. 42479 FRC PPOJECT C5417 FRC TASK 13 EG&G IDAHO, INC. SU BCONTRACT NO. K-7615 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 l

This report was prepared as an account of work performeo tinder a subcontract from EG&G

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Idaho. Inc., a prime contractor to the United States Department of Energy. Neither EGoG l

nor the United States Government nor any agency therec,t. or any of their employetts.

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makes any warranty. expressed or implied, or assumes any iegal liacility or responsibility for any third carty's use, or the results of such use, or any information. apparatus. product or process disclosed in this report, or 'epresents that its use by such thiro party would not infringe privately owned rights.

l NOT E - THIS IS A DRAFT 1

i Because of schedule limitations, this report draf t has not gone througn 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.

THIS DOCUMENT CONTAINS Ds l POOR QUAllTY PAGES .- hh h Franklin Research Center l

A Division of Tne Frankhn inst 2tute The Benjamin Franen Park.ay PNta Ps ' i' M 2'.5 + 448 ' OE 8188106489

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TECHNICAL EVALU ATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION CON 10NWEALTli EDISON C0fPN#

QUAD CITIES NUCLAR PC'fR STATION UNIT 2 NRC DOCKET NO. 50-265 NRC TAC NO. 42479 FRC PROJECT C5417 FRC TASK 13 EG&G IDAHO, INC. SU BCONTRACT NO. K-7615 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 from EGdG Idaho. Inc., a prime contractor '.o the United States Department of Energy. Neither EGoG nor the United States Government nor any agency therecf. or any of their employees.

makes any warranty, expressed or implied, or assumes any iegalliacility or responsioility for any third carty's use or the results of such use, or any information. apparatus. product j

or process disclosed in this report, or represents that its use cy such third carty would not i infringe privately owned rights.

i NOTE -THIS IS A DRAFT Because of schedule limitations. this report draft has not gone througn the complete i 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 :s completed b.J Franklin Research Center A Division of The Franklin Institute The Beniam n Franen Paru*ay PN a Ps :i 03 2 : 5 443 : W;

o a TER-C5417-13 CONTENTS Section Title Page 1 INTRODUCTION. . . . . . . . . . . . . . 1-1 1.1 Purpose of the Review . . . . . . . . . . 1-1 1.2 Generic Issue Background . . . . . . . . . 1-1 1.3 Specific Issue Background . . . . . . . . . 1-6 1.4 Scope of the Review . . . . . . . . . . 1-7 2 NRC CRITERIA FOR ENVIRONMENTAL QUALIFICATION. . . . . . 2-1 2.1 Criteria Provided by the NRC . . . . . . . . 2-1 2.2 Staff Positions and Supplemental Criteria . . . . . 2-1 2.2.1 Service Conditions Inside Containment for a Loss-of-Coolant Accident. . . . . . . . 2-1 2.2.2 Submergence . . . . . . . . . . . 2-2 2.2.3 Equipment Located in Areas Normally Maintained at Room Conditions . . . . . . . . . 2-2 2.2.4 Simulated Service Conditions and Test Duration . . 2-3 2.2.5 Deferment of Qualification Review . . . . . 2-3 2.2.6 Test Sequence . . . . . . . . . . 2-4 l

i 2.2.7 Radiation . . . . . . . . . . . 2-4 3 METHODOLOGY USED BY FRC . . . , . . . . . . . 3-1 4 TECHNICAL EVALUATION. . . . . . . . . . . . 4-1 i

4.1 Methodology Used oy the Licensee . . . . . . . 4-1 4.1.1 Environmental Conditions . . . . . . . 4-1 4 .1. '. Aging . . . . . . . . . . . . 4-3 4.1.3 Identification of Electrical Components . . . 4-3 4 .1. 4 Qualified Life . . . . . . . . . . 4-4 d . _h iiL

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, e TER-C5417-13 CONTENTS Section Title Page 4.2 Equipment Qualified for Plant Life. . . . . . . 4-5 4.2.1 NRC Category I.a Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines . . . . . 4-5 4.2.2 NRC Category I.b Equipment for Which Deviations From the DCR Guide-lines Are Judged Acceptable. . . . . . . 4-5 4.3 Equipment Qualified With Restrictions . . . . . . 4-6 4.3.1 NRC Category II.a Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines and Has a Service Life Less Than Plant Life. . . . . 4-6 4.3.2 NRC Category II,b Equipment That Fully Satisfies All Applicable Requirements of the DOR Guidelines Provided That

' Specific Modifications Are Made. . . . . . 4-6 4.3.3 NRC Category II.c Equipment for Which Deviations From the DOR Guidelines Are Judged Acceptable . . . . . 4-7 4.4 NRC Category III Equipment That Is Exempt From Qualification . . . . 4-8 4.5 Equipment for Which Documentation Contains Deviations From the Guidelines That Are Judged Unresolved. . . . 4-9 4.5.1 NRC Category IV.a Equipment Which Has Qualification Testing Scheduled but Not Completed. . . . . . . 4-9 I

4.5.2 NRC Category IV.b Equipment for Which a Qualification Documentation l in Accordance With the Guidelines Has Not 3een Established. . . . . . . . . . . 4-13 4.6 NRC Category V i Equipment Which Is Unqualified. . . . . . . . 4-41 4.7 NRC Category VI squipment for Which Qualification is Deferred . . . . 4-51

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TER-C5417-13 CONTENTS Section Title Page 5 CONCLUSIONS. . . . . . . . . . . . . . 5-1 6 REFERENCES . . . . . . . . . . . . . . 6-1 APPENDIX A - ENVIRONMENTAL SERVICE CONDITIONS APPENDIX B - EQUIPMENT ITEM TABLE APPENDIX C - SAFETY SYSTEMS FOR WHICH ENVIRONMENTAL QUALIFICATION IS TO BE ADDRESSED APPENDIX D - EQUIPMENT ITEM CROSS-REFERENCE LIST e.

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1. INTRODUCTION 1.1 PURPOSE OF THE REVIEW The NRC Office of Inspection and Enforcement (IE) isst.ed Bulletin 79-01B,

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

The objectives of the 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 equipm:nt is capable of performing its specifie4 design basis safety function when it is exposed to a harsh environment and (2) equipment whose qualification documentation is deficient, i.e., does not give reasonable assurance that the equipment is capable of performing it specified safety function.

To meet the overall program goals, the objective of chis Technical l

l Evaluation Report is to review the Licensee's submittals to determine if the l

i Licensee reviewed its safety-related electrical equipment for environmantal qualification in accordance with the DOR Guidelines and NUREG-0588 as required by IE Bulletin 79-0lB. The NRC will perform an audit of the qualification documentation references as part of its safety evaluation program. If discrepancies are found, the audit will be extended.

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

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a d TER-C5417-13 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 Yuus 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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TER-C5417-13 In addition, qualification requirements are also embodied in 10CFR50 Appendix A, General Design Criteria 1, 2, and 23 and Appendix B, Quality Assurance Criteria for Nucleac 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 f act that electrical components were of high industrial quality. Af ter 1971, qualification was judged on the basis of IEEE 323-71; however, no regulatory guide was issued adopting the 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 adcpted the most recent standard, IEEE 323-74.

• In 1977, the NRC 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 qualificaticn (SEP Topic III-12) was selected for accelerated evalua-tion as part of this program. Seismic qualification of equipment was to be addressed as a separate SEP topic. In December 1977, the NRC issued a generic letter to all SEP plant Licensees requesting that they initiate reviews to 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, 1 it was recommended that additional effort should be devoted to examining the installation and environmental qualification documentation of specific electrical equipment in all cperating reactors.

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TER-C5417-13 On May 31, 1978, the NRC Office of Inspection and Enforcement issued IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants," which required all Licensees of operating plants (except those included in the SEP program) to examine their installed safety-related electrical equipment and ensure appropriate qualification documentation for equipment function under postulated accident conditions.

Subsequently, on February 8,1979, the NRC Office of Inspection and Enforce-ment issued IE Bulletin 79-01, which was intended to raise the status of IE Circular 78-08 to the level of Bulletin, i.e., action requiring a Licensee response. This Bulletin required a complete re-review of the environmental qualification of safety-related electrical equipment as described in IE Circular 78-08.

The review of the Licensee responses indicated certain deficiencies within the scope of equipment addressed, definition of harsh environments, and adequacy of support documentation. It became apparent that generic criteria were needed to evaluate the elictrical equipment environmental qualification for both SEP and non-SEP operating plants. Therefore, during the second half of 1979, the Division of Operating Reactors (DCR) of the NRC issued internally a document entitled " Guidelines for Evaluating Environmental Qualification of Class lE 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 i

qualification documentation in accordance with the DCR Guidelines. However, initial NRC review of this documentation, which was compiled to support Licensee submittals, revealed the need for obtaining independent evaluations j and for accelerating the qualification review program.

t l In Cctober 1979, the NRC awarded Franklin Research Center (IRC) a contract to provide assis rance in the " Review and Evaluation of Licensing l Actiona for Operating Rea : tors," which included an assignment for review of equipment environmental c aalification under SEP Topic III-12. FRC was given l the assignment to review equipment environmental qualification documentation l

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TER-C5417-13 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 Sulletin 79-01B, which expanded the scope of IE Bulletin 79-01 and requested addi:Lonal information on environmental qualification of safety-related electrical equipment at operating facilities, excluding the 11 facilities undergoing the SEP review. This Bulletin stated that the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification are the 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 sesolved using NUREC-0588 as a guide.

In early Feocuary 1980, the NRC decided that Indian Point Uaits 2 and 3 and Zion Units 1 and 2 should be included w'ithin SEP Topic III-l* for tha purpose of equipment environmental qualification reviewi On February 21, I~ 10, the NRC a,nd 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 (29]* which included a second document,

" Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Is To Be Addressed," (29) l together with the request that the Licensees review their plant systems and provide additional equipment environmental qualification information to the NRC on an accelerated schedule.

For non-SEP plants, the NRC Office of Inspectio .nd Enforcement formed a t

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

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TER-C5417-13 review of the Licensees' responses to IE Bulletin 79-013, 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 staf f positions being issued in a supplement to IE Bulletin 79-OlB 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-80-21, [32]

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 achi've e 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 tne plants whose Licensees responded to IE Bulletin 79-01B. FRC was l given the assignment to evaluate the Licensee's equipment environmental l

qualification submittal and to present the resalts in the form of a Technical Evaluation Report for each plant.

l 1.3 SPECIFIC ISSUE BACKGROUND

! The staf f held regional meetings with the Licensees and interested parties during the week of July 13, 1*980 in various locations. The staff issued a second supplement to IE Bulletin 79-013, a response to significant questions raised during the public meetings, and two Orders. The Order dated May 30, 1980 required the Licensees to ecmply with the previously issued t

Commission Memorandum and Order of May 27, 1980 (CLI-80-21) . The above Orders l

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TER-C5417-13 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 79-013, highlighting the staff positions affecting the Licensees' responses, were issued September 29 and October 24, 1980, respectively.

1.4 SCOPE CF THE REVIEW l

Environmental qualification of safety-related electrical equipment was selected by the NRC for accelerated review. Therefore, the scope of this

. report is limited to equipment that must function to mitigate the consequences of a loss-of-coolant accident (LOCA) or high energy line break (HELB) and whose environment is adversely affected by"that event. In addition, IE Bulletin 79-OLB requires enviromental qualification for all safety-related electrical equipment exposed to a harsh environment in accordance with the DCR Guidelines or NUREG-0588. Harsh environstats 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 and (ii) radiation from fluids which are recirculated f rom inside containment to accomplish long-term cooling subsequent to an accident. Qualification aspects not included within the scope of this evaluation are:

e seismic qualification e equipment protection against natural phenomena e equipment operational service conditions (e.g., vibration, voltage, and frequency deviations) e equipment located where it is subject to outdoor environments e equipment protection against fire hazards e equipment protection against missiles.

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

e " Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors" (29]

e " Guidelines for Identification of That Safety Equipment of SEP Operating Reactors for Which Environmental Qualification Is To Be Addressed" (29]

e NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment." [33)

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 DCR screening guidelines.

2.2.1 SERVICE CONDITICNS INSIDE CONTAINMENT FCR A LOSS-CF-COOLANT ACCIDENT (DCR GUIDELINES SECTION 4.1)

For Pressurized Water Reactors (PWRs) , the DCR Guidelines state that the i 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) i 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) FWR Ice Condenser Lower Compartments --

l 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, (30]

"these values are a screening device, per the Guidelines, and can be used in Da 2-1

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TER-C5417-13 lieu bf 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 becsk condition should include ssperheated 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 1

and design considerations at the time the profiles were developed. The COR Guidelines and NUREG-0588 provide guidance and consideratiens required to determine if the calculated plant-specific temperature / pressure profiles encompass the LOCA and HELB accidents inside containment.

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

Equipment submergence (inside c'r outs'ide containment) should be addressed where the possibility exists that submergence of equipment may result from HELas or other postulated occurrences. Supplement 2 to IE Bulletin 79-013

[30] provides the following additional criterion: If the equipment satisfies the guidance and other requirements of the DOR Guidelines or NUREG-05a8 for the LOCA and HELB accidents, and the Licensee demonstrates that its failure will not adversely affect any safety-related function or mislead the operator af ter submergence, the equipment can be considered exempt from the submergence portion of the qualification requirements.

i 2.2.3 ECUIPMENT LCCATED IN AREAS NORMALLY MAINTAINED AT RCCM CCNDITIONS (DOR GUIDELINES SECTICN 4.3.3)

Supplement 2 of IE Bulletin 79-01B (30] permits deferment of the review l

of environmental qualification for all safety-related equipment items located l- in plant areas where the equipment is not exposed to the direct effects of a HELB or to nuclear radiation emanating f rom circulation of fluids containing radioactive substances. At the Licensee's option, the review may be deferred until after Fe'ruary c 1, 1981.

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TER-C5417-13 By June 30, 1982, all safety-related electrical equipment potentially exposed to a harsh environment in nuclear generating stations licensed to operate on or before June 30, 1982 shall be qualified to either the DOR Guidelines or NUREG-0588 (as applicable) . Safety-related electrical equipment is that required to bring the plant to a cold shutdown condition and to mitigate the consequences of the accident. It is the responsibility of the Licensee to evaluate the qualification of safety-related electrical equipment to function in environmental extremes not associated with accident conditions and to document it in a form that will be available for the NRC to audit.

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

2.2.4 SIMULATED SERVICE CCNDITIONS 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 i..itiation of the accident until the service conditions return to normal.

Supplement 2 to II Bulletin 79-013 [301 provides the following additional criterion: " Equipment designed to perforr. its saf ety-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 DEFERRENT OF QUALIFICATION REVIEW Supplement 3 to IE Sulletin 79-013 (31] permits the submittal of qualification documentation regarding the TMI Action Plan equipment and the equipment required to achieve and maintain a cold shutdown condition to be delayed as follows:

e qualification information for installed TMI Action Plan equipment must be submitted by February 1,1981.

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r TER-C5417-13 e' Qualification information for future TMI Action Plan equipment (reference NUREG-0737, when issued) , which requires NRC pre-implementation review, must be submitted with the f pre-implementation review data.

e Qualification information for TMI Action Plan equipment currently under NRC review should be submitted as soon as possible, o Qualification information for TMI Action Plan equipment not yet installed that does not require pre-imolementation review should be submitted to NRC for review by the Laplementation date.

e 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 SECTICN 5.2.3)

Supplement 2 to IE Bulletin "-013 (30] 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.

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

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

3. Test programs in progress should ce 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 SECTICNS 4.1. 2, 4. 2.2, and 4.3. 2, SUBITEM 2)

Supplement 2 to II Bulletin 79-013 (30] provides the following additional criteria:

"Both the DCR Guidelines and NUREG-0588 are similar in that they provide the methods for determining the raciation source term when considering LOCA events inside containment (100% nuble gases /50% iodine /16 partic-ulates) . These methods consider the radiation source term resulting f rom an event which completely depressurizes the primary system and releases the source term inventory to the containment.

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

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

When developing radiation source terms for equipment qualification, the Licensee must ensure consideration is given to those events which provide the most bounding conditions. The following table summarizes these considerations (RCS = reactor coolant system) :f LOCA Non-LOCA HELB Outside Containment NUREG-0578 NUREG-0588 (100/50/1 (10/10/0 in RCS) in RCS)

Insids Containment Larger of NUREG-0588 NUREG-0588 .

(100/50/1 -

(10/10/0 in Containment) in RCS) or NUREG-0578 (100/50/1 in RCS)

Gamma equivalents may be used when consideration of the 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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3. METHODOLOGY USED BY FRC IE Bulletin 79-01B required the Licensee to:

e provide a master list whien identifies the systems and electrical equipment required to function during and subsequent to an accident and to maintain the plant in a safe condition o provide the environmental service conditions e identify the submergence levels e provide written evidence of the qualification of the equipment identified e evaluate the qualification documentation using the DOR Guidelines and NUREG-0588 e submit a Licensee Event Report (LER) for electrical equipment determined not to be environmentally qualified.

The requirements of IE Bulletin 79-01B were requested under provisions of 10CFR5 0.54 ( 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 IE l

Bulletin 79-OlB and to provide a basis for the NRC Safety Evaluation Report l

(SER), FRC developed this Technical Evaluation Report (TER) by:

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

requirements of the DOR Guidelines as augmented by the supplements to the 79-01B Bulletin t

e using NUREG-0588 to resolve open issues.

l The results and conclusions contained in this report are valid assuming that the Licensee's analyses of test reports referenced in the Licensee submittal are correct. Review of test reports was not within the scupe of FRC's assignment. However, the NRC staff will audit selected analyses and fw

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• e TER-C5417-13 test reports, incorporating the results of the reviews with the conclusions of the TERs, when developing the plant-specific SERs.

The Licensee, Commonwealth Edison Co. , identified an extensive list of safety-related electrical equipment items in various locations of the Quad Cities Nuclear Power Station Unit 2 in its submittals to the NRC. FRC analyzed the Licensee's listing and grouped tcgether 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 122 different equipment items that formed the basis for the review. Appendix A contains the environmental service conditions for each location, Appendix 3 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 w3* reviewed by FRC in relation to:

e 'NRC DOR Guadelines, as modified by NRC staff interpretations e Licensee definition of harsh service environments (Appendix A) e analysis and/or justification of qualification e Licensee-proposed remedies for qualification deficiencies.

Topics not within the scope of FRC evaluation ares e completeness of the Licensee's listing of safety-related equipment e acceptacility of Licensee-provided environmental service conditions e acceptability of Licensee-stated position concerning safety system or component function e review and acceptability of qualificatica test reports and other qualification documentation.

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

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s TER-C5417-13 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 aasigned to one of the generic qualification categories provided by the NRC. NRC categories are described below.

All equipment item numoers discussed in Section 4 of this report are associated with Reference 34.

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 giv6.4 in the System Component Evaluation Work Sheets (SCIWS) of the Licensee's report. The details of this site inpection are documer.ted in an internal NRC memorandum (33) and will be addressed by the NRC.

NRC QUALIF'ICATIOW CATEGORIES AND DEFINITIONS e NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPT.ICA3LE REQUIREMENTS CF 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.

e NRC Category I.o EQUIPMENT FOR WHICH DEVIATIONS FROM THE DOR GUIDELINES ARE JUDGED ACCEPTABLE This category includes equipment items which do no. satisfy one or more of the applicable criteria defined in the DOR Guidelin' F r however, sufficient information has been presented to determine that the specific deviations are acceptable.

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r TER-CS417-13 e NRC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES 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 timo interval which is less than plant life, e NRC Category II.b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE OCR GUIDELINES PROVIDED THAT SPECIFIC MODIFICATIONS ARE .MDE 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 the designated date. When the modifications are complete, the equipment can be considered qualified, o NRC Category II.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 speci'fic deviations are judged to be acceptable for less than plant life or the specific deviations are judged oy FRC to be acceptable for less than plant life based on review 9f the applicable qualification documentation associated with the general equipment environmental qualification program.

e NRC Category III EQUIPMENT THAT IS EXEMPT FRCH 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), (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 subject to a potentially adverse environment as a result of accidents for which proper operation of the equipment is require.l. In addition, any failure of the exempt component must not degrade the ability of a qualified component to perform its required safety-related function.

l l e NRC Category IV.a l EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLET1?

t 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 l

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, I l TER-C5417-13 j 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.

e NRC Category IV.b

, EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION IN ACCORDANCE WITH THE 4

GUIDELINES HAS NOT BEEN ESTABLISHED 4

} 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

! cperation should be provided for each item.

e NRC Category V

. EQUIPMENT WHICH IS UNQUALIFIED The DOR Guidelines require that complete and auditable records reflecting I a comprehensive qualification methodology and program be referenced and made i available for review of all Class lE equipment.

h 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 .,uidelines can be categorized as follows: (i) documen-tation reflecting q1g?.ification as specified in the DOR Guidelines has not I been made available at review, (ii) qualification documentation made availaole for review is inadequate, or (iii) the documentation indicates that the equipment item has not passed the 2.q?lred tests.

j e NRC Category VI

EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED

! This category includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittals; however, the i 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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4. TECHNICAL EVALUATICN i

f 4.1 METHODOLOGY USED BY THE LICENSEE i

The final response to IE Bulletin 79-OlB from the Licensee dated November 1,1980 contained a general introductory section which described the Licensee's basic approach to qualification and evaluation methodology. A review by FRC has generated the following observations and concerns.

4.1.1 ENVIRONMENTAL CONDITIONS

1. The Licensee states in section 4.1 of its response the following approach to applying design basis event (DBE) conditions to equipment:

Where components, because of their location, could be subject to differing environments for the various accidents, the most severe

environmental conditions were utilized for qualification. Components i

located within compartments with postulated HELBs would be subjected to pressure, temperature, and humidity conditions resulting frcm that HELB, but would not be subjected to radiation doser in excess of 5 x 104 rads simultaneously. These same components could be subjected to radiation docer in excess of 5 x 104 rads following a -

LOCA, but these doses would not be simultaneous with pressure, temperature and humidity. To simplify this analysis, qualification data was initially sought which demonstrated operability of these

components for the combination of all environmental conditions. Where i

qualification could not be demonstrated for the entire spectrum of conditions simultaneously, components were evaluated for the l conditions associated with each individual accident. Environmental l conditions are based on the specific accidents for which the l components must f unc tion. Components which are exposed to harsh environments during accidents for which they are not required to function do not require qualification for these environments. Where qualification testing is to be performed, testing will be performed for each postulated environment separately.

FRC's position is that all components which have potential common-mode failures due to environmental stress must be qualified if any such failure woula adversely affect connected circuits. Therefore, equipment which has no l active function during a CBE cannot be exempted from qualification for this reason only. In addition, FRC is concerned that qualification for a short i

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r TER-C5417-13 cperating period may not be sufficient if failures in equipment at some point af ter a required operating period would adsarsely affect connected circuits.

FRC r.otes that short operating periods are given for some of the equipment listec in the Licensee's submittal. It was not obvious that the environments specified would remain as given if the additional i hour of operating time required by the NRC is added to the stated operating time.

2. The Licensee has used the following assumptions in evaluation of harsh and non-harsh areas:

a. Integrated doses have been calculated for areas outside the d rywe ll. Doses were established for i day, 30 days, and 1 year exposure. Integrated doses of less chan 5 x 104 rads during a component's service life are evaluated as nonharsh environmental conditions. Integrated doses of 5 x 104 rads and greater are evaluated as harsh environmental conditions.

For certain electronic equipment, such as process parameter transmitters, susceptibility to performance degradation may occur at threshold levels lower 4

than 5 x 10 rads. For other types of electrical equipment which do not contain electronic components, FRC does not expect noticeable degradation to 6ccur below 5 x 104 rads.

b. Environments were considered nonharsh when the temperature was controlled to 104*F or less and the maximum integrated radiation dose was less than 5 x 104 rads. Areas where infrequent temperature extremes up to 120*F could occur, and aeditionally, where

• mperature variations are not a result of the postulated accidenta ;.e considered to be mild environments. Equipment in these areas functions normally in the same anvironment as postulated for post-accident conditions. For nonharsh and mild environments, qualification data is not required.

FPC believes that the Licensee's approach is less conservative than is permitted by the Guidelines. It is FRC's understanding that power plant equipment is usually designed for an environment of 50-104'F, 30-70% RH, and negligible radiation dose. This is not intended to imply that the equipment should be expected to fail if the temperature rises to 105'F, but certainly questions could be raised if it rises above ll5'F and is exposed to high humidity and moderate radiation dose rates.

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TER-C5417-13 i

i For individual equipment items that have 120*F as the specified temperature, FRC has accepted that this is non-harsh provided that the elevated temperature is not a result of a DBE. .

4.1.2 AGING In Section 4.3.6 of the Licensee's response, the following statements about aging are made. i

a. The component a which are located outside the drywell and steam tunnel are exposed tt insignificant amounts of radiation during normal operating conditions. The ef fects of radiation aging are therefore not considered in the qualification evaluation of these components.

h. Most areas outside the drywell are maintained in a suitable environmental concition by safety-related EVAC equipment. The normal maximum environmental design temperature is 103*F, which in this study is a defined as a nonharsh environment (Section 4.3.4) . Thermal aging for these components is not required since the normal and post-accident environments are nenharsh. In addition, temperature extremes (up to 120*F) may occur in some plant areas. However, these conditions would result only during periods of extreme outdoor

, temperatures. Equipment designed and installed per industry standards would be capable of satisfactory operation without exhibiting

! aging-related degradation due to these temperature extremes.

Therefore, the effects of thermal aging are not considered for components located in areas where the maximum ambient temperature is maintained at 120*F or below.

4

) FRC's previous statements concerning radiation and temperature apply to these assumptions. It is not obvious that 120*F is due in all cases to causes atner than a DBE. The Licensee has not clarified this for individual equipment items listed in the Licensee's response.

4.1.3 IDENTIFICATION CF ELECTRICAL CCMPCNENTS The Licensee states that the FSAR was the casts for determining the equipment for which qualification documentation is required.

l The clearly stated NRC position is that equipment items needed for mitigation of an accident, including that identified in the Emergency Operation Procedures that the Licensee relies upon to mitigate CBEs 1

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TER-CS417-13 must he evaluated either to demonstrate qualification or to provide justification that unqualified equipment will not be misleading to the operator. Whether equipment is listed in the FSAR is irrelevant. The Licensee should assure that all safety-related electrical equipment has been identified and addressed. For example, it appears that splices, wire terminations, and connecting lugs have not been included.

4.1. 4 QUALIFIED LIFE The Licensee has not adequately addressed the topic of qualified life for any of the safety-relatec equipment identified by the Licensee as essential for safe shutdown of the plant. The DOR Guidelines required that equipment with ccmponents that are susceptible to degradation caused by thermal, radiation, or wear conoitions is 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 conoitions 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 icng as required after the accident. The qualified life may depend on carrying out a specified 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 when Justified by new information that permits a reanalysis of the qualification program.

It is necessary to establish a qualified life for every item 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.

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TER-C5417-13 4.2 EQUIPMENT QUALIFIED FCR 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 FULI,Y SATISFIES ALL APPLICABLE REQUIREMENTS OF THE COR GUIDELINES This section 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.

4.2.1.1 Equipment Item No. 117

Temperature Switches Located in the SW Corner Room Fenwal Model 17002-40 (Licensee References 18,19, and 26)

Licensee Reference 26 is a test report. The Licensea indicates that the qualification data is satisfactory.

4.2.2 NRC Category I.b --

EQUIPMENT ECR WHICH DEVIATIONS FRCM 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, sufficient information has been presented to determine that the specific deviations are acceptable. For the Quad Cities 2 plant, no items fall in this category.

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TER-C5417-13 4.3 EQUIPMENT QUALIFIED WITH RESTRICTICNS 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 equipment is qualified for a time interval less than plant life; or (iii) the equipment requires specific modification which, when ccmpleted, 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. 90 Solenoid Valves Located Outside the Drywell ASiO, Type NP-1 *

(Licensee Reference 24)

Licensee Reference 24 is not a qualification report for this item. This item has been placed in its most likely et,egory pending review of the qualification data.

4.3.2 NRC Category II.b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES PROVIDED THAT SPECIFIC MCDIFiCATIONS ARE .%DE Equipment items in this category will be fully acceptacle and will satisfy all applicable criteria defined in the DCR 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 the Quad Cities 2 plant, no items fall in this category.

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TER-C5417-13 4.3.3 NRC Category II.c EQUIPMENT FOR hTIICH DEVIATIONS FRCM THE DCR GUIDELINES ARE JUDGED ACCEPTABLE This section includes equipment items which do not satisfy one or more of the applicable criteria defined in the DCR 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 the Quad Cities 2 plant, no items fall in this category.

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TER-C5 417-13 4.4 NRC Category III EQUIPMENT THAT IS EXEMPT FRCM QUALIFICATICN Equipment items in this category 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. Foc Quad Cities Unit 2 no items fall into this category.

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TER-C5417-13 4.5 EQUIPMENT FCR WHICH CCCUMENTATICN CCNTAINS DEVIATICNS FRCM THE GUIDELINES THAT ARE JUCGED UNRESOLVED This section includes equipment items which are deficient on the basis that all criteria defined in the DCR Guidelines are not satisfied. However, the equipment item is either scheduled to be tes:ad or is judged to have a high likelihood of operability.

4.5.1 NRC Category IV.a M UIPMENT WHICH HAS QUALIFICATICN IESTING SCHEDULED BUT NCT CCMPLETED The qualification of the following equipment items has been judged deficient or inadequate based upon FRC's 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 cperation prior to testing should be prouided for each item. .

4. 5.1.1 Equipment Item No. 7 Pressure Transmitter Located in the NW and SW Corner Rooms General Electric Model 4532K11001 (Licensee References 11 and 19)

Licensee Reference 11 is a qualification report which will be reviewed later. This item has been placed in its most likely category pending review.

The Licensee makes the following statements and commitments:

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

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

Finally, should the operating equipment suffer degradation due to 4-9

• O TER-C5417-13 radiation exposure, the shut down redundant systes could be activated.

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

4. 5.1. 2 Equipment Item No. 8 Flow Transmitter Located in the NW and SW Corner Lxnes General Electric Model 4532K43001 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test repcets; therefore, qualification documentation is deficient for this item.

The Licensee makes the following sta*.ements and commitments:

A contract will be issued for seru 7e to qualify this equipment by analysis and/or testing, f ailing whic.; the appropriate equipment or parts thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic ,

models. Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant in3ection. This would result in radiation exposurer to only one of two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

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

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

l 4.5.1.3 Equipment Item No. 9 ylow Switch Located in the NW and SW Corner Rooms Barton Model 289 (Licensee References 18, 19, and 21)

Licensee Reference 21 is a qualification test report that we have not previously reviewed. The Licensee indicates that radiation was not addressed in this report and makes the following statements and commitments:

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

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TER-C5417-13 4 l I

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours af ter the postulated accident. During this time, action will be taken to shut down redundant systems beyond those I needed for coolant injection. This would result in radiation exposures to only one c 2 two redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

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

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

4.5.1.4 Equipment Item No. 54 Flow Transmitter Located in the NE and SE Corner Rooms General Electric Model GE/MAC 553 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

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

which occur several hours after the postulated accident. During this time, actio" will be taken to shut down redundant systems beyond those needed for :solant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also actual doses would i

be less than those calculated using such conservative assumptions.

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

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

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TER-C5417-13

4. 5.1. 5 Equipment Item No. 57 Pressure Switch Located in the NE and SE Corner Rooms Mercoid Model GN-L-3 (Licensee References 18 and 19)

Licensee References la and 19 are not qualification test taports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statement and commitments:

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

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

FinaA!v, should the operating equipment suffer degradation due to radiation exposure, the shut down reddndant system could be activated.

During the time available af ter stabilization of core coeling, additional coolant in]ection paths could be established, if necessar, to assure long term cooling.

4.5.1.6 Equipment Item No. 59 Pressure Transmitters Located in the NE and SE Corner Rooms General Electric, Mocel GE/MAC 551 50-55.132GAAW1 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification text reports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

l Radiation doses were calculated 2 sing conservative non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident. During this time, action will be taken to shut down redundant systems beyond those

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1 TER-C5417-13 needed for coolant injection. This would result in radiation exposures to_only one of two redundant equipment trains. Also actual doses would l be less than those calculated using such conservative assumpt ' ^*.

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

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

4. 5.1. 7 Equipment Item No. 60 Motor-Driven Pumps Located in the NE and SE Corner Rooms General Electric Model 5K6336XC193 (A,B,D)

(Licensee References 18 ano 19)

Licensee References 18 and 19 are not qualification text reports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

. justified for the following reasons:

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

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

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

During the time available af ter stabilization of core cooling, additional

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

4.5.2 NRC Category IV.b ECUIPMENT FOR hMICH QUALIFICATION COCUMENTATION IN ACCORDANCE WITH THE GUIDELINES EAS NOT BEEN ESTABLISHED The qualificacian of the following equipment items ie 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 4-13

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• tIR-C5417-13 auditable recoros reflecting comprehensive qualification cocumentation have not been made available for review. Specific justification for 'eterim plant operation should be provided for each item.

4.5.2.1 Equipment Item No. 3 Motor Operated Valve Located in the NW and SW Corner Rooms Limitorque Podel SMB-0-25 (Licensee References 18, 19, and 20)

Licensee Reference 20 is a test report for Limitorque valve cperators.

This item has been placed in its most likely category pending review of the qualification data.

4.5.2.2 Equipnent Item No. 4 Motor Operated valve Located in the Torus Area Limitorque Medel SMB-0-15 with Peerless AC Motor (Licensee References 18, 19, and 20)

Licensee References 18 and 19 are not qualification test reports.

Reference 20 is a test report on the radiation component only. This item has been placed in its most likely category pending review of the qualificatien cata.

4.5.2.3 Equipment Item No. 5 Motor Operated Valve Located in the Secondary Containment Area Limitorque Model SMB-2-40 with Reliance AC Mctor (Licensee Reference 7)

Licensee Reference 7 is a test report for a Limicorque valve actuator for Class lE service outside primary containment. This item has been placed in its most likely category pending review of the qualification data.

4.5.2.4 Equipment Item No. 6 Motor Operated valve Lccated in the Torus Area Limitorque Model SMB-000 with Reliance AC Motor (L3 censee Ref erence 7)

Licensee Reference 7 is a qualification type test report for a Limitorque valve actuator. The Licensee has not yet established the test time. FRC notes that the Licensee's submittal indicates that the potential accident radiation exposure exceeds that in the test report.

4-14

TER-C5417-13 The Licensee makes the following statements and commitments:

Additional vendor information is being sought to resolve outstanding environment qualification items.

Although qualification data is not available for radiation, continued station operation is justified for the following reason: This valve opens on low flow to provide a minimum flow line. Should the valve f ail in the open position, coolant injection would be reduced but would still exist. Additionally radiation doses were calculated using ,

conservative, non-mechanistic models. Mechanistic release models would result in radiation releases which occur several hours after the postulated accident. During this time, action will be taken to shut down recundant systems beyond those needed for coolant injection.

This would result in radiation exposures to only of two recundant equipment trLins. Also actual doses would be less than those calculated using such conservative assumptions. Finally, should the operating equipment suffer degradation due to radiation exposure, the shut down redundant system could bs. :tivated. During the time available after stabilization of cote cooling, additional coolant injection paths could be established, if necessary, to assure long term cooling.

This item has been placed in its most likely gateg,ory pending review of the qualificutien data. -

4.5.2.3 Equipment Item No. 11 Stop Valve Located in the HPCI Rooms Manufacturer Not Stated, Model 178250E02D4 (Licensee References 18 and 19)

Licensee References 18 and 19 are not quali ation test reportst therefore, qualification documentation is deficient for this item. The Licensee has indicated that the required operating pericd is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the environmental stress remains negligible for this item during the stated cperating perioc, FRC concludes that the qualification review can be deferred until after February 1, 1981, in secordance with NRC criteria presented in Section 2.2.3 of this rerset. It should be shown that the 120*F peak temperature is not a result of the DBE in orcer to conclude that the DBE environmental stress is negligible.

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TER-C5417-13 4.5.2.6 Equipment Item No. 12 Motor Cperated Valve Located in the HPCI Room Limitorque Model SMB-3 with Peerless CC Motor (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 minutes. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter TcLeuary 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the ObE in order to conclude that the DBE environmental stress is negligible.

4.5.2.7 Equipment Item No. 15 Motor Operated Valve Located in the Steam Tunnel Limitorque Model SMB-3-80 with peerless DC Motor (Licensee Reference 18)

Licensee Reference 18 is .aot a qualification document for this, item. The Licensee has indicated that the required cperating period is 10 minutes. If the environmental stress remains negligible for this item during the stated operating pericd plus I hour, FRC concludes that the qualifiention review can be d=ferrea until after February 1, 1981, in accordance with NRC criteria p' Tented in Section 2.2.3 of this report, It should be shown that the 120'F peak temperature is not a result of the CBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.8 Equipment Item No. 16 Motor Cperated valve Located in the HPCI Room Limitorque Models SMB-0, SMB-3, SMB-4, and SMB-000 (Licensee References 13 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has incicated that the required operating pericd is 10 minutes. If the envirenmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until after Feoruary 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that i

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TER-C5417-13 the 120*F peak temperature is not a result of the CBE in orcer to conclude that the DBE environmental stress is negligible.

4.5.2.9 Equipment Item No. 17 Solenoid Valves Located in the HPCI Rootu ASCO Model 830281F (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification cocuments for this item. The Licensee has indicated that the required operating period is 10 minutes. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.10 Equipment Item No. 19

• Flow Transmitter Located in the HPCI Room General Electric Mocel 4532K13001 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 cays. If the environmental stress remains negligible for this item during the l

l stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to concluce that the DEE environmental stress is negligible.

4.5.2.11 Equipment No. 20 i Pressure Transmitter Located in the HPCI Room General Electric Model 4532K11001 (Licensee References 11 and 19)

Licensee Reference 11 is a qualification report which will be reviewed 1 ster. This item has been placed in its most likely category pending teview.

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TER-C5417-13 4.5.2.12 Equipment Item No. 22 Pressure Transmitter Located in the HFCI Room General Electric Model 50-551032CAAY1 (Licensee References 11,18, and 19)

Licensee Reference 11 is a qualification report which will be reviewed later. This item has been placed in its most likely category pending review.

4.5.2.13 Equipment Item No. 24 Turbine Gland Seal Condensate Drain Pump Located in the HPCI Room General Electric Model 58225A3525 '

(Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required cperating period is 12 days. If the environmental stress remains negligible for this iten during the stated cperating period, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.14 Equipment Item No. 25 Gland Steam Exhaust Fan Located in the HPCI Room General Electric Model 5BC74AB2193 (Licensee References 18 and 19)

Licensee References 13 and 19 are not qualification cocuments for this item. The Licensee has indicated that the required operating period is 12 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in orcer to concluce that the DBE environmental stress is negligible.

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TER-C5417-13 4.5.2.15 Equipment Item No. 26 Motor Speed Changer Located in the HPCI Room General Electric Mocel 5BC26AC389 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. If the environmental stress remains negligible for this item during the statet coerating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presentec in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.16 Equipment Item No. 27 Motor Gear Unit Located in the HPCI Room General Electric Model SCD14019A-111620 (Licensee References la and 19)

L'icensee References 18 and 19 are not qualification documents for this item. The Licensee hae indicated that the required operating period is 12 ,

days. If the environmental stress remains negligible for this item during the stated operating period FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria pecsented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result af the DBE in order to conclude that the DBE l environmental stress is negligible.

4.5.2.17 Equipment Item No. 28 011 Pump Motor Located in the HPCI Room General Electric Mocels SCD218E252 and SCD326E758 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is li days. If the environmental stress remains negligible for this item during the stated operating perico, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accorcance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120'F 4-19

TER-C 5417-13 pean temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.18 Equipment Item No. 29 HPCI Motor Control Signal Converter Located in the HPCI Room General Electric Mocal 357513TC108 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification reviaw can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak teJperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.19 Equipment Item No. 30 Level Switch Located in the HPCI Room Mercoid Model 123-2 (Licensee References 18 and 19)

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Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. If the environmental stress remains negligible for this item during the stateo operating perioc, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presenteo in Section 2.2.3 of this report. It should be shown that the 120*F peak temperarare is not a result of the DEE in order to conclude that the DBE envircnmental stress is negligible.

4.5.? 20 Equipment Item No. 31 Level Switch Located in the HPCI Room Magnetrol Model 291-SP (Licensee References 18, 19, and 23)

Licensee Reference 23 is a test report. The data presented by the Licensee indicates that all qualification requirements except aging are satisfied. If the environmental stress remains negligible for this item 4-20

TER-C5417-13 during the stated operating period, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.21 Equipment Item No. 3 Flow Switch located in the EPCI Room Barton Model 289 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120'F peak temperature is not a result of the DBE in orcer to conclude that the DBE environmental stress is negligible.

4.5.2.22 Equipment Item No. 33 Pressure Switch Located in the HPCI Rocm Static-O-Ring Model 6NN-AA21-VRR (Licensee References 18 and 19)

Lice.nsee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until af ter February 1, 1981, in accordance with NRC criteria presentea in Section 2.2.3 of this report. It should be shown that the 120*F peak is not a result of the CBE in order to conclude that the DBE environmental stress is negligible.

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TER-C5417-13 4.5.2.23 Equipment Item No. 34 Pressure Switch Located in the HPCI Room Barksdale D2H-M150SS (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 dcys. If the environmental stress remains negligible for this item during the statec operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.24 Equipment Item No. 38 Motor Operated valve Located Inside the Drywell Limitorque Model SMB-0C0 (Licensee References 20 and 24)

Licensee References 20 and 24 are test reports en'Limitorque valve cperators. The Licensee makes the following statements and commitments:

The test procedure requirec saturated atmosphere, additional vendor information is being sought to resolve outstanding environmental qualification items. But humidity was not measured during the test.

Test used saturated steam for temperature. Although qualification data is not available, continued station operation is justified for the following reasons:

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

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! b. These components ccmplete their functicn in a very short period of time and would not experience siSinficant effects of increased enviror. mental conditions in this short time perioc.

c. These components uncergo periodic functional testing to verify l operability. This testing would identify age related degradation.

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

This item has been placed in its = cst likely category pending review of l the qualification data.

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TER-C5417-13 4.5.2.25 Equipment Item No. 39 Motor Operated Valve Located in the Steam Tunnel Limitorque Model SMB-00-7.5 with Peerless DC Motor (Licensee Reference 18)

Licensee Reference 10 is not a qualification document for this item. The Licensee has indicated that the required operating period is 35 seconds. If the environmental stress remains negligible for this item ouring the stated operating period plus one hour, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 cf this report. It should be shown that the 120'F temperature is not a result of the design basis event in order to conclude that the DBE environmental stress is negli",. ible.

4.5.2.26 Equipment Item No. 40 Differential Pressure Indicating Switch Located in the Secordary Containment Barton Model 278 (Licensee References 18 and 19)

Lice'nsee References 18 and 19 are not qualification test reports; therefore, qualification documentation .s deficient for this item. The Licensee notes that these sensors are used to detect a main steam line break in the steam tunnel anc complete their function within 1 minute. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.27 Equipment Item No. 41 Temperature Switen Located in the Steam Tunnel Fenwal Model 17002-40 (Licensee References 18 and 23)

Licensee Reference 18 and 23 are not qualification test reports; therefore, qualification documentation is deficient for this item. The Licensee notes that these sensors are used to detect a main steam line break in che steam tunnel and complete their function within 1 minute. If the 4-23

i TER-C5417-13 environmental stress remains nrigligible for this item curing the stated cper .ing pertoo plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferreo until af ter February 1,1981, in accoroance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.28 Equipment No. 42 Motor Operated Valve Located in the NE and SE Corner Rooms Limitorque Models SMB-0-15 and SMB-2-60

> (Licensee References 18,19, and 20)

Licensee Reference 20 is a test report on Limitorque valve operators.

This item is placed in its most likely category pending review of qualification data.

4.5.2.29 Equipment No. 43 Kotor Operated Valve Located in the Torus Area Limitorque Mocel SMB-000-5 (Licensee References 18 and 20)

Licensee Reference 20 is a test report on Limitorque valve operators.

This item is placed in its most likely category pending review of qualification cata.

4.5.2.30 Equipment No. 44 Motor Operatec Valve Located in the NE and SE Corner Rcoms Limitorque Model SMB-2-40 (Licensee References 7,18, and 19)

Licensee Reference 7 is a test report for a Limitorque valve actuator.

This item has been placed in its most likely category pending review of qualification data.

4.5.2.31 Equipment No. 45 Motor Cperated Valve Located in the SE Corner Room Limitorque Model SMB (Licensee References 18 and 19)

Licensee References 18 anc 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 25 seconos. If the environmental stress remains negligible for this item during 4-24

a s TER-C5 4' 7-13 the stated operated period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.32 Equipment Item No. 46 Motor Operated Valve Located in the Secondary Containment Limitorque Model SMS-0-15 (Licensee References 18, 19, and 20)

Licensee Reference 20 is a test report on Limitorque valve motor operators. This item is placed in its most likely category pending review of qualification data.

4.5.2.33 Equipment Item No. 47 Motor Operated Valve Located in the Secondary Containment Area Limitorque Model SMB (Licensee References 7, 18, and 20)

Licensee Reference 7 is a qualification report. This item has been placed in its most likely category pending review of the qualification data.

l 4.5.2.34 Equipment Item No. 48 l Motor Operated Valve Located in the Torus Area Limitorque Models SMB-5T-150 and SMB-2-60 (Licensee Reference 7) i l Licensee Reference 7 is a test report "Tr a Limitorque valve actuator for Class lE service outside primary Containment. The Licensee makes the follwing statements and commitments:

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

a. Existing qualification data is within a f actor of 2 of the c:_lculated

! radiation dose.

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

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

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TER-C5417-13

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

4.5.2.35 Equipment Item No. 49 Motor Operated Value Located in the Torus Area Limitorque Module SMB-3-100, SMB-4T-150, and SMB-0-10 (Licensee References 18 and 20)

Licensee Reference 20 in a qualification report. This item has been placed in its most likely category pending review of the qualification data.

4.5.2.36 Equipment Item No. 50 Motor Operated Valve Located in the_ Torus Area Limitorque Model SMB (Licensee References 18 and 19)

Licensee Ref erences 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 40 seconds. If the environmental stress remains negligible for this item ducirig the stated operat:ng period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification

~

review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.37 Equipment Item No. 51 Motor Cperated Valve Located Inside the Drywell Limitorque Models SMB-3 and SMB (Licensee Reference 18)

Licensee Referer.ce 18 is not a qualification test reports therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

a. These components or similar items have been partially tested for environmental cond'.tions.

b. These components remained functional curing the June 5, 1970 l

-depressurization incident at Dresden Unit 2. This incident resulted in harsh environmental conditions. l l

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• TER-C5417-13 4.5.2.38 Equipment Item No. 53 Pressure Transmitter Located in the NE and SE Corner Rooms General Electric Model GE/MAC 551 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; Pherefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

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

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

During the time available af ter stabilization of core cooling, additional coolant injection paths coulo be established, if necessary, to assure loirs term cooling.

4.5.2.39 Equipment Item No. 55 Level Switch Located in the RHR Pump Room j Magnetrol Model 249C-X-EP-SIMD4DC l (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for tais item. The Licensee has indicated that continuous operation is required. If the environmental stress remains negligible, FRC concludes that the i

qualification review can be deferred until after Feocuary 1, 1981, in

, accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperarture is not a rusult of the DBE in order to conclude that the environmental stress due to DBE is negligible.

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TER-C5417-13 4.5.2.40 Equipment Item No. 58 RHR Service Water Pump Motor Located in the RHR Pump Room General Electric Mocal SK821167A31 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that continuous operation is requireo. If the environmental stress remains negligible, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F temperature is not a result of the CBE in order to conclude that the environmental stress due to CBE in negligible.

4.5.2.41 Equipment Item No. 61 Motor Operated Valve Located in the NE and SE Corner acom Limitorque Module SMB-1 and SMB-0 (Licencee References 7,18, and 19)

Licensee Reference 7 is a qualification report. This item has been

p,laceo in its most likely category pending review of the qualification data.

4.5.2.42 Equipment Item No. 63 Rcom Cooler Located in the RER Pump Rocm Manufacturer and Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that continuous operation is required. If the environmental stress remains regligible, FRC concludes that the I qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It 3 l

I should be shown that the 120*F peak temperature is not a result of the CBE in order to conclude that the CBE environmental stress is negligible.

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TER-C5417-13 I

4.5.2.43 Equipment Item No. 64 Solenoid Valve Located in the Torus Area ASCO Model HT8316B14 and HT831614 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 15 seconds or less. If the environmental stress remains negligible for this item during the stated cperating period plus I hour, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.44 Equipment Item No. 65A Solenoid Valve Located in the Torus Area Versa Models VPS-2402 and VCS-4422 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicatea that the required operating period is 10 seconds. If the environmental stress remains negligible for this item during .

the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC* concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.45 Equipment Item No. 66 Solenoid Valve Located in the Secondary Containment Versa Model VPS-2302 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 seconds. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981,,in accordance with NRC l criteria presented in Section 2.2.3 of this report.

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TER-C5417-13 4.5.2.46 Equipment Ites No. 67 Solenoid valve Located in the Secondary Containment ASCO Models 8302026F, HT83161814, and HT831614 (Licensee References 18 and 19)

Licensee References la and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 seconds. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.47 Equipment Item No. 68 Solenoid valve Located in the Secondary Containment Area Versa Model %PS-2302 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 seconds. If the environmental strees remains negligible for this item during ,

thLs statea operating period plus I hour, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC

-criteria presented in Section 2.2.3 of this report.

4.5.2.48 Equipment Item No. 69 Motor Cperated Valve Located in the Secondary Containment Limitorque Model SMB-000 (Licensee References 18 and 19)

Licensee References 18 ano 19 are not qualification doc 2ments for this item. The Licensee has indicated that the required operating period is 25 seconds. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presentec in Section 2.2.3 of this report.

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TER-c5417-13 4.5.2.49 Equipment Item No. 73 Motor-Driven Pump Located in the RER Pump Rocm General Electric Model 5K365AK169 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 30 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It must be shown that the peak temperature of 120*F is not due to the design basis event in order to conclude that the DBE stress is negligible.

4.5.2.50 Equipment Item No. 75 Rocm Cooler Fan Located in the HPCI Room Buf f alo Forge Model G123-HV Type 15474 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operation period is 12 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

l 4.5.2.51 Equipment Item No. 80

. Solenoid Ball Valve Located in the Secondary Containment Area

( General Pneumatic Model 608KW106 l (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 minutes. If the environmental stress remains negligible for this item during

! the stated operating period plus i hour, FRC concludes that the qualification review can te deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

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TER-C5417-13 4.5.2.52 Equipment Item No. 81 Squib Shear Valve Located in the Secondary Containment Area Pyrodyne, Model Not Statea (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification cocuments for this item. The Licensee has indicated that the required operating period is 10 minutes. If the environmental stress remains negligible for this item during the stated operating period plus I hour, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. The Licensee is investigating the existence of qualification data with the manufacturer.

4.5.2.53 Equipment Item No. 82 Motor Operated Valve Located in the Drywell Limitorque SMB-1-40 with Peerless AC Motor (Licensee References 20 and 22)

. Licensee References 20 and 22 are test reports of Limitorque valve operators. This item has been placed in its most likely category pending review of the qualifi:ation data.

4.5.2.54 Equipment Item No. 84 Solenoid Valve Located in the Torus Area ASCO Model HT831614 (Licensee References 18 and 19)

Licensee References 18 and 19 see not qualification documents for enis item. The Licensee has indicated that the required operating period is 20 seconds. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

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. o TER-C5417-13 4.5.2.55 Equipment Item No. 85 Solenoid Valve Located in the Secondary Containment ASCO, Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has inoicated that the required operating period is 10 seconds. If the environmental stress remains negligible for this item during the stated operating period plua 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.56 Equipment Iter.No. 86

' . Motor Operated Valves Located in the Torus Area Limitorque yodel SMB-000-5 with Peerless AC Motor (Licensee Prferences 20 and 22)

Licensee Referr.nces 20 and 22 are qualification-type test reports for Limitorque valve operators. This item has been placed in its most likely category pending review of qualification data. . .

4.5.2.57 Equipment Item No. e7 Solenoid _ Valves Located in the Seconcary Containment Area ASCO Models HVA90-405-2A, EVA96-082A, WPBLX831636, and HVA-96-081A (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is less than 1 minute. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the i

qualification review can be deferred until after February 1, 1981, in j accordance with NRC criteria presented in Section 2.2.3 of this report.

I l

4.5.2.58 Equipment Item No. 88 Level Switches Located in the Secondary Containment Area l

Magnetrol Model 402 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is less than 1 minute. If the environmental stress remains negligible for this item l

4-33 l

t

.-- -. ,- ,-,y -

TER-C5417-13 during the stated operating perioc plus I hour, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.59 Equipment Item No. 89 Position Switches Located in the Secondary Containment Area Namco Model Mark II D1200G (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 20 seconds. If the environmental stress remains negligible for this item during this stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be ceferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.60 Equipment Item No. 91 Solenoid Valve Located in the RWCU Room

• No Manufacturer or Model Number Stated (Licensee References 18 and 19) l Licensee References 18 and 19 are not qualification documents for this l

item. The Licensee has indicated that the required operating period is 10 seconds. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.61 Equipment Item No. 92 Pressure Switches Located in the Secondary Containment Area l Barksdale Model 32T-M12SS and 32T-Al2SS (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this

item. The Licensee has indicated that the required operating period is 2 minutes or less. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the l qualification review can be deferred until after February 1, 1981 in accorcance with MRC criteria apresented in Section 2.2.3 of this report.

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TER-C5417-13 4.5.2.62 Equipment Item No. 93 Level Indicating Switch Located in the Secondary Containment Area Yarway Models 4418C and 4418CE (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this iter. The Licensee has indicated that the required operating period is less than 1 minute. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until after February 1, 1981 in accoraance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.63 Equipment Item No. 94 Motor Cperated Valves Located Inside the Drywell Limitorque Models SMB-2, SMB-000, anc SMB (Licensee reference not cited)

The Licensee has indicated that additicnal vendor information is being sought to resolve outstanding environmental qualification items. Although qualification data is n.ot available, continued station operation is justified for the following reasons:

a. These components or similar items have been pactially testea for environmental conditions.

b. These compenents remained functional during the June 5, 1970 depressurization incident at Dresden Unit 2. This incident resulted in harsh environmental conditions.

(

4.5.2.64 Equipment Item No. 95 Differential Pressure Indicating Switches Located in the Secondary Containment Sarton Model 288 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification dccuments for this item. The Licensee has indicated that the required operating pericd is 2 minutes. If the environmental stress remains negligible for this item during the stated cperating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until afts. February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

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TER-C5417-13 4.5.2.65 Equipment Item No. 96 Differential Pressure Indicating Switches Located in the NE and SE Corner Rooms Barton Model 288 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 minutes. It the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.66 Equipment Item No. 97 Radiation Element GM Tube Located in the Turbine Building General Electric DWG 194X927GI (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operac.ng period is 10 minutes. Since the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presentec in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in orcer to conclude that the DBE environmental stress is negligible.

4.5.2.67 Equipment Item No. 98 Solenoid Valves Located in the Secondary Containment Versa /Barksdale Models VPS-2402 and VGS-4422/DlH-A15055 (Licensee References 18 anc 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 10 minutes. Since the environmental stress remains negligible for this item during the statec operating period, FRC concludes that the qualification review can be ceferred uniel after February 1, 1981 in uccordance with NRC criteria presentec in Section 2.2.3 of this report. It should be shown that 4-36

TER-C5417-13 the 120*F peak temperature is not a result of the DBE in orcer to conclude that the DBE environmental stress is negligible.

4.5.2.68 Equipment Ite- No. 102 Switchgear Located in the Secondary Containment Area General Electric Models AMH 4.76-250 and AKD-5 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that continuous operation is required. If the environmental stress remains negligible for this itsm during the stated operating period, FRC concludes that the qualification review can be deferred uniti af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.69 Equipment Item No. 103A .

480 V Motor Control Center Located in the Secondary Containment Area General Electric Model 7700 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that continuous operation is required. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred uniti after February 1, 1981 in accorcance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.70 Equipment Item No. 113 Motor Cperated Valve Located Inside the Drywell Limitorque Model SMB (Licensee References 20 and 22)

Licensee References 20 and 22 are qualification test reports. This item nas been placed in its most likely category pending review by FRC using previous experience.

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TER-C5417-13 4.5.2.71 Equipment Item No. 114 Motor Operated Valves Located in the Steam Tunnel Limitorque, Medel Not Stated, with Peerless DC Motor (Licensee Reference 18)

Licensee Reference 18 is not a qualification document for this item. The Licensee has indicated that the required operating period is 10 minutes. If the environmental stress remains negligible for this item curing the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.72 Equipment Item No. 115 Solenoic Valves Located in the SW Corner Room ASCO Model 830281F

. (Licensee Referencas 18 anc 19) , ,

~

Licenseee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required cperating period is 10 minutes. If the environmental stress remains negligible for tnia item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the ll4'T peak temperature is not a result of tho DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.73 Equipment Item No. 116 Differential Pressure Indicating Switches Located in the SW Corner Room Sarton Model 288 (Licensee References 18, 19, and 25)

Licensee Reference 25 is a test report. Licensee Reference 18 is not a qualification document for this item. The Licensee has indicated that the l-required operating period is 10 minutes. If the environmental stress remains negligihle for enis item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC i

4-38 i

e

• TER-C5417-13 concludes that the qualification review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the ll4*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.74 Equipment Item No. 118 Motor Cperated Valves Located in the SW Corner Room Limitorque Modele SMB and SMB-0 (Licensee References 18 aol 19)

Licensee References 18 and 19 att not qualification documents for this item. The Licensee has indicated that the required operating period is 10 minutes. If the environmental stress remains negligible for this item during the stated operating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the ll4*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental ~ stress is negligible.

4.5.2.75 Equipment Item No. 119 Pressure Switchen Located in the SW Corner doom Barksdale Model B2T-A12SS (Licensee References 18, 19, and 27)

Licensee Reference 27 is a test report. Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the requireo operating period is less than 1 minute. If the environmental stress remains negligible for this item during the stated cperating period plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, FRC concludes that the qualification review can be deferred until af ter Fecruary 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the ll4'F peak temperature is not a result of the CBE in order to conclude that the CBE environmental stress is negligible.

l i 4-39

• O TER-C3417-13 4.5.2.76 Equipment Item No. 120 Solenoid Valve Loccted in the SW Corner Room ASCO Model 830281F (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualifications documents for this item. The Licensee has indicated that the required operating pericd is 10 minutes. If the environmental stress remains negligible for this item during the stated operating period plus I hour, FRC concludes that the qualification review can be deferrea until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It s: - Id be shown that the ll4*F peak temperature is not a result of the design basis event in orcer to conclude that the DBE environmental stress is negligible.

h 1

4-40

I TER-C5 417-13 4.6 NRC Category V EQUIPMENT WHICH IS UNQUALIFIED The DOR Guidelines require that complete and auditable records reflecting i a comprehensive qualification methodology and pe; gram be referenced and made available for review of all Class 12 equipment.

The qualification of the following equipment items has been judged to be deficient or inadequate, based upon review of tne documentation pecrided by the Licensee. The extent to whicn the equipment items fail to satisfy the criteria of the DOR Guidelines can be categorized as follows: (i) documenta-tion reflecting qualification as specified in DOR Guidelines has not been made availaole for reviews (ii) documentation reflecting qualification inadequate, or (iii) the documentation incicates that the equipment item has not successfully passed required tests. The following equipment items are therefore considered unqualified.

4.6.1 Equipment Item No. 1 Temperature Elements Located in the RWCU Room Manufacturer and Model Number Not Stated (Licensee References 13 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. The Licensee notes that, where these temperature switches are used for leak detection in the RWCU coom, conditions are normally non-harsh. Immediately l

following a leak, the temperature will increase. As soon as the leak occurs, the switches will function, initiating system isolation within 1 minute.

4.6.2 Equipment Item No. 2 Motor-Driven Pumps Lacated in the NW Corner Room General Electric Mocals SK6338XC23A and 5K6336XC193 (Licensee References 18 and 19)

Licensee References 18 and 19 are not test reports; therefore, qualification documentation is deficient for this item. Tne Licensee makes the following statements and commitments:

4e

. . Franklin Researen Center 4-41

= c wmane rven.ww.

...e, . - . - n . .. - - ~ - -,- , - - . - - - - - - n --. . , , , ~ - - . , . - , . - . . .

TER-C5417-13 A contract will be issued for service to qualify this equipment by analysis and/or testing, failing which the appropriate equipment or parts thereof will be replaced with qualified components. Al; hough qualification data is not available, continued station operation is justified for the following reasons:

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

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

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

4.6.3 Equipment Item No. 10 Pressure Switch Locted in the NW and SW Corner Rooms Mercontrol Model CA-7043-804 (Licensee References 18 and 19) .

Licensee References 18 and 19 are qualification test reporte, therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

The equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justifiec for the following reason:

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

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

During the time availacle af ter stabilization of core cooling, additional coolant injection paths could be established, if necessa.ry, to assure long-term ccoling.

4-42

a e l

l TER-C5417-13 )

l 4.6.4 Equipment Item No. 13 Motor Operated Valve Located in the Dry. ell Limitorque Model SMB-1 (Licensee Reference 7)

Licensee Reference 7 is a qualification test report for Limitorque valve actuator. FRC notes that the test radiation dose is less than the postulated DBE radiation dose. The Licensee makes the following statements and commitments :

The equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is justifiec for the following reason:

This valve is located inside drywell and is normally open. Following a postulated accident, it would remain open to allow steam flow to the HCPI turbine. Valve operation would only be required to isolate the HPCI steam line. Three additional valves are located on this steam line outside drywell to isolate the steam line. Since the harah environment inside drywell is associated with an accident which would not affect environments or HPCI steam line pipe integrity outside drywell, the three outside drywell valves would be capable of isolating the steam line.

4.6.5 Equipment Item No. 14 Motor Operated Valve Located in the Torus Area Limitorque, Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for th? . tem. This item has not been qualified for elevated temperature and pressure as required for the indicated service conditions.

4.6.6 Equipment Item No. 21 Temperature Switch Located in the HPCI Rocm United Electric Controls Model 883 (Licensee References 18 and 19)

Licensee References 18 and 19 are nor qualification documents for this item. The Licensee has indicated that the required cperating period is 12 days. If the environmenral stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after Fectuary 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4-43

- 4 TER-C5417-13 The Licensee notes that these temperature switenes detect a HPCI steam line break. In the event of a leak, these switches will function and isolate the HPCI steam line. Since the temperature associated with this etent is within the range of routine calibration, additional qualification data is not required.

4.6.7 Equipment Item No. 35 Solenoid Valve Located Inside the Drywell Allied Controis-Gould Models 320X-39 and 320X-30 (Licensee Reference 18)

Licensee Reference 18 is not a qualification test report; therefore, qualification documentation is ceficient for this item. The Licensee makes the following statements and commitments:

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

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

b. These components complete their function in a very short pe-iod of time and would not experience significant effects of increased environmental conditions in this short time period,

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

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

4.6.8 Equipment Item Nos. 36 and 37 Relief Valve and Solenoid valve Located Inside the Drywell Dresser Industries Electromatic Type C5450-5 and 1525VX (Licensee References 13 and 15)

Licensee Reference 15 is a test report which does not adequately address operating time and aging. The Licensee makes the following statement l The number of actuations which this component was subjected to during the test is considersoly larger than the numcer of actuations during 12 days following the accident. Therefore, this component is considered qualified for the required operating time.

1. _a_

...; Franklin Research Center 4-44 s t,vww e r% semewaue

e

• 4 TER-C5417-13 FRC does not concur with the Licensee's argument. The 12-day period in a harsh environment can cause equipment deyradations whether or not the equipment it is operated.

4.6.9 Equipment Item No. 52 Motor Operated Value Located in the Steam Tunnel Limiterque Model SMB (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation it deficient for this item. The Licensee makes the following statements and commitments:

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

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

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

4.6.10 Equipment Item No. 56 Differential Pressure Indicating Switch Located in the NE and SE Corner Rooms Barton Model 289 (Licensee References 18 ard 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitme-ts:

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

4-45 1

• o i I

l l

TER-C5417-13 l

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

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

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

4.6.11 Equipment Item No. 62 Dif ferential Pressure Switch Located in the NE Corner Room ITT Barton, Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. the Licensee makes the following reatements and commitments:

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

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

to only one of cwo redundant equipment trains. Also actual doses would be less than those calculated using such conservative assumptions.

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

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

I i

4-46

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

e .

TER-C5417-13 4.6.12 Equipment Item No. 65B Solenoid Valve Located in the Torus Area Versa Models VPS-2502, VGS-4522, and VGS-4422 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

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

b. An alternate flow path is available to relieve torus vacuma in the event these components shoula fail.

4.6.13 Equipment Item No. 71 -

Pressure Switch Locatec in the SE Corner Room Static-G-Ring Model 12NN-KK215-VX (Licensee Reference 18 and 19)

Licensee Reference 18 and 19 are not qualification test reports; therefore, qualificajon documentation is deficient for this item. The Licensee mades the following statements and commitments:

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

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

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

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

During the time available af ter stabilization of core cooling, additional coolant in]ection phths could be established, if necessary, to assure long term cooling.

i 4-47

. e TER-C5417-13 4.6.14 Equipment Item No. 72 Temperature Element Located Inside the Torus Area Pall Trinity Micro 14-T-2H (Licensee Reference 19)

Licensee Reference 19 is not a qualification test reports therefore, qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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

a. Raciation doses were calculated using conservative non-mechanistic models. Mechanistic release models would result in L2diation releases which occur several hours after the postulated accident.

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

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

4.6.15 Equipment Item No. 74 Fan Motors Located in the NE and NW Corner Rooms General Electric Models SK213AK2476 and SKl84AL2191 (Licensee References 18 and 19)

Licensee References 18 and 19 are nct qualification test reports; therefore, qualification documentation is deficient for this item. The Licensee makes the following statements ano commitments:

This equipment will be replaced with qualified equipment. Although

! qualification data is not availaole, continued station operation is justifiec for the following reasons:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases that occur several hours after the postulatec accident. During this time, action will ce taken to shut down redundant systems beyond those needec for coolant injection. This would result in radiation exposures to only one of two redundant equipment trains. Also, actual doses would te less 4-48

e .

TER-C5417-13 4

than those calculated using such conservative assumptions. Finally, should the operating equipment suffer degradation due to radiation exposure, the shut down recundant system could be activated. During the time available af ter stabilization of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

4.6.16 Equipment Item No. 83 Motor Operated Valve Located in the RWCU Room Limitorque Model SMB (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification cocumentation is deficient for this item. The Licensee makes the following statements and commitments:

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

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

b. These components complete their function in E very short period of time and would not experience significant effects of increased environmental conditions in this short time period.

c. These components uncergo periodic functional testing to verify operacility this testing would identify age related degradation.

4.6.17 Equipment Item No. 103B 480 V Motor Control Center Located in the Secondary Containment Area General Electric Model 7700 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. The Licensees make the following statements and commitments:

This equipment is subjected to harsh radiation only, and will be relocated and/or shielded to reduce the radiation exposure to a non-harsh level. Although qualification data is not available, continued cperation is Justified for the following reasons:

4-49

TIR-C5417-13

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

Aceval doses would therefore be less than those calculated using such couvervative assumptions.

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

4.6.18 Equipment Item No. 112 125 V de Distribution Panel Located in the Secondary Containment Catler-Hammer, Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 cre not qualification test reports; therefore, qualsfication documentation is deficient for this item. The Licensee makes the following statements and ccmmitments:

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

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

Actual doses would therefore ce less than those calculated using such conservative assuptions.

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

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TER-C5417-13 4.7 NRC Category VI EQUIPMENT FCR WHICu QUALIFICATION IS DEFERRED This section includes equipment items which have been addressed by the Licensee in the equiiment 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.

I 4.7.1 dquipment Item No. 18 Differential Pressure Indicating Switch Located in tne HPCI Room 9arton Model 288  ;

(Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. Since the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. .

4.7.2 Equipment Item No. 23 Pressure Switch Located in the Secondary Containment Area Barksdale Model B2T-A12SS (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this i

l Item. The Licensee has indicated that the required operating period is 12 days. Since the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance witn NRC criteria presented in Section 2.2.2 of this report.

l l 4.7.3 Equipment Item No. 70 Pressure $sitch Located in the Secondary Containment Area l

Static-0-Ring Mocal 12N-AAS-PP (Licensee References 18 and 19)

{

l Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 days. Since the environmental stress remains negligible for this item curing 4-51 L.

TER-C5417-13 the stated operating period, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2..' or this report.

4.7.4 Equipment Item No. 76 Fan Motors Located in Diesel Room 2 Manufacturer anc Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this 1

item. The Licensee has indicated the required operating period is 30 days.

If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the D8E environmental stress is negligible.

4.7.5 Equipment Item,No. 77 Motor-Driven o"mc Located in Diesel Room 2 General Ele ;odel SKl82BL315 (Licensee ...ces 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated the required operating period is 30 days.

If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until af ter February 1,1981, in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak cemperature is not a result of the DBE in ceder to conclude that the DBE environmental stress is negligible.

4.7.6 Equipment Item No. 78 Level Switches Located in Diesel Room 2 Magnetrol Model A-103F-EP/VP (Licensee References 18 and 19)

Licensee References 19 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 30 1

4-52

o .

TER-C5417-13 days. If the 9avironmental stress remains negligible far this item during the stated operating pctiod, FRC concludes that the qbalification review can be deferred until af ter February 1,1981, in accorcance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120'F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4 67 7 Equipment Item No. 79 Solenoid Valve Located in Diesel Room 2 ASCO Model 8211CS9 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 30 days. If the environme tal stress remains negligible for this item curing the statec operating perir , FRC concluces that the qualification review can be deferreo until after February 1, 1981, in accordance with NRC criteria

. presented in Section 2.2.3 of this report. It should be shown that the 120'F peak temperatere is not a result of the DBE in order t~ conclude that the DBE environmental stress is negligible.

4. 7. 8 Equipment Item 120. 99 Diesel Auxiliary Control Located in Diesel Room 2 Ideal Electric & Manufacturs9g Model SO No. 267777 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicaced that the required operating period is 30 days. If the environmental stress remains negligible for this item during the stated operating period plus. FRC concludes that the qualification review can be deferred until after February 1, 1981 in accordance witn NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120'?

peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4-53

TER-C5417-13 4.7.9 Equipment Item No. 100 -

Excitation Cabinets Located in Diesel Room 2 Electromotive Div. of GM, Model 9474 (Licensee References 18 and 15)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 30 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualificatien review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented in Section ?.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.7.10 Equipment Item No. 101 Diesel Generators Located in Diesel Room 2 Electromotive Div. of GM, Model 8366072 A-20-Cl (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualificati,on documents for this item. The Licensee has indicated that the required cperatir? period is 30 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be ceferreo until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is .7pgligible.

4.7.11 Equipment Item No. 104 Engine Control Panel Located in Diesel Room 2 Electremotive Div. of GM, Model S20E4GW (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operation period is 30 days, If the environmental stress remains negligible for this item during the stated cperating period, FRC concludes that the qualification review can be deferred until after February 3, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that 120'F peak

.... eranklin Research Center 4-54 m a w N nie aw.

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l TER-C5417-13 temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.7.12 Equipment Ites No. 105 4 kV Non-segregrated Bus Located in the Turbine Building Manufacturer and Model Nct Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operation period is 30 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that 120*F peak temperature is not a result of the DBE in order to conclude that the JBE environmental sttess is negligible.

4.7.13 Equipment Item No. 106 DIG Secondary Control Panel Located in Diesel Room 2 Ideal Electric S.O. 9267777 (Licensee References 18 and 19)

Licensee References 13 and 19 are not qualification documents for this item. Tae Licensee has indicated that the required operation period is 30 days. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes that the qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F l

peak temperature is nct a result of tP's DBE in order to conclude that the DBE f er.vironnental stress is negligible.

l l

4.7.14 Equipment Item No. 107 DIG Neutral Grounding Panel Located in Diesel Room 2 i General Electric Model 208419-68P l (Licensee References 18 and 19)

Licensee References 13 and 19 are not qualification documents for this item. The Licensee has indicated that the required operation period is 30 l days. If the envircnmental stress remains negligible for this item during the i

t 4%

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.... Franklin ac- ae 3, Research

% o, .Ce.r:ter 1

TER-C5417-13 stated operating period, FRC concludes that the qualification review can be deferreo until af ter February 1,1931 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be noted that the 120*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.7.15 Equipment Item No. 108 Battery Chargers Located in the Battery Charger Room Gould Models GRF240T100X, GRF-1200T100X, and GRTF24S25F30X (Licensee References 15 and 19)

Licensee References 18 and 19 are not qualification cocuments for this item. The Licensee has indicated that continuous operation is required. If the environmental stress remains negligible fc this item, FRC concludes that

the qualification review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to concluoe that the DBE environmental stress is negligible.

4.7.16 Equipment Item No. 109 250 V DC Motor Control Center Located in the Battery Charger Room Cutler Hammer Model 6002H347B (Licensee Refereness 18,19, and 28)

Licensee Reference 28 is a test report for Class lE DC motor control.

! Ljcensee References 18 and 19 are not qualification documents for this item.

The Licensee has indicated thr. continuous operation is required. If the environmental stress remains negligible for this item, FRC concludes that tre qualification review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120*F peak temperature is not a result of the DBE in order to concluce that the CBE environmental stress is negligible.

893 '

.... FranMn Research Center s w wee won v.aue

TER-C5417-13 4.7.17 Equipment Item No. 110 Batteries Located in the Battery Charger Room Gould Models FPS-25, FPR-13, and DPR-9 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that centinuous operation is required. If the envi onmental stress remains negligible for this item, FRC concludes that the qur _ification review can be deferred until af ter February 1,1981 in accore ince with NRC criteria presented in Section 2.2.3 of this report. It should be shown that the 120'F peak temperature is not a result of the CBE in order to conclude that the DBE environmental stress is negligible.

4.7.18 Equipment Item No. 111 CC Distribution Panel Located in the Battery Charger Rocm Cutler Hammer, Model Not Stated (Licensee References' 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that continuous operation is required. If the environmental stress remains negligible for this item during the stated operating period, FRC concludes th.at the qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this repcst. It should be shown that the 120*F peak temper >ture is not a result of the CBE in orcer to conclude that the DBE environmental stress is negligible.

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TER-C5417-13

5. CONCLUSICNS Review of the qualification documentation and other information submitted by Commonwealth Edison Company for these equipment stems anc their applications in the Quad Cities 2 plant has resulted in the following categories:

NRC Compliance With The COR Quantity Of Category Guideline Requirements Equipment Items I.a Equipment Fully Satisfics All Applicable Requirements for 1 Life of the Plant I.b Equipment Does Not Meet All Applicable Requirements for Life of the Plant; However, O Deviations are Judged Acceptable II.a Equipment Fully Satisfies All Applicable Requirements for Less Than Plant Life 1 II . b .

• Equipment Fully Satisfies All Applicable Requirements Provided Thrt Specific Modifications are Made 0 II.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 Satisf actory for Less Than Plant Life Besed on Total EEQ Program Review 0 III Equipment is Exempt from Qualification 0 IV.a Equipment has Qualification Testing Scheduled 7 IV.b Equipment has High Likelihoco of Operability; Bowever, Proper Qualification Documentation is Not Available 76 V Equipment is Unqualified 19 VI Qualification is Oeferred 18

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.... Frank:n Researen Center s kan ao N vman osaase

TER-C3417-13 In general, the mayor 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 environment 51 qualification evaluation conducted by TRC in accordance with the methodology presented in Section 3. The evaluation results are largely based on tha available qualification documentation provided by the Licensee. The results of the review do not necessarily Lmply that the equipment is unreliable or unsafe or that it represents a significant plant safety issue s they do imply, however, that qualification documentation is inadequate and that additional information is required.

the Equipment Environmental Qualification Summary Form that is presented on the following pages shows the overall results of the FRC review. The entries on this form delineate the overall status of each specific equipment item with respect to compliance with the Guidelines criteria defined in Section 2 and the resultant qualification categories defined in Section 3.

The following designations are used:

X = A deficiency witE respect to ecmpliance with a Guidelines requirement. Deficiencies result in equipcent items being 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.

O = NRC Qualification Category.

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

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l FRC TASK AEACTCR PLANT NAME PAGE nidin Research Center I b cifs G 2 A ciwmon of The Franwin :stsaane PROJECT UTIUTY l

EQ12NP,NT ENVIRONMENTAL *OU N N W M (D85 "

CUAUFICATICN  !

CCCKET NRC TAC DATE/ ENGINEER IES 79018 50-265- 4N7T '/f/f* SAS

SUMMARY

REVIEW EQUIPMENTITEM NUMBER i l 1 l 3 l '+-l i l 4 l 7 l 5' l i l sc l" l sc l C l r+l,ilie. e7ldl.il2c GU10ELINE REQUIREMENTS, (CESIGNATIONS: X - DEFIC:ENCY, L - UMITING CCNCITION)

EVt0ENCE OF CU AUFICATION lXlXI l l l Xl lXlXlXl XIXlXlXI IXl RELATICNSHIP TO TEST SPECIMEN l lX lXl X lX l l l l l l l l l l l l AGING CEGF ADATION EVALUATED I l l l l ll l l l l l l l l l l  ! I CUAUFIED UFE ESTAEUSHED l l l l l l l l l l l I I I l l l l PROGRAM Tol0ENTIFY AGING l l

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l l l l l l l l l l l l l l l l l {

CU AL. FCR STEAM EXPCSUPE l  ! l I l l l l l l l l. l l l l l I PEAK TEMPERATURE ACECUATE l l l I l l l l I l l lXl l l l l I  !

PEAK PRESSURE ADECUATE I l l l l l l I l l l l l  !

l l l l l f TESTOURATION ACECUATE l l l l l ll l l l l l l l l l l l l REQUIRED PRCFILE ENVELCPED l l l l l l l l l l X,l l. l l l l l CUAL. FCR SU BMERGENCE l l l l l l l- l l l l l l l l  ! I CU AL. :CR CHEMICAL SP AAY l .l l l l l l l l l l l l l l l l QU AL. FOR RACIATICN l l l l lNlXl lX l l l lXl l l l l l l EE'A RACIATION CONSIDEPED l l l l l I l l l l l l l l l l I l l TESTSECUENCE l l l l l l l l Il l l l l l l l l TEST OURATION (1 HOUR - FUNCTICN) '

l l l l l l l l l l l l l l l l l QUANTITY CF ECUIPMENT ECUIPMENTINSPECTED AT SITE l l9liiil1141312l11%l4l1Illilill191412l1Iil l l l l l l l l l l l l l l l l l l l l GUAUFICATICN CATEGCRY, '

O - CATEGORY CESIGNATION l

!-A. CUAL. FCR PLANT UFE l l l l l l l l l l l l l I l l ll-3. QUAL. SY JU CGEMENT 11 A. CU AL. FOR < PLANT UFE l

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l l l l l l l l l l l l l l l  ! l l l ll 3. CU AL. PENCING MCOlF!CATICN l l l l l l l l l l l l l l l l l l l l l Il-C. QU AL. < PLANT LIFE /FRC REVIEW l l l l  ! l l l l l l l l l l l l l l l l til. EXEMPT FRCM QUAL.  ! l l l )

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t i j lVI. CUAL. IS CEFERREc l l l

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SUMMARY

REVIEW EdUIPMENTITEM NUMBER

'2r l 22l23l 2h5{n l27l2Yl2'i l N h h1l3 5 l'I-lh*lIc lI 7l17l: 7 l%

GulOELINE RECulREMENTS. (CESIGNATIONS: X - DEFICIENCY, L - LIMITING CONCITION)

EVICENCE OF CU AUFiCATICN lXl l lX XlXlXlXlXlXlXlXlXlXlXl l l IXIX RELATIONSHIP TO TEST SPECIMEN l l l l l l l l l l l l l l l l lXl l AGING CEGRADATION EVALUATED l l l l l l ll l l l l l lX lNl l l CUAUFIED LIFE ESTABLISHED l l l l l l l l l l l l l lXlXl l  !

P ACGRAM TO IDENTIFY AGING l l l l l l l l l l l l l l l l5lXl l l CUAL FOR STEAM EXPOSUPE l l I l l I I l l l I l  !  ! I I I I I I PEAK TEMPERATURE ACECUATE l l l l l l l l l l l l l l  !  !  !  !

PEAK PRESSURE ACECUATE l l l l l l l l l l l I  ! l l l  !  ! l TESTCURATICN ACECUATE I)( l l l l l l l l l l l l lXIX! l l l REQUIRED PROFILE ENVELOPED l l l l l l l l l l l l- l! '

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lCUAL FOR SUBMEFGENCE l l l l 1 l~l l l l l l l l l- l l l l lCUAL FOR CHEMICAL SPRAY l l l l l l l f !l l l l l l l l l l l CU AL FOR RACIAT!ON l l l l l l !l l l l l l l l l l l l BETA RACIAT!ON CONS!CEPED I l l l i I  ! l l l l l  ! l l l I l TEST SECUENCE l l  ! l l l l I l l l l l l l I TEST CURAT!CN O HOUR - FUNCT:ON)  ! l l l l l  ! l l l l l l l l l l  !

CUANTiTY CF ECUIPMENT lIIl/l4llll!Illl2*lIlll1 /l/l1lfl Il9lllI!ld!

ECulPMENTlNSPECTED AT SITE l I I l l l l l l l l l l l l l l l l  ! l CUAUF1 CATION CATEGCRY. ' O -CATEGCRY CESIGNATICN l l ll A. QUAL FCR PLANTLIFE l l l l l ll l l l l l l l l ) l l

!!-8. CUAL 3Y JUCGEMENT l l l l l l 1 l l l l l l l l  !  ! l  ! l l l 3

l 1 l lIl A.CUAL FCR < ?LANT UFE l l l l l l l l l l l l l l l l l l l  ! l l l l l i l l l j 11 E. CUAL. PENCING MCCIF! CAT!ON l l l l l l l l I l l l l Il-C. CUAL < PLANT UFE!FRC REVIEW l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l f Ill. EXEMPT FROM CUAL. l  ! l l l l l l l l l l l l l I l l l l l l l l l l 1%A. CUAL TEST SCHECULE IV-B. CU AL. NOT ESTA BUSHED i l0 l l0l0l0l0lO!Ol0jo10l0ldl l l l0lo!Ol

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EQUIPMENT ENVIRONMENTAL 02GG7-01 gg ,,,yggjg gpfg,y GUAUFICATION DCCXET NRC TAC DATE/ ENGINEER IEB-79-018 go 2fg 42471 Uf/fo MS

SUMMARY

REVIEW EQUIPMENTITEM NUMBER w !-Zl-il+-l-5 l*/.,l+7lv(l-ilse li. l5 : l5i livli> lic li7 liir l5 ) l3 GUIDEUNE RECUlRE. MEN'. 7, (CESIGNATICNS: X - DEFIC:ENCY, L - UMITING CCNDITION)

EVICENCE OF CUALIFICATICN lXl l l lNl l l l l X l Xl X l X lX l% l X l Xl Xl% l X-RELATIONSHIP TO TEST SPEC! MEN l lXlXlXl l X l X!K lX l l l l l l l l t l l AGING CEGRACATION EVALUATED l l l l l l l l l l l l l l l l l CUAUFIED LIFE ESTA8USHED l l I l k l l l l l l l l l l l l l l l P ACGRAM TO ICENTIFY AGING l l l l l l l l l l l l l l l l l l l l l CUAL. FOR STEAM EXPCSURE I l l I l I I l l l l l  ! l l I l l I PEAK TEMPERATURE ACECUATE l I l l I l I l l l I I I I I I l I  !

PEAK PRESSURE ACECUATE I l l l l l l l I l l l l l l I l  ! l TEST CURATION ACECUATE l_l I I l l l l l l I I l  ! l l l l l RECulRED PROFILE ENVELCPED l l l l l l l' l l l l l l l l l l l  ! l CU AL. FOR SUSMERGENCE l l l i l l l I l l l l l l l  ! l l l l CU'A L. FCR CH EMICAL SPPAY l l l l l l l l l l l l l l l l l l l l CU AL. FOR RACIATICN l l l l l l $h l l l  !  ! I !  !  !  ! I SETA RACIATION CCNSICERED l l l I l l l l l l I l l l l l l l I TEST SEQUENCE l l l l l l l l l l l l l l l l l l l TEST CURAT10N (1 HOUR + FUNCTICN) l l l l l l l l l l l l l l l l l l l l I

CU ANTITY OF EQUIPMENT lI d l 9 l 1 l 4 l 2.k 1 l 2.l 9 l I l / l M / l 1 l I l 4 l 2 l 3 l 4 l 2 l 4 l ECulPMENTINSPECTED ATSITE I l l } l l l l l l l  ! l l l l l I l l CUALIFICATICN CATEGORY. ' O - CATEGOFW CESIGNATION l l-A. CUAL. FCR PLANT UFE l l l l l l l l l l l l l l l l l l l-8. CU AL. 3Y JU CGEMENT l l l l l l i I l l l l l l l l l l 5 j ll-A. CU AL. FCR < PLANT UFE l l l l l l l l l l l l l l l l l l l l l

!!-3. CU AL. PEN CING MOCIFICATICN l l l l l l l l l l l l l l l l l l l l l Il-C. CU AL. < PLANT UFE/ FRC P EVIEW l l l l l l l l l l l l l l l l l I l Ill. EXEMPT FROM CU A L. l l l l l l l l l l l l l l l l l l  ! l lV- A. CU A L. TEST SCH EDU LE l l l l l l l l l l l l l loi  ! lol I o lo l IV B.CUAL. NOT ESTABUSHED l 0 l0 l0 l 0 l 0l O 1010 l 0 !010l l0l l 0l l l0l l l lV. ECUIP. NOT CU AUFIED l l l l l l l  ! l l 10l l l l0l l  !  ! l VI. CU AL. lS CEFERPED l l l l l l l l l l l l l l l l l REPLACEMENT SCHECULE l l l l l l l l l l l l l lAl l A l& l 1 i,

A FRC TASK AE CTCR PLANT NAME PAGE bl) Frankjin Research Center b 3 WA ' N d '7'" #

A cu on et The Franwin insonne p g UTIUTY ECUIPMENT ENVIRCNMENTAL 02GG7-9 g ,., gg yg g up CUAUFICATION CCCKET NRC TAC OATE/ ENGINEER 1E9-79-018 So- 24 5 4579 8/7/fd SA 5

SUMMARY

REVIEW ECUIPMENTITEM NUMBER 6 I l i!.lJ 3l6v k54l65dct lc 1 lcile 'e l 70 l 7i l72.l 7 3 l 7%l 75l 7? l 17 l 79 l h GUIDELINE RECUlREMENTS, (CESIGNATICNS: X - CEFICIENCY, L - L1MITING CONDIT!CN) l EVICENCE CF CU AllFICATION l l5lNlN NlNlXlNlNlNI lXlXl[lMIYl l l 8 i RELATIONSHIP TC TEST SPECIMEN Xl l l l l l l l l l l l l l l l l l AGING DEGRADATION EVALUATED  ! l l l l ll l l l l l l l l l l l l CUALIFIED LIFE ESTABLISHED l I I l I l l l l l l I I I l l I l!

P ACGR AM TO ICENT!FY AGING l l l  ! l l l l l l  ! l l l l l l CUAL. FCR STEAM EXPCSURE I l l I l l l l l l l l l l l l l l l PEAK TEMPERATURE ACECUATE l l l I l l l l l l l l l l I l l I PEAK PAESSURE ACECUATE l l l l I l l l l l l l l l  ! l l l l TEST CURATICN ACECUATE l l l l l l l l l l l l l l l l l l l l RECUIRED PROFILE ENVELCPED l l l l l l l l l l l l l l l*l l l CU AL. FCR huBMERG ENCE l l l l l l l l l l l l l l l I l l l 4

CU AL. FCR CHEMICAL SPPAY l l l l l l l l l l l l l l l l l l l l

l CU AL. FCR RA0lAT!CN l l l l l l l l l l l l l l l l l l ll

! BETA AACIATICN CCNSIDERED l l l l I l l l l l l l l l l l l l !l TEST SECUENCE l l l l l l l l l l l l l l l l l l l l TEST OURATION U HOUR + FUNCTlCN) l l l l l l l l l l l l l l l l l l ll CU ANTITY OF ECU!PMENT #'ll2lYlkfl'/!2l2.llllIllll4l2-l4l1l4lIll!llllll l ECulPMENTINSPECTED AT SITE l l l l l l l l l l l l l l l l l l l l l l CUAL!FICATION CATEGORY, ' C -CATEGCRY OESIGNATICN 1-A. CU AL. FCR PLANT LIFE l l l I Il l l l l l l l l l lI l-8. CU AL. SY . UCGEMENT l l l l l  ! i l  ! l l l l l l l l l l l l I "II A CUAL FOR < PLANT LIFE

. . l  ! l l l  !

l l l l l l l l l l i l l 11-3. CUAL. PENCING MCCIFICATICN l l l l l l l l l l l l l l l l l l l l Il-C. CUAL. < PLANT LIFE /FRC REViE'N l l l l l l l l l l  ! l l l l l l l l I I til. EXEMPT :PCM CU AL. l l l l l l l I l l I l l l f l l l I l l llV-A. OUAL. TEST SCHECULE l l l l l l l l l l l l l l  !  ! l l I i  !

llV E. CUAL. NCT ESTA3LISHED lCl l0l0l0j l0lOlol0l i l loi lcl l l l l

lV. ECUIP. NOT OUALIF:ED Cl l l l0l l I l i l0lOl [Cl l  !  ! l l IVI. CU AL. is CE:EPPEO l l l l l l  ! l l0j l l l l lCl0l0l01 FEPLACEMENT SCHEDULE l l l l l l l l l l l l l l l l l. l l 1 i l

4 FRC TASK AEA CR PLANT NAME PAGE b Franklin Research Center 3WA' 4'#D </17 6 & S

^ N" d N F'"d" ^""

PROJECT UTILITY ECUIPMENT ENVIRONMENTAL MG G1M1 CUALIFICATION foM Ao#WutTW G A/5od#

DCCKET NRC TAC DATE/ ENGINEER

~

IES-1'9-018 50-265 4 2+ ?? 8/7/f8 54[

SUMMARY

REVIEW ECUIPMENTITEM NUMBER W l91 l RlV*>lWl'5il?clM l Nlr)Iwl3 # l t 2l 7 7l ~ ?l 7il F.l /7l r rl 77 G ulCELINE REQUIREMENTS, (CESIGNAT!CNS: X - DE. 1C:ENCY, L - LIMITING CCNCITION)

EVICENCE CF CUALIFICATION l X l bl l Xl blX l l NIM l Xl lNl[lXl 5 l/l lXl/I RELATICNSHIP TO TESTSPEC: MEN l l l% l l l l)(l l l l l l lXl l l l l AGING CEGRADATION EVALUATED l l l l l l l l l l !l l l l l l GU ALIFIED LIFE ESTA BLISHED l I I l l 1l l l l l l I I I  !  !  !

P ACGRAM TO 10ENT1FY AGING I l i l l l l l l l l l l I l l l l l QUAL. FOR STEAM EXPCSURE l l l l l l,l l l l l l l l l l l l  !  !

PEAir TEMPERATURE ACECUATE l I I I l I l l l l l l l I I I I l l l l PEAK PRESSURE ACECUATE l l I l l i l l l l l l l l l l  ! i  !  !

TEST CURATION ACECUATE l l l l l l l l l l l l l l l l l l  !

RECulRED PROFILE ENVELOPED l l l l l l l l l l .l l l l l I I l lCU AL. COR SUBMERGENCE l l l l l  !  ! l l l l l l l l l l l  ! l CU AL. FOR CHEMICAL SPRAY l l l l l l l l l l l l l l l l l l 1 l l CUAL. FOR RAO!ATICN l l l l l l l l l l l l l l l l l l l EETA RACIATION CCNSIDERED l l l l I I I l l l I l I l l l l l l TEST SEQUENCE l l l l l l l l l l l l l l l l l l l l TEST OURATION (1 HOUR - FUNCTION) l l l l l l l l l l l l l l l l l l l l

!CUANTITY OF EGUIPMENT l$ l d l l l l l k!1l2lI l4 l 3l l l / l/d/1l $ l 4 l fl 2-l k! [l l ECU!PMENTINSPECTED AT SITE l l l l l l l l l l l l l l l l l l l l CU AUF! CATION CATEGORY, ' O - CATEGORY DESIGNATICN l l  :-A. OVAL. FOR PLANT LIFE l i l l l l l l l l l l l l l l l l l a. CU AL. EY JUCGEMENT l l l l l l  ! l l l l l l l l l l i j l l li-A. QU AL. FCR < PLANT UFE l l  ! l l l l l l l l0l l l l l l  !  ! l l it-a. cVAL. PENCING MoctFICATICN  ! l l l l l l l l l l l l l l l l l 3 l l Il-C. CU AL. < PLANT UFE/FRC REVIEW l l l l l l l l l l l l l l l l l l l l Ill. EXEMPT F2CM CUAL l l l l l l l l l l l l l  ! i l l l l l

!v 4. CuAL. EST SCHEcutE l I I l l I  ! l l l l l l 1 i I l 1  ; I I liv-a. CuAL. NOT ESTAauSHED :o l o lo l lolololololol loloiololololo!o!  !

V. ECulP. NCT CUAUFTED l l lcl l l l l l l l l l l l l l l l l VI. CU AL. lS CE.:EPRED l l l l l l l l l l l l l l l l l lO PEP ACEMENTSCHEDULE l l l l l l l l l l l l l l l l l l l l l l l

l l

FRC TASK NCR PLANT NAME PAGEl {

nidin Research Center 0 I

~

• U MS u '

A Omsson of The FrenWin Inseante UT1UTY I PROJECT EQUIPMENT ENVIRONMENTAL -

MM*MNEM CUAUFICATICN OCCKET N,R g C CATE/ ENGINEER IES 79 018 8/f/f#

50 24.7 42477 MI

SUMMARY

REVIEW ECUIPMENTITEM NUMBER c

s vl is. l sch ',$e4c-hcy ea h; 7 l n. < hs ;l, .o l o i h i :lu 'li.-l . ,5lu ; ln -l .<

t IGUIDEUNE REQUIREMENTS. (CESIGNATIONS: X - CEFIC;ENCY, L - LIMITING CONDITICN)

EVIDENCE CF QUALIFICATION '

lN Ilh ll l l l l Inl l5!Xl l I5 RELATIONSHIP TO TEST SPECIMEN l l l l ll l l l l l l l l l l l AGING DEGRADATICN EVALUATED  !  ! !l l! l l l l l l l  !!

CU ALIFIED LIFE ESTA BUSHED l l l I l l l l l l l l l l l !

PRCGRAM TOICENTIFY AGING '

l l l l l l l l_l l l l l l l l l l CUAL FOR STEAM EXPCSURE l l l l l l l l l l I I I I l l l l PEAK TEMPERATURE ADECUATE l l l l l l l l l l l I  ! l l l l  ! l ll PEAK PRESSURE ACECUATE l l l l 4 I l l l l l l l I l  ! l l  !

TESTCURATION ADECUATE l l l l l l l l l l l l l l I l l l ll RECulRED PRCFILE ENVELOPED l  ! I l l l l l l l l l l l l l l l l I.

CUAL. FOR SU BMEPGENCE l l l l l l l l .l l_l l l l l l l l*l l f lCU'AL FOR CHEMICAL SP AAY l l  ! l  ! i f  !  ! l l 1 l I  !

l CUAL FOR RACfATICN l l l l l l l l l l l l l l l l l l l BETA AADIAT1CN CONSIDERED l l l l l l l l I l l I II l l l ll TEST SEQUENCE l l l l l l l l l l l l l l l l l l TEST OURATICN (1 HOUR - FUNCT!CN) '

l l l l l l l l l l l l l l l l l l CUANTITY CF ECUIPMENT l I l l l414 l6 ll ll II / l 7l3 lV l4 ll l1 ll l1 ll lisi2,l ECUIPMENTINSPECTED AT SITE l l l l l l I l l l l l l l l l l CUAUFICATICN CATEGCRY, ' C - CATEGCRY OESIGNATICN l I l-A. CUAL FCR PLANT UFE l l l l l l l l l l l l l l l l lol l l

t-B. CUAL 3't UOGEMENT I l l l l l l l l l l l l l l l l l l l l II A. CU AL. FOR < ?LANT UFE l l l l l l l l l l l l l l l l l l l l l lII-3. CU AL. PENCING MCCIF!CADCN l l l l l l l l l l l.l l l l 'l l l l l l lll C. CU AL. < PLANT LIFE /FRC REVIEW l  ! l l l l l l l l l l l l l l l l l l lit. EXEMPT FROM CU AL l l l l l  ! I l l l l l l l l l l l l l IV A. CUAL TEST SCHECULE l l l l l l l l  ! l l l l l l l l l l  ! l i IV 3.CUAL NCT ESTABUSHED '

l l0l0l l l i

! I I l [OlOlcl0l lcl j lV. ECulP. NCT CUALIFIED l l lOl l l l l l l l l0 ' l l l l I VI. CUAL. !S ::EFERP ED l 0 lO l l0lOl0 Ol0lOlOlOl l  ! l l l l l REPLACEMENT SCHECULE l l l l l l l l l l l l l l l l l l

! I i

A FRC TASK A CR PLANT NAME PAGE bb Franklin Research Center b# 8W" 4"# cms 1 7 l 4 ca.on or Th. Franan :naw PROJEC7 UTIUTY ECulPMENT ENVIRONMENTAL MQ17 01, oggu,,,,gg py Eppsse CUAUFICAMN l COCKET NRC TAC OATE/ ENGINEER IES49-018 50-145 <+2W9 1/ rho di

SUMMARY

REVIEW EQUIPMENTITEM NUMSER iri lt Ml l l l l l l l l l l l l l l l l l l GulCELINE RECUIREMENTS, (CESIGNATICNS: X- CEFICIENCY, L-LIMITING CCNCITICN)

EVICENCE CF CUALIFICATION l lKl l l l ll l l l l l l l I l l I RELATIONSHIP TO TEST SPECIMEN l l l l l l l l l l l l l l l l l l l l AG NG CEGRACATION EVALUATED Xl l l l l ll l l l l l l l l l l l l CUAUFIED UFE ESTABLISHED I l l l I l l l l l l l l I l l I l PPCGRAM TOICENTIFY AGING l I l l l l l l l l l l l l l l l l l CUAL. FOR STEAM EXPCSURE i l l l l 1 l l I l l l l I I I I I I PEAK TEMPERATURE ACECUATE l l l l l l l l l l l l l  !  !  !  !  ! l PEAK PRESSURF. ACECUATE LXl l l l l l l l l l l l l l l l l l l TEST CURATICN ADECUATE l l l l l l l l l l l l l l l I l I RECUtRED PROFILE ENVELOPED l l l l l I l ! l l l l l l l l l l l CUAL. FOR SUBMERGENCE l l l l l l l l l l l l l l l l l I  ! l l GU'AL :CR CHEMICAL SPPAY l l l l I i l  ! I l l l l l l l l l I

,CUAL. FOR RADIATICN l l l l l l l l l l l  ! !l l l l l l BETA RACIATION CONSIDERED l I l I I l l I l l  !  !  ! l l l I TEST SEQU ENCE l l l l l l l '

l l l l l l l I l l l l TES T CURATICN (1 HOUR - FUNCTION) l l l l l l l l l l l l l l l l l l ll CUANTITY CF ECUIPMENT Ikl1! l l l l l l l l l l l l l l l _ !l ECUIPMENT!NSPECTED AT SITE I l l } l l l l I l l I } l l l l l CUALIFICATICN CATEGORY. ' O - CATEGORY CESIGNATICN l i-A. QUAL FCR PLANT UFE l l l l ll l l l l l l l l l l ll l-8. CU AL SY JUCGEMENT l l l l l l l l l l l l l l l l l l l l l Il-A. CUAL FCR < PLANT UFE l l l l l l l l l l l l l l l l l l l l l Il-E. QUAL PENCING MCCIFICATION l l l l l l l l l l l l l l l l l l l l Il-C. CUAL. < PLANT UFE/FRC REVIEW l l l l l l l l l l l l l l l l l l l l lil. EXEMPT FRCM CU AL l l l l l l l l l l l l l l l l l l  ! l l IV- A. CU AL. TEST SCH ECU LE l l l l l l l l  !  ! l l l l l l l l l l IV 3.CUAL MCT ESTAEUSHED lC lO - l l l l t l l l l l l l l l l l ll V. ECUIP. NCT CU ALiFIED l l l l l } l l l  ! l l l  ! l  ! l l !

!VI. CU AL. lS CE.: ERRED l l l l l l l l l l l l l l l ll REPLACEMENT SCHECULE l l l l l l l l l l l l  ! l l l l l

e I e

P m

m 91 m

3 m

2 O

m M

. e TER-C5417-13

6. REFERENCES QUALIFICATICH REFERENCES

1. FSAR Section 10.10

2. Becntel Radiation Study

3. FSAR Table 8.2.3

4. FSAR Figures 5.2.15 and 5.2.16

5. FSA2 Sections 6.2.3.2

6. Special Report No.12, Rev. 1, Feb. 1975

7. Limitorque 600461-B0003 Quad Test Report

8. Limitorque 600426-80009

9. F-C2232-01

10. F-C3441

11. DV-145C3006 rualification Design Verification File GE Test Report

12. FSAR Section 6.2.7.2 (D)

13. FSAR Table 5.2.1 ,

14. FSAF Section 6.2.4.2.2 1 PEP 442963 Test - Dresser Relief Valve Actuator

16. FSAR Section 6.5

17. FSAR Section 6.2.3.2

18. Report Section 4.4

19. Report Section 4.3.6

20. WCAP-7410-L, Test on Limitorque Motor Operators

21. GE Test Report No. DV-145C3008 Qualification Design Verification File and ITT Barton TP199-4

22. F-C2485-01 Tests of Limitorque Valve Operator

23. Cr?ibration Procedure QLS 26-1

24. Test Report ACS216781TR, Rev. A, Qualification Test of Solenoid Valves

25. GE Test Report No. DV-145C3009, Qualification Design Verification File and ITT Barton Report No TP-1999-4

26. GE Test Report No. DV-145C3004, Qualification Design verification File

27. GE Test Report No. DV-115C3010, Qualification Design Verification File and AETL Report No. 596-0398

28. F-C3781-2 -

W -h- 6-1 en

.... Franklin

• s--mwn.rww Researe.n

. C.u.ter

e .

I l

TER-C5417-13 OTHER REFERENCES

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

Subject:

Electrical Equipment Environmental Qualification, dated February 19, 1980.

30. Letter from Norman C. Mosely, NRC, to B. H. Grier, J. P. O'Reilly, J. G. Keppler, K. V. Sezfrit, and R. H. Engelken, NRC.

Subject:

IE Supplament No. 2 to Bulletin 79-OlB, Environmental Qualification of Class lE Equipment, dated September 29, 1980.

31. Letter from Norman C. Moseley, NRC, to B. H. Grier, J. P. O'Reilly, J. G. Keppler, K. V. Sezf rit, and R. H. Engelken, NRC.

Subject:

IE Supplement No. 3 to Bulletin 79-OLB, Environmental Qualification of Class LE Equipment, dated October 24, 1980.

32. U.S. NRC Memorandum and Order (CLI-80-21) pursuant to the Petition for Emergency and Remedial Relief files with the NRC on Ncvember 4,1977.

33. NUREG-n588, Interim Staf f Position on Environmental Qualification of Jafety-Related Electrical Equipment, cated Decemcer 1979.

34. Commonwealth Edison Co. response to IE Bulletin 79-018 for Quad Cities Nuclear Power Station Units 1 and 2, dated November 1,1980.

l

35. Memorandum for V. V. Thomas,' NRC, through D. W. Hayes, NRC f ecm J.

Hughes, NRC.

Subject:

Screening Review of Licensee Responses to IE Bulletin 79-01B and Summary of Instructions of Installed System at Quad Cities Unit 1 and 2 Facility--Docket No. 50-254; dated April 14, 1980.

A-2-- 6-4.

.... F.anklin Research Center m.an a n, em m,

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

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

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f f

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

TER-C5417-13 APPENDIX A - ENVIRONMENTAL SERVICE CCNDITIONS The Licensee has provided detailed information concerning environmental zones and expected environmental service conditions in all locations within the plant. Figures A-1 and A-2 show the inside-containment profile envelopes provided by the Licensee.

Quad Cities 2 has a demineralized water spray system rather than a chemical spray system inside-containment. This is considered in the Licensee's analysis.

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

The Licensee States that, where environmental conditions are maintained by HVAC equipment, the HVAC system is provided with redundant components and/or a backup power supply for reliable operation. Safety-related HVAC systems tre provideo tot tha following areast

a. control room, cable spreading room, battery room, computer room, and electrical equipment room

b. standby diesel generator room

c. HPCI toom

d. low-pressure coolant injections corner rooms.

Ws A-1

... 5nklin Research C.e.nter

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c,o I -lTI Illi - ~-~l I~lT1 T11 1 T I'1 IIll I TI IIlli ~~l TITI!!i ~~T T' l'ITil  !lli I

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1__t_ L Lillt _ 1_._1_1_11111 1__1_J _1 t ill L 1 1 11111..-. l _i _ L L t.ll! __ _ l _.. s . t.1.1 t il _1__ t _t .1 1 l i t C 0 I 4 5 lo 10 10 10 10 10 10 gg6 IIME AFl[Il ACCIDf f41 ISECONDSI Figure A-1. Containment Pressure 14esponse Following Design FIGUPJi S'.li;i'LtED .

nasis noss-or-cooiant-acciaent BY lilE LICENCEE

TER-C5417-13 nW

.:w

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C - / d CE F

3 /

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r -

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e

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l 2 m c

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j Table A-1 2E s5 2$'

f't%

s FIAX IMilM I?!W i ltOleMI?t3 TAI, COilD I TIOflS INSIDl? TilG DRYWi?!.l.

FOI.I.OWI f3G Till? POSTill.ATl?D !.OCA/IIEl,Il 1[.

-?

Ile I a t ive Containment Gamma Sulamergence Temperature Pressure ilumid i ty Spray Itadiation F.levation

' 7

'2 81 F 63 psia 100% Demineralized I day-4.3x10 #"'" ~"

8 water 30 day-l.0x10 8 #8d" 1 year-1.1x10 rads i

t 4

4 T4

=

A I

C i b FIGURf. P."- .ng BY TME L;G .i .

jq Table A-2 d

im MAXIMllM EllViltOt3MEllTAI, COtIDITIOtI!i N , OllTSI DM Till! DRYWE!.I. FGl.I,0WillG Tile POSTill.ATED llHI.8 ACC IDCllTS

%;i s

r n

i Maximum Maximum Relative 4 Pressure Temperature ilumid ity Area pipe lireak (psia) (*F) (%)

Torus compartment II M' I steam 27.0 242 100 (region of postulated itCIC Steam Iine break)

Core spray /stCIC room ItCIC steam

• riot evaluated - Equipment in this room not p r'"uired for itCIC steam line break fiteam tunnel Main steam .1. 0 242 100 Feedwater ItCIC steam .

ItWCII lieat exchanger and itWCU tiot evaluated - Only two containment isolation holdisig pump r oom valves required to function. Quali f ica t ioni will meet conservatively assumed inside drywelI conditions.

Iliqh-pressure heater Main steam tiot evaluated - ik> equipment wlilch is reqtilred bay Feedwater to function is located in this area.

Turbine building Main sicam riot evaluated - No equipment which is required ?

el 615'-6" to function is located in this area. Y north of Column G, C between Columns 9 .ind 11 and 15 and 16 FIGURE SUf'I'UED BY THE LICEl13EE

Table A-2 (continued) l Li i5' Maximum Ma x imism IteIative

!!3 Pressure Temperature Ilum id i ty

?j 'Asca Pipe Dreak (psia) (*F) (1) la I n:r

[g Iteactor feed pump Feedwater 130t evaluated - 130 equipment which is required ii t oona to function is located in this room.

Turbine building Feedwater 130t evaluated - 130 equitmient winich is required el 595'-0" to function is located in this area.

area nouth of tinit 1 pump room and north of linit 2 pump room

> Diesel generator room Feedwa te r flot evaluated - Qualification for the environ-a ment due to a postulated feedwater 1ine break is not required since three diesels are available to provide emergency ac power.

4 i

4 i,

. I C.

4 FIGui'd."' '

DY Tifi UL> - "I

Table A-3

,' ; ;' ItADI ATIOti I:t3VIItOriMI:i1 TAI. COflDITIOrlS OllTSIDI:

i

"{:: DitYWI?I.I. FOI.I.OWIt3G Tile POSTUI.ATED IOCA d MAX IMilH ltADI ATIOti SOllitCCS sk' 52 h5 Integrated Dose I,evels (rads)

I$

[.

Area Source

• 1 Day 30 Days 1 Year 7

~k Torun SP 1.5x10 3.2x10 3.9x10 6

ites idua l lien t removal corner rooms SP 2.4x10 9.4x10 1.7x10 6

IIPCI room MS 6.6x10 1.6x10 1.7x10 6

Core spray /ItCIC rooma MS 6.6x10 1.6x10 1.7x10

{ Stcam tunnel MS 3.lx10 8.5x10 1.6x10 6

6 6 Iteactor l>uilding el 595'-0" Itw 2.5x10 7.8x10 1.4x10 5 6 iteact or liullding el 623'-0" CA 6.8x10 1.6x10 1.6x10 5 0 6 iteactor building el 647'-6" CA 6.8x10 1.6x10 1.6x10 6 6 Iteactor buildinq el 666'-6" CA 6.8x10 1.6x10 1.6x10

• SP = Suprension Imol liquid I,tw = lteact or wa ter FIS = lteactor steam a CA = Containment. airborne y a

f:

Y t:

FIGuiiL .. >

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. s TER-C5417-13 APPENDIX B - EQUIPMENT ITEM TABLE This appendix contains the list of safety-related electrical items for the Quad Cities Nuclear Generating Station Ur.it 2 provided by the Licensee in its Novemoer 1, 1980 response to IE Bulletin 79-01B. This listing shows the equipment items by manufacturer and model number, plant location, and time required to function as identified by the Licensee.

i I

4 B-1

.... Franklin 4 w w n.Research.Cen.ter re c

r TER-C5417-13 Quad Cities Unit 2 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 1 Temperature Element RWCU 1-6 18,19 No Manufacturer Room No Model No.

2 Motor-Deiven Pump NW and SW 7-9 18,19 General Electric Corner Rooms 5K6338XC23A Motor-Operated Valve NW and SW 10-12 18,19,20 3

Limitorque (Peerless AC) Corner Rooms SMB-0-25 4 Motor-Operated Valve Torus 13-14 13,19,20 timitorque (Peerless AC) Area SMB-0-15 5 Motor-operated valve Secondary 15-18 7 Limitorque (Reliance AC) Containment 277-278 SMB-2-40 Motor-Operated valve Torus 19-21, 7 6

Limitorque (Reliance AC) Area 277-278 SMB-000 NW and SW 22-24 11,19 7 Pressure Transmitter General Electric Corner Rooms 4532K11001 NW and SW 25-27 18,19 l 3 Pressure Transmitter General Ele:tric Corner Rooms 4532K43001 NW and SW 28-30 18,19,21 9 Flow Switch l Barton Corner Rooms 289 l

i NW and SW 31-34 18,19 10 Pressure Switch Mercontrol Corner Rooms DA-7043-804 I

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.... Franklin Research Center aomeorm n w mu, l

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TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 11 Stop Valve HPCI Room 35 18,19 No Manufacturer Cat No. 178250H02D4 12 Motor-Operated Valve HPCI Room 36 18,19 Limitorque (Peerless DC)

SMB-3 13 Motor-operated Valve Inside 37-38 7 Limitorque (Reliance AC) Drywell SMB 14 Motor-Operated valve Torus 39-40 18,19 Limitorque (Peerless DC) Area No Model No, 15 Motor-operated valve Steam 42-43 18 Limitorque (Peerless DC) Tunnel SMB-3-80 16 Motor Operated Valve HPCI Room 41, 44-47, 18,19 L:mitorque 50-53 SMB-0 SMB-000 SMS-2 SMB-3 SMB-4 17 Solenoid Valves HPCI Room 48-49, 18,19 ASCO 54-55 830281F 18 Differental Pressure Secondary 56-57 18,19 Indicating Switch Containment Barton 288 19 Flow Transmitter HPCI Room 58 18,19 General Electric 4532K13001 20 Pressure Transmitter HPCI Room 59 11,19 General Electric 4532K11001

1. -a-

.... Franklin Research Center B-3 4 hoa eme rma a rinu.

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TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE RE'ERENCES REFERENCES 21 Temperature Switen HPCI Room 60-69 18,19 United Electric Controls 88B 22 Pressure Transmitter HPCI Room 70 11,18,19 General Electric 50-551032CAAY1 23 Pressure Switch Secondary 71-73 18,19 Barksdale Containment B2T-Al2SS HPCI Room 74 18,19 24 Turbine Gland Seal Condensate Drain Pump General Electric 58225 A3525 HPCI Room 75 18,19 25 Glanf. Steam Exhauster Fan General Electric

• 5BC74AB2193 HPCI Room 76 18,19 26 Motor Speed Changer General Electric .

SBC26AC389 HPCI Room 77 18,19 27 Motor Gear Unit General Electric SCD14019A-lll620 HPCI Room 78-79 18,19 28 Oil Pump General Electric SCD218E252 SCD326E758 EPCI Room 80 18,19

29 HPCI Motor Control Signal Converter l

General Electric 357513TC108 HPCI Room 81 18,19 30 Level Switch Mercoid Type 123-2 W-h- 3-4

.... F inkhn Research Center e e at N r - ww.

. b TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 31 Lovel Switch Torus Area 82-83 18,19 Magnetrol 291 32 Flow Switch HPCI Room 84 18,19 Barton 289 33 Pressure Switch HPCI Room 85 18,19 Static-O-Ring 6NN-AA21-VRR 34 Pressure Switch HPCI Room 86-87 18,19 Barksdale D2H-M150SS 35 Solenoid valve Inside 88-93 18 Allied Controls-Gould Drywell 320X-39 320X-20 36 Safety Relief Valve and Inside 94-95 18 Solenoid Valve Drywell Dresser Industries C5450-5 37 Relief Valve and Inside 96-99 15,18 Solenoid Valve Drywell Dresser Industries Electromagnetic Type 1515VX 38 Motor-Operated Valve Inside 100-101 20,22 Limitorque (Peerless AC) Drywell SMB-000 l

39 Motor-Operated Valve Steam 102 18 l Limitorque (Peerless DC) Tunnel SMB-00-7.5 40 Differential Pressure Secondary 103-112 18,19 l Indicating Switch Containment

[

Barton 278 l

l r

...- Frankhn Research Center B-5

. A c.- or n em mou.

4 .

TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES ,REYERENCES 41 Temperature Switch Steam Tunnel 113-122 18,23 Fenwal 17002-40 42 Motor-Operated Vulve NE and SE 123-125, 18,19,20 Limitorque (Peerless AC) Corner Rooms 126-128 SMB-0-15 SMB-2-60 43 Motor-Operated Valve Torus 131-132 18,20 Limitorque (Peerless AC) Area SMB-0-000-5 44 Motor-Operated Valve NE and SE 129-130, 7,18,19 Limitorque Corner Rooms 133-135 SMB-2-40 45 Motor-Operated Valve SE Cornet 136, 202 18,19 Limitorque (Peerless) Room SMB 46 , Motor-Operated Valve Secon'ary d 137-138 18,19,20 Limitorque (Peerless AC) Containment-SMB-0-15 47 Motor-Operated valve Secondary 139-141 7,18,19 Limitorque (Reliance AC) Containment SMB 48 Motor-Operated Valve Torus 142-144. 7 Limitorque (Reliance AC) Area 147-149 SMB-5T-150 SMB-2-60 Motor-operated Valve Torus 145-146, 18,20 49 Limitor pa (Peerless AC) Area 150-153 SMB-3-100 SMB-4T-150 SMB-0-10 50 Motor-Operated Valve Torus, 154 18,19 Limitorque (Peerless DC) Area SMB d-%- B-6

.... Franklin Research

• wwm a# T,. ar w ., C. enter

. 6 TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFFRENCES 51 Motor-operated valve Insida 155-156, 18 Limitorque (Reliance AC) Drywell 159-160 SMB-3 SMB i

52 Motor-operated valve Steam 157-158 18,19 Limitorque (Peerless DC) Tunnel SMB 53 Pressure Transmitter NE and SE 161-163 18,19 General Electric Corner Rooms GE/MAC 551

/

54 Flow Transmitter NE and SE 164-168 18,19 General Electric Corner Rooms GE/MAC 553 Level Switch RER Pump Room 169-171 18,19 55 Magnetrol 24 9C-X-EPL-SIMD4 DC 4

56 Differential Pressure NE and SE 172-194 18,19 Indicating Switch Corner Rooms Barton 289 57 Pressure Switch NE and SE 175-180 18,19 Mercoid Corner Rooms, GN-L-3 RHP Service Water RHR Pump Room 181-183 18,19 58 Pump Motor General Electric SK821167A31 59 Pressure Transmitter NE and SE 184-187 18,19

, Ganeral Electric Corner Rocms GE/MAC 551 50-55132GAAW1 60 Motor-Driven Pump NE and SE 188-191 18,19 l General Electric Corner Rooras SK6336xC193(A,B,D)

I.

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( #N .... Franklin Research Center B-7 A W of N FN monaste

TER-C5417-13 EQUTPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION P7.GE REFERENCES REFERENCES 61 Motor-Operated Valve NE and SE 192-195 7, 18,19 Limitorque (Reliance AC) Corner Rooms SMB-1 SMB-0 62 Differental Pressure NE Corner 196-198 18,19 Switch Room ITT Barton N9 Model No.

63 Room Ccoler PJIR Pump Room 199-201 18,19 No Manufacturer No Model No.

64 Solenoid Valve Torus Area 203-204, 18,19 ASCO 206, 224 HT83161B14 HT831614 65A,B Solenoid Valve Torus Area 205, 207-208, 18,19 Ve.rsin 211, 216-218 . .

VPS-2402 VPS-2502 VGS-4422 VGS-4522 66 Solenoid valves Secondary 209-210 18,19 Versa Containment VGS-4532 VPS-2402 VPS-2401 VPS-4422 67 Solenoid Valve Secondary 212-213, 18,19 ASCO Containment 214, 219-223 HT831614 HT8316B14 8302026F Secoradary 215 18,19 68 Solenoid valve Versa Containment VPS-2302 Motor-Operated Valve Secondary 225 18,19 69 Limitorque Containment SMB-000

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.... Franedin Research Center B-8 a o.me er w nm w.

TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 70 Pressure Switch Secondary 226-232, 18,19 Static-O-Ring Containment 240-243 12N-AAS-PP 71 Pressure Switen SE Corner 233-235 18,19 Static-0-Ring Room 12NN-KK215-VX 72 Thermocouples Torus 236-239 19 Pall Trinity Micro vea 14-T-2H 73 Motor-Driven Pump RHR 244 18,19 General Electric Pump Room 5K365AK169 74 Fan Motor NE and SE 245-247, 18,19 General Electric NW and SW 249-251 5K213AK2476 Corner Rooms SK184AL2151 75 Room Cooler Fan HPCI Room 248 18,19 Buffalo Forge G-123HV Type 15474 76 Fan Motor Diesel Room 2 252 18,19 No Manufacturer No Model No.

77 Motor-Driven Pump Diesel Room 2 253 18,19 General Electric 5Kl82BL315 78 Level Switch Diesel Room 2 255 18,19 Magnetrol A-103F-EP/VP 79 Solenoid Valve Diesel Room 2 254 18,19 ASCO 8211C89 80 Solenoid Ball valve Secondary 256-259 18,19 General Pneumatic Containment

, 608KW106 W-h- ' B-9

.... Franklin Research Center

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TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 81 Squib Shear Valve Secondary 260-263 18,19 Pyrodyne Containment No Model No.

82 *otor-operated Valve Inside 264-265 20,22 Limitorque (Peerless AC) Drywell SMB-1-40 83 Motor-Operated Valve RWCU Room 266-267 18,19 Limitorque SMB 84 Solenoid Valve Torus Room 268-271 18,19 ASCO HT831614 85 Solenoid valve Secondary 272-273 18,19 ASCO Containment No Model No.

86 Motor-Operated Valve Torus 274-276 20,02 Limitorque

• Area SMB-000-5 87 Solenoid Valve Secondary 279-282, 18,19 ASCO Containment 286-289 HVA90-405-2A WPBLX831636 HVA96-082A l HVA96-081A l

l 88 Level Switch Secondary 283-295 18,19 Magnetrol Containment 402 89 Position Switches Secondary 290-292 18,19 NAMCO Containment Mark II D1200G l

l

• 90 Solenoid Valve Inside 293-294 24 l ASCO Drywell Type NP-1 t

I i

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.... Franklin Research Center B-10 s m e at n, vrean n ma.

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TER-C5417-13 j EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 91 Solenoid Valve RWCU Room 295 18,19 No Manufacturer No Model No.

92 Pressure Switch Secondary 256-297, 18,19 Barksdale Containment 298-300, B2T-M12SS 314-316, B2T-A12SS 320-321 I 93 Level Indicating Secondary 301-313 18,19 Switch Containment Yarway 4418C 4418CE 94 Motor-Operated Valve Inside 317-319, None Limitorque Drywell 330-332, SMB 333-335 SMB-2 95 Differential Pressure Secondary 322-324 18,19 Indicating Switch Containment Bartan 288 96 Differential Pressure NE and SE 325-329 18,19 Indicating Switch Corner Rooms Barton 288 97 Radiation Element GM Turbine 336-337 18,19 Tube Building General Electric DNG 194X927GI ,

98 Solenoid Valve Secondary 338-340 18,19 Versa /Barksdale Containment VPS-2402, VGS-4422/

DlE-A150SS 99 Diesel Auxiliary Diesel Room 2 341-342 18,19 Control Ideal Electric &

Manufacturing SO No. 267777 W-h-

.... Frankhn Research Center B-11

• ce w n.n n u, 4 - - - . . _ _ , , - -. . _

o .

TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 100 Excitation Cabinet Diesel Room 2 343-344 18,l9 Electromotive Div.

of GM 9474 101 Diesel Generator Diesel Room 2 345-346 18,19 Electromotive Div.

of GM 8366072 A-20-Cl 102 Switch Gear Secondary 347-350 18,19 General Electric Containment AMH 4.76-250 AKD-5 103A,H_. 480 V Motor Control Secondary 351-356, 18,19 Center Containment 370-372 General Electric 7700 104 Engine Control Panel Diesel Room 2 362-363 18,19 Electromotive . ,

Division of GM S20E4GW 105 4 kV Nonsegregated Turbine 364-365 18,19 Bus Building No Manufacturer No Model No.

106 D/G Secondary Diesel Room 2 366-367 18,19 Control Panel Ideal Electric S.O. 267777 107 D/G Neutral Grounding Diesel Room 2 368-369 18,19 Panel General Electric 208419-68P

• KVA-5 I

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dw l .... Franklin Research Center B-12 t a w s n.Fr a tv.

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

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TER-C5417-13 ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 102 Battery Charger Battery Charger 373, 379-380, 18,19 Gould Room 388-391 GRF240T100X GRF-120-T GRF-120T100X GRF24525F30X 109 250 V DC Motor Battery Charger 374-377 18,19,28 Control Center Rocm Cutler Hammer 6002H347B 110 DC Battery Battery Charger 378, 381, 18,19 Gould Room 386-387 FPS-25 FPR-13 DPR-9 111 DC Distribution Battery Charger 382-383, 18,19 Panel Room 392-393 Cutler Hammer No Model No. -

112 125 V DC Distribution Secondary 384-385 18,19 Panel Coritainment Cutler Hammer No Model No.

113 Motor-operated Valve Inside 394-395 20,22 Limitorque (Peerless AC) Drywell SMB 114 Motor Operated valve Steam Tunnel 396 18 Limitorque (Peerless DC)

No Model No.

115 Solenoid valve SW Corner Room 397 .98 18,19 ASCO 830281F 116 Differential Pressure SW Corner Room 399-400 18,19,25 Switch Barton 288 117 Temperature Switch SW Corner Room 402-411 18,19,26 Fenwal 17002-40 A -b

.... Franklin B*3 4cm aornPe,s,carch

, Center ain,u.

i .

TER-C5417-13 EQUIPMENT ITEM ITEM SUBMITTAL QUALIFICATION NO. DESCRIPTION LOCATION PAGE REFERENCES REFERENCES 118 Motor-operated Valve SW Cor.ser Room 412, 419 18,19 Limitorque SMB SMB-0 119 Pressure Switch SW Corner Room 413-416 18,19,27 Barksdale B2T-Al2SS 9

120 Solenoid Valve SW Corner Room 417, 418 18,19 ASCO 830281F t

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.... Franklin

• >= w w,m. Research.C. . n,. enter

TER-C5417-13 i

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 IE Bulletin 79-01B and was included in the Licensee's November 1, 1980 response.

-l I

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.... Franklin Research Ceriter C-1 4 %

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c. , - , , + . .. - - , , - - , , - i,c-,4- ,,e .- - - - - - . , , , - , - e y, ~ - ,,y, , ---.--- -,+, --- .%- - - - --,,--,--y-4 e -

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TER-C5417-13 e Reactor Protection System o Core Spray System o High-Pressure Coolant Injection System o Auto Depressurization System / Main Steam System o Residual Heat Removal / Containment Spray System e Pressure Suppression System o Stanoby Gas Treatment System o Service Water System e Diesel oil Piping System o Containment Isolation System * <

o Control Rod Drive Hycraulic System o -Reactor (Nuclear Boiler) Recirculation System e Process Radiation Monitoring System o Reactor Building Ventilation System o Control Room, HVAC e Standby Alternating Current Power e Standby Direct Current Power e Reactor Core Isolation Cooling System (RCIC) e General Use Electrical Equipment

• Containment isolation includes all components in various systems performing the containment isolation function.

d - h-~ .,

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ranklin Resear.en Center

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

, o TER-C5417-13 APPENDIX D - EQUIPMENT ITDi CROSS-REFERENCE LIST EQUIPMENT FINAL TECHNICAL ITEM 10. EVALUATION REPORT SECTION 1 4.6.1 2 4.6.2 3 4.5.2.1 4 4.5.2.2 5 4.5.2.3 6 4.5.2.4 7' 4.5.1.1 8 4.5.1.2 9 4.5.1.3 10 4.6.3 11 4.5.2.5 12 4.5.2.6 13 4.6.4 14 4.6.5 15 4.5.2.7 16

• 4.5.2.8 17 . , 4.5.2.9 18 4.7.1 19 4.5.2.10 20 4.5.2.11 21 4.6.6 22 4.5.2.12

1. 23 4.7.2 24 4.5.2.13 25 4.5.2.14 l

26 4.5.2.15 27 4.5.2.16 28 4.5.2.17 29 4.5.2.18 30 4.5.2.19 31 4.5.2.20 32 4.5.2.21 33 4.5.2.22 34 4.5.2.23 35

• 4.6.7 36 4.6.8 37 4.6.8 38 4.5.2.24 39 4.5.2.25 40 4.5.2.26 41 4.5.2.27 4-h- D-1 i

i

.... Franklin Research Center a rme s N nwea mew.

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TER-C5417-13 EQUIPMENT FINAL TECHNICAL ITEM NO. EVALUATION REPORT SECTION 42 4.5.2.28 43 4.5.2.29 44 4.5.2.30 45 4.5.2.31 46 4.5.2.32 4.5.2.33

• 47 48 4.5.2.34 49 4.5.2.35 50 4.5.2.36 51 4.5.2.37 52 4.6.9 53 4.5.2.38 54 4.5.1.3 55 4.5.2.39 56 4.6.10 57 4.5.1.5 58 4.5.2.40 59 4.5.1.6 60 4.5.1.7 61 4.5.2.41 62 4.6.11 63 4.5.2.42 64 4.5.2.43 65A 4.5.2.44 65B 4.6.12 66 4.5.2.45 67 4.5.2.46 68 4.5.2.47 69 4.5.2.48 70 4.7.3 71 4.6.13 72 4.6.14 73 4.5.2.49 74 4.6.15 75 4.5.2.50 i 76 4.7.4

! 77 4.7.5 78 4.7.6 79 4.7.7 80 4.5.2.51 81 4.5.2.52 82 4.5.2.53 83 4.6.16 84 4.5.2.54 85 4.5.2.55 86 4.5.2.56 I

87 4.5.2.57 D-2

.... Franklin Research Center s w o N rvranen e,oue

TER-C5417-13 EQUIPMENT FINAL TECHNICAL ITEM NO. EVALUATION REPORT SECTION 88 4.5.2.58 89 4.5.2.59 90 4.3.1.1 91 4.5.2.60 92 4.5.2.61 93 4.5.2.62 94 4.5.2.63 95 4.5.2.64 96 4.5.2.65 97 4.5.2.66 98 4.5.2.67 99 4.7.8 100 4.7.9 101 4.7.10 10 2 4.5.2.68 103A 4.5.2.69 103B 4.6.17 104 4.7.11 10 5 4.7.12 106 4.7.13 107

• 4.7.14 108 4.7.15 109 4.7.16 110 4.7.17 111 4.7.18 112 4.6.18 113 4.5.2.70 114 4.5.2.71 115 4.5.2.72 116 4.5.2.73 117 4.2.1.1 118 4.5.2.74 119 4.5.2.75 120 4.5.2.76

1. D-3

.... Franklin a %.aa .# Researc.h w re.n - Center