ML20004D980

Equipment Environ Qualification, Final Draft Technical Evaluation Rept

ML20004D980
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-C5417-012, TER-C5417-012-DRFT, TER-C5417-12, TER-C5417-12-DRFT, NUDOCS 8106100438
Download: ML20004D980 (150)

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TECHNICAL EVALUATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION l cmmSLTH EDISON QWANY l

QUAD CITIES NUCLEAR POWER STATION UtlIT 1 NRC DOCKET NO. 50-254 NRC TAC NO. 4'.478 FRC PROJECT C5417 EG&G IDAHO, INC. SU BCONTRACT NO. K4015 FRC TASK 12 j Prepared by l

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 EG&G Idaho, Inc., a prime contractor to the United States Department of Energy. Neither EG&G nor tne United States Government nor any agency thereof. or any of tneir employees. .

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

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

N THIS DOCUMENT CONTAINS lqd.

J Franklin Research Center POOR QUAL.lTY PAGES A Division of The Franklin insuute The Bengmin Frannlin Parkway Ph'ia Ps . ):2 2. 0, 446 , 'aM l

8106106438

1 TECHNICAL EVALUATION REPORT FINAL DRAFT EQUIPMENT ENVIRONMENTAL QU ALIFICATION COM U MEALTH EDISON CU P#lY f QUAD CITIES NUCLEAR POWER STATION Ut!IT 1 i

NRC DOCKET NO. 50-254 NRC TAC NO. 42478 FRC PROJECT C5417 EG&G IDAHO, INC. SU BCONTRACT NO. K-7615 FRC TASK 12 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 performeo under a subcontract from EG!.G

! Idaho. Inc., a prime contractor te the Uniteo States Department of Energy. Neither EG&G l nor the United States Government rior any agency thereof, or any of their employees.

makes any warranty e< pressed or implied, or assumes any legal tiability or responsiO; lit /

for any third party's use, or the results of such use. or any m.crmation. apparatus. procuct or prr:ess disclosed in this re::crt, or 'cresents that its use by sucn third party would not ininrge privately owned rights.

NOTE - THIS IS A DRAFT Because of senecule limitations. this report draf t has not gone through :ne comolete review Cycle of FRC. Wh le the overall conclusion is expected to rer tain the same. the reader is cautioned that some details of the report may change as the revie.:w is ;ompletec.

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TER-C5417-12 CONTENTS Section Title Page 1 INTRCDUCTION. . . . . . . . . . . . . . 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 NPC CRITERIA FOR ENVIRCNMENTAL 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 2.2.7 hadiactor. . . . . . . . . . . . 2-4 3 METHODOLOGY USED BY FRC . . . . . . . . . . . 3-1 4 TECHNICAL EVALUATICN. . . . . . . . . . . . 4-1 4.1 Methodology Used by the Licensee . . . . . . . 4-1 i

4.1.1 Environmental Conditions . . . . . . . 4-1 4.1.2 Aging . . . . . . . . . . . . 4-3 4.1.3 Identification of Electrical Compenents. . . . 4-3 4.1.4 Qualified Life . . . . . . . . . . 4-4 4.2 Equipment Qualified for Plant Life. . . . . . . . 4-5 4 h_- iii

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CONTENTS Section Title Page 4.2.1 NRC Category I.a Equipment That Fully Satisfies All Applicable Requirements of the COR Guidelines . . . . . 4-5 4.2.2 NRC Category I.b Iquipment for Which Deviations From the 00R 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 DCR Gaidelines 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 tade. . . . . . 4-6 4.3.3 NRC Category II.c Equipment for Which Deviations From the COR Guideliaes Are Judged Acceptable . . . . . 4-6 4.4 NRC Category III Equipment That Is Exempt Fecm Qualification . . . . 4-7 4.5 Equipment fer Whien Documentation Centains Deviations From the Guidelines That Are Judged Unresolved. . . . 4-3 4.5.1 NRC Category IV.a Equipment Which Has Qualification Testing Seneduled but Not Completed. . . . . . . 4-3 4.5.2 NRC Category IV.b Equipment for Which a Qaalificatien Documentation in Accordance With the Guidelines Has Not Been Established. . . . . . . . . . . 4-15 l

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o i TER-C5417-12 CONTENTS Section Title Pace 4.6 NRC Category V Equipment Which Is Unqualified. . . . . . . . 4-45 4.7 NRC Category VI Equipment for Which Qualification is Deferred . . . . 4-60 5 CCNCLUSICNS. . . . . . . . . . . . . . 5-1 6 REFERENCES . . . . . . . . . . . . . . 6-1 APPENDIX A - ENVIRCNMENTAL SERVICE CCNDITICNS APPENDIX B - EQUIPMENT ITEM TABLE APPENDIX C - SAFETY SYSTEMS FOR '#rfICH ENVIRCNMENTAL QUALIFICATICH IS TO BE ADDRESSED APPENDIX D - EQUIPMENT ITEM CROSS-RIFERENCE LIST 9

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1. INTRODUCTION 1.1 PURPOSE OF THE REVIEW The NRC Of fice of Inspection and Enforcement (IE) issued Bulletin 79-01B,

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

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

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

To meet the overall program goals, the objective of this Technical Evaluation Report is to review the Licensee's submittals 'to determine if the Licensee reviewed its safety-related electrical equipment for environmental qualification in accordance with the DOR Guidelines and NURIG-0588 as required by IE Bulletin 79-013. The NRC will perform an audit of the qualification

, documentation references as part of its safety evaluatien program. If discrepancies are found, the audit will be extended.

1.2 GENERIC ISSUE BACKGROUND Safety-related electrical equipment must be capacle of performing design safety functions under all normal, ace- mal, and accident conditiens. Of particular concern is the assurance that equipment will remain operable during

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TER-C5417-12 and following exposure to the harsh environmental conditions (i.e. ,

temperature, pressure, humidity (steam) , chemical sprays, radiation, and suomergence) 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 f ailures consequent to a loss-of-coolant accident (LOCA) , main steam line break (MSL3) 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 tre years, and industry standards concerning qualification have been revised as the design of reactor systems has changed and as regulatory and operating experience has accumulated. Examples of such standards are IE'E Standards 279-71, 323-74, 383-74, 317-76, 334-7,4, 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 IE

, Safety Related Equipment." The positions documented therein are applicable to plants that are or will be in the construction permit or cperating license review process.

Although qualification standards and regulatory recuirements have undergone considerable development, all of the currently operating nuclear power plants are required to comply with 10CFR50, Appendix A, General Cesign 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 renditions associated with normal operation, maintenance, testing, and postulated accidents, including less-of-cociant accidents."

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TER-C5417-12 In addition, qualification requirements are also embodied in 10CFR50 Appendix A, General Design Criteria 1, 2, and 23 and Appendix B, Cuality Assurance Criteria for Nuclear Power Plants and Puel 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 see met for electrical safety-related equipment. In the oldest plants, qualification was based on the fact that electrical components were of high industrial quality. After 1971, qualification was judged en the basis of IEEE 323-71; however, no regulatory guida ias issued adcpting the IEEE 323-71 standard. For plants whose Safety Evaluation Reports were issued after July 1, 1974, the Commission issued Regulatcry Gaide 1.39 whie 5 in most respects adopted 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. Ihe subject of electrical equipment environ-mental qualification (SEP Topic III-12) was selected for accelerated evalua-tion as part of this program. Seismic qualification of equipment was to be l addressed as a separate SEP topic. In December 1977, the NRC issued a generic l 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 l

deficiencies requiring immediate remedial actions were identified." However, it was recommended that additional effort should be devoted to examining the j installation and environmental qualification documentation of specific j electrical equipment in all operating reactors.

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6 TER-C5417-12 On May 31, 1979, 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.

Suosequently, on February 9,1979, the NRC Office of Inspection and Enforce-ment issued IE Bulletin 79-01, which was intended to raise the status of IE Circular 73-08 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 witnin the scope of equipment addressed, definition of harsh environments, and adequacy of support documentation. It became apparent that generic criteria were needed to evaluate the electrical equipment environmental qualification for both SEP and non-SEP operating plants. Therefore, during the second half of 1979, the Division of Operating Reactors (DOR) of the NRC issued internally a document entitled " Guidelines for Evaluating Environmental Cualification of Class lE Electrical Equipment in Cperating Reactors." (The document is hereafter referred to as the " DOR Guidelines.") The document was prapared as a screening standard for reviewing all operating plants, including SEP plants. Originally it was intended that the Licensees would evaluate their gus11fication documentation in accordance with the DOR Guidelines. However, initial NRC review of this documentation, which was compiled to support Licensee submittals, revealed the need for obtaining independent evaluations and for accelerating the qualification review program.

In October 1979, the NRC awarded Franklin Research Center (FRC) s contract to provide assistance in the " Review and Evaluation of Licensing Actions for Operating Reactors,' which included an assignment for review of equipment environnental qualification under SEP Topic III-12. FRC was git en the assignment to review equipment environmental qualification documentation Z_e 1-4

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. e TER-C5417-12 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 ana Enforcement issued the DCR Gdidelines and IE Bulletin 79-OlB, which expanded the scope of IE 3uJletin 79-01 and requested additional information on environmental qualification of safety-related electrical equipment at operating facilities, excluding the 11 facilities undergoing the SEP review. This Sulletin stated that the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification are the DOR Gaidelines. 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 critaria contained in the DOR Guidelines would be used in its review of Licensee submittals; problems arising from this review would be resolved using NUREG-0588 as a guide.

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

a. 3 Zion Units 1 and 2 should be included within SEP Topic III-12 for the purpose of equipment environmental qualification review.

On February 21, 1980, the NRC and representatives of the SEP Plant Owners Group held an open meeting at NRC headquarters to discuss an accelerated review program in accordance with the DOR sc.eening guidelines. Represen-tatives of the Indian Point Units and Zion Station also attended tnis 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 *dhich Environmental Qualification Is To Be Addressed," (29]

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

For non-SEP plants, the NRC Office of Inspection and Enforcement formed a task force including a principal reviewer in each region and a task leader i

from headquarters. The regional members are responsible for the technical

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review of the Licensees' responses to IE Bulletin 79-01B, and the task leader is responsible for the overall coordination of the review effort with NRC to assure overall consistency. The regional reviewers held meetings with the Licensees in their respective regions which resulted in staff positions being issued in a supplement to IE Bulletin 79-013 dated February 29, 1980.

In April 1980, the NRC organirational 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.

Cn May 27, 1950, the NRC issued Memorandum and Order CLI-80-21, [32]

specifying that Licensees and applicants must meet the requirements set forta in the COR Guidelines and NUREG-0588 regarding environmental qualification of safety-related electrical equipment in order to c'tisfy 10CFR50, Appendix A, General Design Criteria,Section I, Criterion 4. This Order also established that the Safety Evaluation Reports on this subject, to be prepared by the NRC staff, must be issued on February 1, 1981 and that all subsequent actions to be taken by Licensees to achieve full compliance with the DOR Cuidelines or I

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

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

1.3 SPECIFIC ISSUE 2ACKGROUND The staff hold regional meetings with the Licensees and interested parties during the week of July 13, 1980 in various locations. Ihe staff issued a second supplement to IE 3ulletin 79-013, a response to significant questiens raised during the public meetings, and two Ceders. The Order dated May 30, 1580 required the Licensees to comply with the previously issued Commission Memorandum and Order of May 27, 1980 (CLI-80-21) . The above Orders Mh 1-6

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TER-C5417-12 required the Licensees to complete the tasks identified in IE Bulletin 79-013 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.

o 1.4 SCOPE OF DIE REVIEW Environmental qualification of safety-related electrical equipment was selected by the NRC for accelerated review. Therefore, the scope of this report is limited to equipment that must function to mitigate the consequences of a loss-of-coolant accident (LOCA) or high energy line break (HELB) and whose environment is adversely affected by that event. In addition, IE Bulletin 79-018 requires enviremental qualification for all safety-related electrical equipment exposed to a harsh environment in accordance with the DCR Guidelines or NUREG-0588. Harsh environments include the limiting conditions resulting from (i) the entire spectrum of postulated line breaks resulting from a less-of-coolant accident (LOCA) or a high energy line break (HELB) inside and outside of containment and (ii) radiation from fluids which are recirculated fecm inside containment to accomplish long-term cooling subsequent to an accident. Qualificaticn 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 equit. snt protection against fire hasards e equipment protection against missiles.

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2. NRC CRITERIA F@R ENVIRONMENTAL QUAltFICATION e

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2. NRC CRITERIA FOR ENVIRONMENTAL QUALIFICATION 2.1 CRITERIA PROVIDED BY THE NRC The DOR screening guidelines used by FRC to evaluate the electrical equipment environmental qualification 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 Equipe.:ent." (34)

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

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

2.2.1 SERVICE CONDITIONS INSIDE CONTAI!DiENT IUR A LOSS-OF-COOLANT ACCIDENT (DOR GUIDELINES SECTION 4.1)

For Pressurized Water Reactors (PWRs), the DOR Guidelines state that the containment temperature and pressure conditions as a function of time should be based on the most recent NRC-approved service conditions specified in the Final Safety Analysis Report (FSAR) or other Licensee documentation. In the specific case of pressure-suppression type centainments, the following minimum high temperature conditions may be used: (1) Boiling Water Reactor (3WR)

Drywells -- 340*F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and (2) PWR Ice Condenser Lower Compartments --

340 *F for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. As stated in Supplement 2 to IE 3ulletin 79-013, (30]

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

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9 O TER-C5417-12 lieu of a plant-specific profile, provided that expected pressure and humidity cenditions as a function of time are accounted for."

Service conditions should bound those expected for coolant and steam line breaks inside containment with due consideration given to analytical uncertainties. The steam line break condition should include superheated conditions, with peak temperatu and subsequent temperature / pressure profile as a function of time. If containment spray is to be used, the impact of the spray on required equipment should be accounted for.

The adequacy of a plant-specific profile is dependent on the assumptions and design considerations at the time the profiles were developed. The DCR Guidelines and NUREG-0588 provide guidance and considerations required to determine if the calculated plant-specific temperature /pressura profiles encompass the LOCA and HEL3 accidents inside containment.

2.2.2 SUBMERGENCE (DOR GUIDELINES SECTION 4.1, SUBITEM 3 and SZCTION 4. 3.2, SUBITEM 3)

Equipment submergence (iriside or outside containment) should be addressed where the possibility exists that submergence of equipment may result from HEL3a or other postulated occurrences. Supplement 2 to IE 3ulletin 79-013 (30] provides the following additional criterion: If the equipment satisfies the guidance and other requirements of the DOR Guidelines or NUREG-0588 for the LOCA and HELS accidents, and the Licensee demonstrates that its failure will not adversely affect any safety-related function or mislead the operator after submergence, the equipment can be considered exempt from the submergence portion of the qualification requirements.

2.2.3 EQUIPMENT LOCATED IN AREAS NORMALLY MAINTAINED AT RCCM CONDITIONS (DOR GUIDELINES SECTION 4.3.3)

Supplement 2 of IE Bulletin 79-01B (30] permits deferment of the review of environmental qualification for all safety-related equipment items located in plant areas where the equipment is not exposed to the direct effects of a HELD or to nuclear radiation emanating from circulation of fluids containing radioactive substances. At the Licensee's option, the review may be deferred.

until af ter February 1,1981.

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TER-C5417-12 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 DCR Guidelines or NUREG-0588 (as applicable) . Safety-related electrical equipment is that required to bring the plant to a cold shutdown condition and to mijigate the consequences of the accident. It is the responsibility of the Licensee to evaluate the qualification of safety-related electrical equipment to function in environmental extremes not associated with accident conditions and to document it in a form that will be available for the NRC to audit.

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

2.2.4 SIMULATED SERVICE CONDITIONS AND TEST DURATION (DOR GUIDELINES SECTICN 5.2.1)

The Guidelines require that the test chamber environment envelop the required service conditions for a time eg,uivalent to the period from the

initiation of the accident until the service conditions retu

n to normal.

Supplement 2 to IE Bulletin 79-013 [30] provides the following additional criterion: " Equipment designed to perform its safety-related function within a short time into an event must be qualified for a period of at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in excess of the time assumed in the accident analysis. The staff has indicated that time is the most significant factor in terms of the margins required to provide an acceptable confidence level that a safety-related function will be completed. The 1-hour qualification requirement is based on the acceptance of a type test for a single unit and the spectrum of accidents (small at;d large breaks) bounded by the single test."

2.2.5 DEFERMENT 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:

l e Qualification infermation for installed TMI Action Plan equipment must be submitted by February 1,1991.

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TER-C5417-12 e Qualification information for future TMI Action Plan equipment (reference NUREG-0737, when issued), which requires URC pre-implementation review, must be submitted with the pre-implementation review data, o Qualification information for TMI Action Plan equipment currently under NRC review should be submitted as soon as possible.

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

e Qualification information for equipment required to achieve and maintain a cold shutdown condition should not be submitted latur than February 1, 1981.

2.2.6 TEST SEQUENCE (DOR GUIDEI.INES SECTION 5. 2. 3)

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

" Sequential testing requirements are specified in NUREG-0538 and the OCR Gaidelines. 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 be evaluated regarding the ability to comply by incorporating aging in the pecper sequence. These programs would then fall in the first or second category."

2.2.7 RADIATION (00R GUIDELINES SECTIONS 4.1. 2, 4. 2. 2, and 4. 3. 2, SUBITEM 2)

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

"Both the DCR Guidelines and NUREG-0538 are similar in that they providu the methods for determining the radiation source term when censidering LOCA events inside containment (100% acble gases /50% iodine /1% partic-ulates). These methods consider the radiation source term resulting fecm an event which completely depressurires the primary system and releases the source term inventory to the containment.

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TER-C5417-12 NUREG-0578 provides the radiation source term to be used for determining the qualification doses for equipment in close proximity to recirculating fluid systems inside and outside containment as a result of LOCA. *his method considers a LCCA event in which the primary system may not depressuri:e and the source term inventory remains in the coolant.

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

When developing radiation source terms for equipment qualification, the Licer.2;e must ensure censideration is given to those events which provide the most bounding conditions. The following table summari:es these consideratiens (FCS = reactor coolant system) :

LOCA Mon-LOCA HEL3 Outside Containment NUREG-0578 NUREG-0588 (100/50/1 (10/10/0 in RCS) in RCS)

Inside Containment *a rger of NUREG-0588 NUREG-0588 (10,0/50/1 (10 /10/0 in Containment) in RCS) or NUREG-0 578 (100/50/1 in RCS)

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

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3. METHODOLOGY USED BY FRC IE Bulletin 79-01B required the Licensee tot e provide a master list which identifies the systems and electrical equipment required to function during and subsequent to an accident and to maintain the plant in a safe condition e provide the environmental service conditions e identify the submergence levels e provide written evidence of the qualification of the equipment identified e evaluate the qualificacion documentation using the COR Guidelines and NUREG-0588 e submit a Licensee Event Re port (LER) for electrical equipment determined not to be anvironmentally qualified.

4 The requiremenes of IE Bulletin 79-01B were requested under provisions of 10CFR5 0.5 4 (f) , " Conditions of Lict.nses," which requires the Licensee to submit written statements, signed under occh or affirmation, to enable the Commissien to determine whether or not a license should be modified, suspended, or revoked.

To provide assurance that the Licensee implemented the requirements of IE Bulletin 79-01B and to .orovide a basis for the NRC Safety Evaluation Report (SER), F3C developed this Technical Evaluation Report (TER) by:

i e assessing the Licensee's responses in relation to the general requirements of the DCR Guidelines as augmented by the supplements to the 79-013 Bulletin e using NUREG-0588 to resolve open issues.

The results and conclusions contained in this report are valid assuming i daat the Licensee's analyses of test reports referenced in the Licensee submittal are correct. Review of test reports was not within the secpe of FRC's assignment. However, the NRC staff will audit selected analyses and is ,_1

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TER-C5417-12 test reports, incorporating the rasults of the reviews with the conclusione of the TERs, when developing the plant-specific SERs.

Ite 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 1 in its submittals to the NRC. FRC analyzed the Licensee's listing and grouped together all identical equipment items located within plant areas that are exposed to the same environmental service conditions. This analysis resulted in a reduced listing containing (148) 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 tha 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 tists the plant systems identified by the Licensee and the NRC as being essential to safety.

Using the listing of safety-related electrical equipment items,* each equipment item was reviewed by FRC in relation tot e NRC DOR Ouidelines, as modified by NRC staf f interpretations e Licensee definition of harsh servic6 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 acceptability of Licensee-provided environmental service conditions e acceptability of Licensee-stated position concerning safety system or component function e review and acceptability of qualification 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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TER-C5417-12 Upon completion of the final review for each equipment item, FRC developed an overall evaluacion of the component and a specific conclusien with respect to its qualification. Based on the FRC conclusion, each equipment item was assigned to one of the generic qualification categories provided by L.4 NRC. NRC categories are described below.

All equipment item numbers discussed in Sectica 4 of this report are associated with Reference 33.

The NRC Office of Inspection and Enforcement conducted an on-site verification inspection of selected IE equipment to verify proper ?nstallatien of equipment, overall interface integrity, location with respect to flood level for equipment inside the containment, and =anufacturer's nameplate data. The manufacturer and model number from the nameplate data were compared to information given in the System Component Evaluation Work Sheets (SCIWS) of the Licensee's report. The details of this site inpection are documented in an internal NRC memorandum (35] and will be addressed by the NRC.

NRC QUALIFICATION CATEGORIES AND DEFINITIONS e NRC Category I.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES This category includes equipment items which are fully acceptacle 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.

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EQUIPMENT FOR WHICH DEVIATIONS FRCM THE COR GUIOELINES ARE JUCCED

( ACCEPTABLE This categcry includes equipment items which do not satisfy one er_mcre of the applicable criteria defined in the DOR Guidelines; however, sufficient information has been presented to determine that the specific deviatiens are acceptable.

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, o NRC Category II.i EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE COR GUIDELINES AND HAS A SERVICE LIFE LESS I LAN PLANT LIFE This category includes equipment items that are fully acceptable on the baris that all applicable criteria defined in the DCR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less than plant life.

e NRC Category II.b

EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR 4

GUIDELINES PROVIDED THAT SPECIFIC '!ODIFICATIONS ARE MADE This category includes equipment items which will be fully acceptable and will satisfy all applicable criteria defined in the DOR Guidelines providef that specific modifications are made on or before the designated date. When the modifications are compl;te, the equipment can be considered qualified.

e NRC Category II.c EQUIPMENT FOR WHICH DEVIATIONS FRCM THE COR GUIDELINES ARE JUDGED ACCEPTABLE This category includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelines; however, either .

sufficient bases have been presented to allow a determination that the specific deviations are judged to be acceptable for'less than plant life or the specific deviations are judged by FRC to be acceptable for less than plant lifa based on review of the applicable qualification decumentation associated with the general equipment environmental qualification program. .

e NRC Category III EQUIPMENT THAT IS EXEMPT FROM QUALIFICATION This category includes equipment items which are exempt from qualification on the basis that (i) the equipment does net 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 te accomplished by some other designated component which is fully qualified, or (111) the equipment is not subject to a potentially adverse environment as a result of accidents for wnich proper operation of the equipment is required. In addition, any failure of the exempt ecmponent must not degrade the ability of a qualified component to perform its required saf ety-related function.

e NRC Category IV.a EQUII-+1ENT *(dICH HAS QUALIFICATION TESTING SQtEDULED SUT NOT COMPLETED Ihe qualification of equipmer.t items in this category has been judged deficient or inadequace based upon review of the documentation provided by the Licensee. However, the Licensee has stated that the equipment item is

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TER-CS417-12 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 GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of equipment items in this categocy is deficient or inconclusive based upon review of the documentation provided by the Licensee.

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

o NRC Category V EQUIPMENT WHICH IS UNQUALIFIED The DCR Guidelines require that complete and auditabte records reflecting a comprehensive qualification methodology and program be referenced and made available for review of all Class lE equipment.

The qualification of equipment items in this category has been judged to be deficient or inadequate, based upon review of the documentation provided by the Licensee. The extent to which the equipment items fail to satisfy the crite of the DOR Guidelines can be categcrised as follows: (i) documen-tatio. .eflecting qualification as specified in the DOR Guidelines has not been made available for review, fii) qualification documentation made available for review is inadequate, or (iii) the documentation indicates that the equipment item has not passed the required tests.

e NRC Category VI l EQUIPMENT FCR WHICH QUALIFICATION IS DEFERRED i This category includes equipment items which have been addressed by the Licensee in the equipment environmental qualification submittals; however, the l qualification review of this equipment has been deferred by the NRC in l

accordance with criteria presented la Sections I.2.3 and 2.2.5 of this

.eport.

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4. TECHNICAL EVALUATION 4.1 METHODOLOGY USED BY THE LICENSEE The final response to IE Bulletin 79-018 from the Licensee dated November 1,1980 contained a general 1 -troductory 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 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 located within compartments with postulated HEL3s would be subjected to pressure, temperature, and humidity conditions resulting from that HELB, but would not be subjected to radiation doses in excess of 5 x 104 rads simultaneously. These same components could be subjected to radiation doses 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 comoination of all environmental conditions.

Where qualification could not be demonstrated for the entire spectrum of conditiens simultaneously, components were evaluated for the conditions associated with each individual accident. Environmental conditions are based on the specific accidents for which the components must function. Components which are exposed to harsh environments during accidents for which they are not required to function do not require qualificatien 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 would adversely affect connected circuits. Therefore, equipment which has no active functicn during a DBE cannot be exempted from qualification for this reason only. Also, FRC is concerned that qualification for a short operating

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TER-C5417-12 period may not be sufficient if failures in equipment at some point after a required operating period would adversely affect connected circuits. FRC notes that short operating periods are given for some of the equipment listed 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 areast

a. Integrated doses have been calculated for areas outside the drywell. Doses were establisned for 1 day, 30 days, and 1 year exposure. Integrated doses of lessEthan 5 x 104 rada during a ecmponent'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, succeptibility to performance degradation may occur at threshold levels lower than 5 x 10 rads. For other types of electrical equipment which do not contain electronic components, FRC does not expect noticeable degradation to occur below 5 x 10 4 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 additionally, where temperature variations are not a result of the postulated accidents are considered as mild environments. Equipment in these areas functions normally in the same environment as postulated for post-accident conditions. For nonharsh and mild environments, qualification data is not required.

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

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1 TER-C5417-12 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 design basis event (DBE) .

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

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

b. Most areas outside the drywell are maintained in a suitable environmental condition by safety-related HVAC equipment. The normal maximum environmental design temperature is 103*F, which in this study is 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 nonharsh. In addition, temperature extremes (up to 120*F) may occur in some plant areas. Mcwever, 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 a.re not considered for components located in areas where the maximum ambient temperature is maintained at 120*F or below.

i FRC's previous statements concerning radiation and temperature apply to l

these assumptiens. It is not obvious that 120*F is due in all cases to causes I

l other than a DBE. The Licensee has not clarified this for individual equipment items listed in the Licensee's response.

4.1.3 IDENTIFICATION OF ELFC"RICAL COMPCNENTS The Licensee states that the FSAR was the basis for determining the equipment for which qualification documentation is required.

The clearly stated NRC position is that equipment items needed for i mitigation of an accident, including that identified in the Emergency Cperation Procedures that the Licensee relies upon t'a mitigate design basis events, musu be evaluated either to demonstrate qualificatien or to provide

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TER-C5417-12 justification that unqualified equipment will not be mislealing to the operator. Whether or not 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-related equipment identified by the Licensee as essential for safe shutdown of the plant. The DCR Guidelines required that equipment with components that are susceptible to degradation caused by thermal, radiation, or wear conditions is to have an established qualified life.

The Licensee should maintain detailed maintenance records to demonstrate th a t those components which can Le 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 lif e is the maxixim pericd of normal service under specified conditions for which it can be demonstrated that the functional capability of the equipment at the end of the period is still adequate for it to perform its specified safety function for an applicable accident and to remain functional as long as required after the accident. The qualified life may depend on carrying out a specifieu maintenance program. The qualified life of some elements of an equipment assembly may be less than the qualified life of the assemoly 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 cnanged 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 saf aty-related equipment that requires environmental qualification. A censervative choice of qualified life must be made to account for the assumptions and approximations made in the qualification program.

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TER-C5417-12 4.2 EQUIPMENT QUALIFIED .FOR PLANT LIFE This section includes equipment items which are fully acceptable on the basis that (i) all criteria defined in Section 2 of the report are satisfied or (ii) sufficient data exist to determine acceptability by judgment.

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

4.2.1.1 Equipment Item No. 125 Temperature Switches Located in the NW Corner Rcom Fenwal Model 17002-40 (Licensee References la,19, and 27)

Licensee Reference 27 is a test report. The Licensee indicates that the qualification data is satisfactory.

l 4.2.2 NRC Category I.b l

EQUIPMENT FOR WHICH DEVIATIONS FRCM THE DCR GUIDELINES ARE l JUDGED ACCEPTABLE This section normally includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Gaidelines; however, sufficient information has been presented to determine that the specific deviations are acceptable. For the Quad Cities Unit 1 plant, there -- no equipment items fallt in this category.

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TER-C5417-12 4.3. EQUIPMENT QUALIFIED WITH RESTRICTIONS This section includes equipment items fully saceptable on the basis that (1) all criteria defined in Section 2 of this report a 'e satisfied, (ii) the equipment is qualified for a time interval less than plcat life, or (iii) the equipment requires specific modification which, when completed, will establish full qualification.

4.3.1 NRC Category II.a EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES AND HAS A SERVICE LIFE LESS THAN PLANT LIFE Equipment items in this category are fully acceptable on the basis that-all applicable criteria defined in the DOR Guidelines are satisfied and that the equipment is qualified for a specific time interval which is less then plant life. For the Quad Cities Unit 1 plant, there are no equipment items in this category.

4.3.2 NRC Category II.b EQUIPMENT THAT FULLY SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DCR GUIDELINES PROVIDED THAT SPECIFIC MODIFICATIONS ARE MADE Equipment items in this category will be fully acceptable and will satisfy all applicable criteria defined in the COR Guidelines provided that specific modifications are made on or before the designated date. When the modificatiens are completed, the equipment can be considered qualified. For the Quad Cities Unit i plant, no equipmer.t falls in this category.

4.3.3 NRC Category II.c EQUIPMENT FOR WHICH OEVIATIONS FRCM THE CCR GUIDELINES ARE 'UDGED ACCEPTABLE This section includes equipment items which do not satisfy one or more of the applicable criteria defined in the DOR Guidelinest however, either suffi-cient bases have been presented to allow a determination that the specific deviatiens are judged to be acceptable for less than plant life, or the specific deviations are judged by TRC to be acceptable for less than plant life based on review of other applicable qualification documentation associated with the general equipment envicenmental qualification program. For the Quad Cities Unit 1 plant, there are no equipment items in this category.

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TER-C5417-12 4.4 NRC Category III EQUIPMENT THAT IS EXEMPT FROM QUALIFICATION 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. For L the Quad Cities Unit 1 Plant, there are no equipoent items in this category.

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TER-C5417-12 4.5 EQUIPMENT EUR WHICH DOCUMENTATION CONTAINS DEVIATIONS FROM THE GUIDELINES THAT ARE JUDGED UNRESOLVED This section includes equipment items which are deficient on the basis that all criteria defined' in the DOR Guidelines are not satisfied. However, the equipment item is either scheduled to be tested or is judged to have a high likelihood of operability.

4.5.1 NRC Category IV.a EQUIPMENT WHICH HAS QUALIFICATION TESTING SCHEDULED BUT NOT COMPLETED The qualification of the following equipment items has been judged deficient or inadequate based upon our 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 re?aits 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.

4.5.1.1 Equipment Item No. 7 Pressure Transmitter Located in the NW and SW Corner Rooms Gen.aral Electric Model 453 2K11001 (Licensee References 19 and 21)

Licensee Reference 21 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, 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 reason:

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 redundant systems beyond those needed for coolant injection. This would result in radiation' exposures to only one of two redundant equipment trains. Also acutal doses would be less than these calculated using such conservative assumptions.

Finally, should the operating equipment suffer degradation due to 3- 4-8

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TER-C5417-12 radiation expnsure, 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.

4.5.1,2 Equipment Item No. 8 Flow Transmitter Located in the NW and SW Corner Rooms General Electric Model 4532K43001 (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 service to qualify this eculpment 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 j ustified for the following reasons:

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

,hich w 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 calcuJated using such conservative assumptions.

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

During the time available after stabilization of core cooling, additional

! coolant injection paths :ould be established, if necessary, to assure long-term cooling.

! 4.5.1.3 Equipment Item No. 9

Flow Switch Located in the NW and SW Corner Rooms l Barton Model 289 (Licensee References 18,19, and 22) l Licensee Reference 22 is a qualification test report that we have not I

previously reviewed. The Licensee indicates that radiation was not addressed in this report and makes the following statements and commitments:

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 ccmponents. Although qualification data is not available, continued station cperation is justified for the following reason:

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TER-C5417-12 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 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 expom 2, the shut down redundant system could be activated.

During the time available af ter stabili:ation 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 Mouci GE/MAC 553 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; ther e fort , 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 reason:

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

t ime, action will be taken to shut down redundant systems beyond those l 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 cc I

radiation exposure, the shut down redundant system could be act.ivated.

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

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TER-C5417-12 4.5.1.5 Equipment Item No. 57 Pressure Switch Located in the NE and SE Corner Rooms Mercoic Model GN-L-3 (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 statement 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 ce replaced with qualified components. Although qualification data is not available, continued station operation is j ustified for tne following reason:

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 t ime , 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 tr.n 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 injection paths could be established, if necessary, to assure long term cooling .

t J.l.6 Equipment Item No. 131 Cable, Location Not Stated General Electric, >bdel Not Stated (Licensee reference not cited)

No qualification references have been cited for this item. The Licensee makes the following statements and commitments:

( A contract will be issued for services to qualify this equipment by l 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. Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation cu.. censer pipe chase,

torus compartment (near postulated HPCI break only) , and RNCU rooms i contain equipment which must function in 1 mir ' . less. Once equipment furstions are completed, there woul . no further active function required. In all cases except the torus compartment, the j only cables entering the potential harsh environment area would l

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TER-C5417-12 terminate in that area. In the case of the torus compartment, other cabling could be in the vicinity of the HPCI line break; however, the torus compartment is so large that the harsh environment would dissipate almost instantly with valva closure. Radiation is not concurrent with other harsh conditions.

b. 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 be less than those calculated using such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

4.5.1.7 Equipment Item No.13 2 Cable Located in the Outside Drywell Simplex, Model Not Stated (Licensee reference not cited)

No qualification referenc,es have been cited 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. Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near postulated HPCI break only), and RWCU rooms contain equipment which must function in 1 minute or less. Once equipment functions are completed, there would be no further active function required. In all cases except the torus compartment, the only cables entering the potential harsh environment

area would terminate in that area. In the case of the torus I compartment, other cabling could be in the vicinity of the HPCI line break; hcwever, the torus compartment is so large that the harsh environment would dissipate almost instantly with valve closure.

Radiation is not concurrent with other harsh conditions.

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

Actual doses would be less than those calculated using such conservative assumptions. In addition, harsh radiation is not 2h

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TER-C5 417-12 concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

4.5.1.8 EquipNent Item No. 133 Cable L7cated Inside the Drywell Simplex, Model Not Stated (Licensee reference not cited)

No qualification references have been cited 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 j ustified for the following reasons:

a. These components or similar items have been partially tested for p environmental conditions.

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

4.5.1.9 Equipment Item No. 138A Cable Polyvinyl Chloride Jacket Located Outside Drywell General Electric, Model Not Stated l (Licensee reference not cited)

No qualification references have been cited for this item. The Licensee makes the following statements and commitments:

A contract will be issued for services to qualify this equipment by analysis an3/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. Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near postulated HPCI break only) , and RWCU rooms contain equipment which must function in 1 minute or less. Once equipment functions are completed, there would be no

1. e 4-13

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e TER-C5417-12 further active function required. In all cases except the torus c ompartment , the only cables entering the potential harsh environment area would terminate in that area. In the case of the torus compartment, other cabling could be in the vicinity of the HPCI line break; however, the torus compartment is so large that the harsh environment would dissipate almost instantly with valve closure.

Radiation is.not concurrent with other harsh conditions.

b. 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.

i Actual doses would be less than those calculated using such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

4.5.1.10 Equipment Item No. 138B

- Cable Located Within the Drywell General Electric, Model Not Stated (Licensee reference not cited)

No qualification reference has been cited for this item. The Licensee makes the following statements and ccmmitments:

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 L justified for the following reasons:

a. These components or similar items have been partially tested for

environmental conditions.

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

i l

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TER-C5417-12 4.5.1.11 Equipment Item No. 139 Cable Polyvinyl Chloride Jacket, Location Not Stated Simplex, Model Not Stated (Licensee reference not cited)

No qualification reference has been cited 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, failing which the appropriate equipment or parts thereof will be replaced with qualified components. Although i qualification data is not available, continued station operation is justified for the following reasons:

a. Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near postulated HPCI break only) , and RWCU rooms contain equipment which must function in 1 minute or less. Once equipment functions are completed, there would be no further active function required. In all cases except the torus compartment, the only cables entering the potential harsh environment area would terminate in that area. In the case of the torus compartment, other cabling could be in the vicinity of the HPCI line break;

• however, the torus compartment is so large that the harsh environment would dissipate almost instantly with valve closure. Radiation is not concurrent with other harsh conditions.

b. 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 be less than those calculated using such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, stress factors are not present to accelerate damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

l 4.5.1.12 Equipment Item No. 140 Plastic Insulation and Jacket Located Outside Drywell Simplex, Model Not Stated (Licensee reference not cited)

No qualification references have been cited 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

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TER-C5417-12 thereof will be replaced with qualified components. Although qualification data is not available, continued station operation is justified for the following reasons:

a. Of the plant areas which could experience harsh pressure, temperature, and humidity, only the steam tunnel, isolation condenser pipe chase, torus compartment (near postulated HPCI break only) , and RWCU rooms contain equipment which must function in 1 minute or less. Once equipment functions are completed, there would be no further active function required. In all cases except the torus compartment, the only cables entering the potential harsh environment area would terminate in thar area. In the case of the torus compartment, other cabling could be in the vicinity of the HPCI line break; however, the torus compartment is so large that the harsh environment would dissipate almost instantly with valve closure. Radiation is not concurrent with other harsh conditions.

b. 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 be less than those calculated using such conservative assumptions. In addition, harsh radiation is not concurrent with pressure, temperature, and humidity; therefore, although some material degradation may occur due to radiation, , stress factors are not present to accelerate. damage. Finally, most of the materials utilized for this cable are currently utilized and have demonstrated the ability to withstand the radiation levels for which they must be qualified.

4.5.2 NRC Category IV.b EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION IN ACCORDANCE WITH THE GUIDELINES HAS NOT BEEN ESTABLISHED The qualification of the following equipment items is deficient or inconclusive based upon our 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 ccmprehensive qualification documentation have not been made available for review. Specific justification for interim plant operation should be provided for each item.

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TER-C5417-12 4.5.2.1 Equipment Item No. 3A Motor Operated Valve Located in the NW and SW Corner Rooms Limitorque Model SMB-0-25 (Licensee References 18,19, and 20)

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

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

4.5.2.2 Equipment Item No. 3B Motor Operated Valve Located in the NW Corner Rocm Limitorque Model SMB (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 it.em 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. 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.

4.5,2,3 Equipment Item No. 4 Motor Operated Valve Located in the Secondary Containment Area Limitorque Model SMB-0-15 with Peerless AC Motor (Licensee References 18, 19, and 20)

Licensee Reference 20 is a test report for Limitorque valte operators.

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

l l

l l 4.5.2.4 Equipment Item No. 5 j Motor Operated valve Located in the Secondary Containment Area Limitorque Model SMB-2-40 with Reliance AC Motor (Licensee Reference 7)

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

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TER-C5 417-12 4.5.2.5 Equipment Item No. 6 Motor Operated Valve Located in the Torus Area Limitorque Model SMB-000 with Reliance AC Motor (Licensee Reference 7)

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

The Licensee makes the following statements and commitmemts:

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 provice a minimum flow line. Should the valve fail 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 af ter the postulated accident. During this time, action will be taken to shut down redundant systems beyond those needed for coolant inj ection.' This would result in radiation exposures to only 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 long term cooling.

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

4.5.2.6 Equipment Item No. 11 Stop Valve Located in the HPCI Rooms Manufacturer Not Stated, Model 17 8250H02D4 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualificaticn test reports; therefore, qualification documentation is deficient for this item. The Licensee has indicated that the required operating period 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 operating period, FRC concludes that the qualification review can be deferred Mh 4-18

.. ; Franklin Research Center a cmn or n, remn +.w.

TER-C5417-12 unti*. 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.

4.5.2.7 Equipment Item No. 12 Motor Operated Valve Located in the HPCI Room Limitorque Model SMB-3 with Peerless DC Motor (Licensee References 18 and 19)

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

4.5.2.8 Equipment Item No. 15 Motor Operated Valve Located in the HPCI Room Limitorque Model SMB-0 (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 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.

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TER-C5417-12 4.5.2.9 Equipment Item No. 16 Motor Operated Valve Located in the Steam Tunnel Limitorque Model SMB-3-80 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 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 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. 17 Motor Operated Valve Incated in the HPCI Room Limitorque Models SMB-2, SMB-3,and SMB-4 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee hia 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.

4.5.2.11 Equipment Item No. 18 Motor Operated Valve Located in the HPCI Room Limitorque Model SMB-0 and SMB-000 (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 M -i 4-20

.... Franklin Research Center 4om.ona#n. % am w e

TER-C5417-12 peak temperature is not a result of the DBE in order to conclude that the DBE l environmental stress is negligible.

1 4.5.2.12 Equipment Item No. 19 Solenoid Valves Located in the HPCI Room ASCO Model 830281F (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 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 d3at the DBE environmental stress is negligible.

4.5.2.13 Equipment Item No. 21 Flow Transmitter Located in the HPCI Room General Electric Model 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 days. If the environmental stress remains negligible for this item during the stated ope:ating 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 s result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.14 Equipment No. 22 Pressure Transmitter Located in the HPCI Room General Electric Model 453 2K11001 (Licensee References 19 and 21)

Licensee Reference 21 is a qualification report which will be reviewed later. This item has been placed in its most likely category pending review.

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TER-C5417-12 4.5.2.15 Equipment Item No. 24 Pressure Transmitter Located in the HPCI Room General Electric Model 50-551032CAAY1 (Licensee References 13,19, and 21)

Licensee Reference 21 is a qualification report which will be reviewed later. This item has been placed in its most likely category pen <*.ng review.

4.5.2.16 Equipment Item No. 26 Turbine Gland Seal Condensate Drain Pump Located in the HPCI Room General Electric Model 58225A3525 (Licensee References 18 and 19 4

i 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 fer this item during the stated operating period, FRC concludes that the qualification review can be t - 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 i environmental stress is negligible.

5 4.5.2.17 Equipment Item No. 27 4

Gland Steam Exhaust Fan Located in the HPCI Room General Electric Model 5BC74AB2193 I

(Licensee References 18 and 19) i

' 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 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.

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TER-C5417-12 4.5.2.18 Equipment Item No. 28 Motor Speed Changer Incated in the HPCI Rocm General Electric Model GE5BC26AC389 (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 order to conclude that the DBE environmental stress is negligible.

4.5.2.19 Equipment Item No. 29 Motor Gear Unit Located in the HPCI Room General Electric Model SCD14019A111620 (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 dtring 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 l environmental stress is negligible.

4.5.2.20 Equipment Item No. 30 Oil Pump Motor Located in the HPCI Room

! General Electric Models SCD218E252 and SCD326E758 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 12 l 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 l

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TER-C5417-12 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. 31 HPCI Motor Control Signal Converter Located in the HPCI Room General Electric Model 357 513TC108 (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 order to conclude that the DBE environmental stress is negligible.

4.5.2.22 Equipment Item No. 32 Level Switch Located in the HPCI Rocm Mercoid Model 123-2 (Licensee Referer.ces 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 dayc. 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 l environmental stress is negligible.

l 4.5.2.23 Equipment Item No. 33 l Level Switch Located in the HPCI Room l Magnetrol Model 291-SP (Licensee References 18,19, and 23) l l Licensee Reference 23 is a test report. The data presented by the Licensee indicates that all qualification requirements except aging are l

satisfied. If the environmental stress remains negligible for this ite.n l

i I

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TER-C5417-12 during the stated operating, period of 12 days, 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.

4.5.2.24 Equipment Item No. 34 Flow Switch Located in the HPCI Room Barton Model 289 (Licensee References 18 and 19)

Licensee Reference 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 12 d ays. 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 QBE in order to conclude that the OPE environmental stress is negligible. -

4.5.2.25 Equipment Item No. 35 Pressure Switch Located in the HPCI Room Static-O-Ring Model 6NN-AA21-VRR (Licensee References 18 and 19)

Licensee References 1.8 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.er 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.

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TER-C5417-12 4.5.2.26 Equipment Item No. 36 pressure Switch Located in the HpCI Rocm 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 dayJ. If the environmental stress remains negligible for this item during the stated operating period, FRC concludJs that the qualification review can be deferred until after February 1,1981 in accordance with NRC criteria presanted 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.

4.5.2.27 Equipment Item No. 39 Motor Operated Valve Located Inside the Drywell Limitorque, Model Not Stated (Licensee References 20 and 24)

Licensee References 20 and 24 are test reports on Limitorque valve operators. The Licensee makes the following statements and commitments:

The test procedure required saturated atmosphere. Additional vendor inform ation is being sought to resolve outstanding environmental qua*ification items, but humidity was not measured during the test. The test used saturated steam for temperature. 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 period of time and would not experience siginficant effects of increased environmental conditions in this short time peri.od.

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

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

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

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o e TER-C5417-12 t.5.2.28 Equipment Item No. 40A Motor Operated Valve Located in the Steam Tunnel Limitorque Model SMB-00-7.5 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 35 seconds. If the environmental stress remains negligible for this item during tha stated operating period plus one hour, FRC concludes that the qualification review can be deferred until af tc. 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 design basis event in order to conclude that the DBE environmental stress is negligible.

4.5.2.29 Equipment Item No. 41 Differential Pressure Indicating Switch Located in the Secondary Containment Barton Model 278 *

(Licensee References 18 and 19) ,

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this item. The i Licensee notes that these sensors are used to detect a main steam line break in the steam tunnel and complete the'3 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 af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.30 Equipment Item No. 4 2 Temperature Switch Located in the Steam Tunnel Fenwall Model 17002-40 *

(Licensee Reference 18)

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

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TER-C5417-12 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 7ebruary 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.31 Equipment No. 45 Motor Operated valve Located in the NE and SE Corner Rooms Limitorque Models SMB-0-15, SMB-2-60, and SMS 2-40 (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.

4.5.2.32 Equipment No. 46 Motor Operated Valve Located in the Torus Area Limitorque Models SMB-00 0-5, SMB-3-10 0, SMB-0-10, and SMB-4T-150 (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.

4.5.2.33 Equipment No. 47 Motor Operated Valve Located in the NE and SE Corner Rooms Limitorque Models SMB-2-40, SMB-0, and SMD-1 (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.

4.5.2.34 Equipment No. 48 Motor Operated valve Located in the SE Corner Room Limitorque, Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documentation for this item. The Licensee has indicated that the required operating period is 25 seconds. If the environmental stress remains negligible for this item gg 4-28

.... Franklin Research Center s o.n,an ae v eme wsue

TER-C5417-12 during 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.

4.5.2.35 Equipment Item No. 49 Motor Operated Valve Located in the Secondary Containment Limitorque Model SMB-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.

4.5.2.36 Equipment Item No. 50 Motor Operated Valve Located in the Torus Area Limitorque Models SMB-5T-150 and SMB-2-60 (Licensee Reference 7)

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

Class 1r service outside primary Containment. 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. Existing qualification data is within a f actor of 2 of the calculated radiation dose.

i

b. 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.

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

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

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TER-C5417-12 4.5.2.37 Equipment Item No. 51 Motor Operated Valve Located in the Torus Area Limitorque Model SMB (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 40 second s. 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.

4.5.2.38 Equipment Item No. 52 Motor Operated valve Located Inside the Drywell Limitorque Models SMB-3 and SMB (Licensee Reference 18)

Licensee Reference 18 is not a qualification test report 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 conditions.

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

4.5.2.39 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; therefore, qualification documentation is deficient for this item. The Licensee makes the followina 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

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. o TER-C5417-12 thereof will be replaced with qualified components. 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 casult 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 cac of two redundant equipment trains. Also actual deses would be less than thosc 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, additio al coolant injection paths could be established, if necessary, to assure long term cooling.

4.5.2.40 Equipment Item No. 55 Level Switch IA:cated in the RHR Pump Room Magnetrol Model 249C-X-EP-SIMD4DC (Licensee References 18 and 19)

Licensee References 18 and 19 are not Q alification documents for this item. The Licensee has indicated that continuous operation is req *uired. If the environmental stress remains negligible, FRC concludes that the l qualification review can be deferred until af ter February 1,19 81 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 result of the DBE in order to conclude that the environmental stress / a to DBE is negligible.

i 4.5.2.41 Equipment Item No. 58 RHR Service Water Pump Motor Located in the RER Pump Room l General Electric Model 5K8 21167A31 l (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 l

the environmental stress remains negligible, FRC concludes that the qualification review ena be deferred until after February 1, 1981 in 1

accordance with NRC criteria presented in Section 2.2.3 of this report. It 1

should be shown that the 120*F temperature is not a result of the DBE in order l to conclude that the environmental stress due to DBE in negligible.

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TER-C5417-12 4.5.2.42 Equipment Item No. 60 Room Cooler Located in the RHR Pump Room Manufacturer and Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. T!ae Licensee has indicated that continuous operation is required. If the environmental stress remains regligible, 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.

4.5.2.43 Equipment Item No. 61 Solenoid Valve Located in the Torus Area ASCO Model HT8316B14 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification doJuments for this item. The Licensee Has indicated that the required operating period is 15 seccnds 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 qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.44 Equipment Item No. 62A Solenoid Valve Located in the Torus Area Versa VPS-2402 and VGS-4422 (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 after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

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TER-C5417-12 4.5.2.45 Equipment Item No. 63 Solenoid Valve Located in the Secondary Contair. ment Versa VPS-230 2 (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 criteria presented in Section 2.2.3 of this report.

4.5.2.46 Equipment Item No. 64 Solenoid Valve Located in the Secondary Containment ASCO Model 8302026F (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 after February 1, 1981 in accordance with NRC j

criteria presented in Section 2.2.3 of this report.

4.5.2.47 Equipment Item No. 65A i Motor Operated Valve Located in the SE Corner Room Limitorque, 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 the required operating period is 25 seconds. If the environmental stress remains negible 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 l

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

f i

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TER-C5417-12 4.5.2.48 Equipment Item No. 65B Motor Operated Valve Located in the NW Corner Room Limitorque, 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 the required operating period is 10 minutes. If the environmental stross remains negligible for this item during the stated operating period plus 1 hot:r, FRC conc 19 des 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 114' F peak temperature is not a result of the DBE in order to conclude that the environmental stress due to DBE is negligible.

4.5.2.49 Equipment Item No. 67 Position Switch Located in the Secondary Containment NAMCO Model Mark II D1200-G (Licensee References 18 and 19)

Licensee Ref grences 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 criteria presented in Section 2.2.3 of this report.

4.5.2.50 Equipment Item No. 68 Motor Operated Valve Located in the Outside Drywell Limitorque Model SMB-000 (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. If the environmenta' 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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e e TER-C5417-12 4.5.2.51 Equipment Item No. 70 Motor Operated Dampers Located in the Secondary Containment Area Limitorque Model SMB (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 perici 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.

4.5.2.52 Equipment Item No. 80 Motor-Driven Pump Located in the RHR Pump Room 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 ftem 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 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.

4.5.2.53 Equipment Item Nc. 82 l

i Room Cooler Fan Located in the HPCI Room l

Buf falo Forge Model G123-HV (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 operation period is 12 l

l 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 2.2.2 of this report. It should be shown that the 120*F l

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

l l

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TER-C5417-12 4.5.2.54 Equipment Item No. 87 Solenoid Ball Valve Located in the Secondary Containment Area General Pneumatic Model 608KW106 (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 February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.55 Equipment Item No. 88 Squib Shear Valve Located in the Secondary Containment area Pyrodyne, 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 the required operating period is 10 minutes. If the environmental stress remains' negligiole 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. The Licensee is investigating the existence of qualification data with the manufacturer.

4.5.2.56 Equipment Item No. 89 Motor Operated Valve Located in the Drywell Limitorque SMB-1-40, SMB with Peerless AC Motor (Licensee References 20 and 24)

Licensee References 20 and 24 are test reports of Limitorque valve operators. This item has been placed in its most likely category pending review of the qualification data.

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l TER-C5417-12 4.5.2.57 Equipment Item No. 91 Solenoid Valve Located in the Torus Area ASCO Model HT831614 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents fce this 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 sccordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.58 Equipment Item No. 92 Motor Operated valves Located in the Torus Area Limitorque Model SMB-000-5 with Peerless AC Motor (Licensee References 20 and 24)

Licensee References 20 and 24 are qualification type test reports for Limitorque t'alve operators. This item has been placed in its most likely category pending review of qualification data.

4.5.2.59 Equipment Item No. 93 Scienoid Valves Located in the S. ondary Containment Area ASCO Models HVA-90-405-2A, HVA-96-082A, 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 qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.60 Equipment Item No. 94 Level Switches Located in the Secondary Containment Area 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

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. o TER-C5417-12 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 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. 95 Position Switches Located in the Torus 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 regligible 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 deferred until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.62 Equipment Item No. 96 Solenoid valves Located Outside the Drywell ASCO, 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 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 1,19 81 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.63 Equipment Item No. 97 Solenoid valve Located in the Cutside Crywell ASCO Model SN-681055 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this item. The Licensee hes 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

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TER-C5417-12

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

4.5.2.64 Equipment Item No. 98 Pressure Switches Located in the Secondary Containment Area Barksdale Model B2T-M12SS and B2T-A12SS (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualificatier. documents for this item. The Licensee has indicated that the required operating period is 2 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 February 1,1981 in accordance with NRC criteria presenced in Section 2.2.3 of this report.

4.5.2.65 Equipment Item No. 99 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 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 qualification review can be deferred until after February 1, 1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.5.2.66 Equipment Item No. 100 Position Switches Located in the RWCU Room Manufacturer and Model Number Not 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 operating period is 5 seconds. If the environmental stress remains negligible for this item during the stated operating period p?.C 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. The Licensee is investigating the existence of qualification data with the manufacturer.

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4.5.2.67 Equipment Item No.191 Motor Operated Valves Located in the Torus Area Limitorque Model SMB-2-40 (Licensee Reference 7)

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

4.5.2.68 Equipment Item No.102 Differential Pressure Indicating Switches Located in the Secondary Containment 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 2 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.

4.5.2.69 Equipment Item No. 103 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 operating period is 10 minutes. 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 order to conclude that the DBE environmental stress is negligible.

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TER-C5417-12 4.5.2.70 Equipment Item No. 104 Solenoid valves Located in the Reactor Building Versa /Barksdale Model VPS-2402 and VGS-4422DlH-A15055 (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 minute s. 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 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.

4.5.2.71 Equipment Item No.108 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 nct 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 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. 109A 480 V Motor Control Center Located in the Secondary Containment Area General Electric Model 7700 (Licensee References 18 and 19) i 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 l 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 l .ed21s 4-41

....' Franklin Research Center ww e. n a ie.uno.

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TER-C5417-12 temperature is not a result of the DBE in order to sanclude that the DBE environmental stress is negligible.

4.5.2.73 Equipment Item No.114 4 kV Non-segregrated Bus Located in the Turbine Building 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 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 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.

4.5.2.74 Equipment Item No. 122 Motor Operated Valves Located in the Steam Tunnel Limitorque, Model SMB-00 with Peerless DC Motor (Licensee Reference 18) i . 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 during the stated I

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

4.5.2.75 Equipment Item No. 123 Position Switches Incated in the NW Corner Room NAMCO Model Mark III D1200G (Licensee References 18 and 19)

Licenseee References 18 and 19 are not qualification test reports; therefore, qualifiction documentation is deficient for this item. The Licensee has indicated that the required operating period is less than 1 4 -h 4-42

.... Franklin Research Center a die at n. n nw.a eru.

TER-C5417-12 minute. If the environter.tal 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 tatt the qualification review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented.in See: ion 2.2.3 of this report.

4.5.2.76 Equipment Item No.124 i Differential Pressure Indicating Switches Located in the NW Corner Room Barton Model 288 (Licensee References 18,19, and 26) 1 Licensee Reference 26 is a test report. 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 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 114*F peak temperature is not a result of the DBE in order to conclude that the DBE environmental stress is negligible.

4.5.2.77 Equipment Item No. 128 Pressure Switches Located in the NW Corner Rocm Barksdale Model B2T-Al2SS (Licensee References 15,19, and 28)

Licensee Reference 28 is a test report. Licensee References 18 and 19 are not qualification documents for this it'm. 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 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.

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. o TER-C5417-12 4.5.2.78 Equipment Item No. 129 Position Switch Located in the RWCU Rooms NAMCO Model Mark II D1200G (Licensee References 18 and 19)

Licensee References 3 and 25 are not qualificaticn documents for this item. The Licensee has indicated that the required operating period is less than 5 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 NBC criteria presented in Section 2.2.3 of this report.

4.5.2.79 Equipment Item No. 134 Solenoid Valve Located in the tM Corner Room ASCO Mcdel 830281F (Licensee Peferences 18 and 19)

Licensee References 18 and 19 are not qualificatiens 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 February 1,1981 in accordance with NRC 1riteria 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.

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• TER-C5417-12 4.6 NRC Category V EQUIPMENT WHICH IS UNQUALIFIED The DOR Guidelines require that complete and auditable records reflecting a comprehensive qualification methodology and program be referenced and made available for review of all Class lE equipment.

The qualification of the following equipment items has been judged to be deficient or inadequate, based upon our review of the documentation provided by the Licensee. The extent to which the equipment items fail to satisfy the criteria of the DOR Guidelines can be categorized as follows: (i) documen-tation reflecting qualification as specified in DOR Guidelines has not been made available for review, (ii) documentation reflecting qualification has been made available for review and is totally inadequate, or (iii) the documentation indicates that the equipment item has not successfully passed required tests. The following equipment items are therefore considered unqualified.

4.6.1 Equipment Item No. 1 .

Temperature Elements Located in the RWCU Room Shnufacturer and Model Number Not Stated (Licensee References 18 and 19)

) Licensee References 18 and 19 are not qualification test reports; ,

therefore, qualification documanterion is deficient for this item. The Licensee notes that, where these temperature switches are used for leak j

detection in the RWCU room, conditions are normally non-harsh. Immediately following a leak, the temperature will increase. As soon as the leak occurs, j the switches will function, initiating system isolation within 1 minute.

4.6.2 Equipment Item No. 2 l Motor-Driven Pumps Located in the NW Corner Room General Electric Models 5K6338XC23A and SK6336xC193 .

(Licensee References 18 and 19) l

' Licensee References 13 and 19 are not test reports; therefore, l qualification documentation is deficient for this item. The Licensee makes the following statements and commitments:

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I TER-C5 417-12 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. Although qualifica-tion 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 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 long-term cooling.

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

Licensee References 18 and 19 are qualification test reports; 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 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 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 long-term cooling.

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TER-C5417-12 4.6.4 Equipment Item No.13 Motor Operted valve Located in the Drywell Limitorque Model SMB-1 (Licensee Reference 7)

Licensee Reference 7 is a qualification test report for Limitorque valve actuator. We note that the test, radiation dose is less than the postulated DBE radiation dose. The Licensee makes the following statements a.d commitments:

The equipment will be replaced with qualified equipment. Although qualification dats is not available, continued station operation is justified 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 harsh 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 SMD-1 (Licensee References 18 and 19)

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

4.6.6 Equipment Item No. 23 Temperature Switch Located in the HPCI Room Cnited Electric Controls Model 88B (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. The Licensee states that these temperature switches detect a HFCI steam line break and, in the event of a leak, these switches will function and isolate the HPCI steam line. The Licensee concludes that, since the temperature associated with this event is within the range of routine e 4-47

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y TER-C5417-12 calibration, additional qualification data is not required. This is not a satisf actory argument since the switches will be exposed to the same temperatures as the sensing element portions of the switch.

4.6.7 Equipment Item No. 37 Solenoid valve Located Inside Drywell Allied Controls-Gould Model 320X-39 and 320X-30 (Licensee Reference 18)

Licensee ' rence 18 is not a 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. 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 period 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 No. 38 Relief Valve and Solenoid Valve Located Inside the Drywell Dresser Industries Electromatic Type 1525VX and C5450-5 (Licensee References 18 and 15)

Licensee Reference 15 is a test report which does not adequately address operating time and aging. The Licensee makes the following statement:

The number of actuations which this component was subjected to during the test is considerably larger than the number of actuations during 12 days following the accident. Therefore, this component is considered qualified for the required operating time.

FRC does not concur with the Licensee's argument. The long 12-day period in a hostile environment can cause equipment degradations whether or not it.is operated.

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. o TER-C5417-12 4.6.9 Equipment Item No. 40B Motor Operated Valve Located in the Scea7 Tunnel Limitorque Model SMB-00 with Peerless DC Motor (Licenste References 18 and 19)

Licensee Reference 18 and 19 are not 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. Existing qualification data is within a factor of 2 of the calculated radiation dose.

b. 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 ,these calculated using such conservative assumptions.

.c. Other equipment similar in design to this equipment has successfull/

been qualified for environments in excess of the calculated requirement for this equipment.

4.6.10 Equipment Item No. 43 Pressure Switch Located in the SE Corner Room Static-O-Ring Model 12NN-KK215-VX (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, continute 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. During this 4 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

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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. 44 Position Switch Located Inside the Drywell NAMCO Model EA-08011100 (No Licensee reference cited)

No qualification reference has been cited for this item. The Licensee makes the following statements and commitments:

This switch was in accessible for inspection. The manufacturer and model number will be established during the next outage permitting entry to the drywell. If the component is not qualified, a replacement part with qualification data will be purchased and installed during the first outage after received on site.

4.6.12 Equipment Item No. 56 Differential Pressure Indicating Gwitch Located in the NE and SE Corner Rooms Barton Model 289 (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:

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 redundant systems beyond those needed for coolant injection. This would result in radiation exposures to only one of two redundant equipment tra in s . 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 long term cooling.

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. e TER-C5417-12 4.6.13 Equipment Item No. 59 Differential Pressure Switch Located in the NE Corner Room 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 statements and commitments:

This equipment will be replaced with qualified equipment. Although qualification data is not available, continued station operation is j 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. 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 long term cooling.

4.6.14 Equipment Item No. 62B 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:

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

i i a. 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.

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

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

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TER-C5417-12 4.6.15 Equipment Item No. 69 Electric Air Heater Located in the Secondary Containment E. L. Wiegland, 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 statements and commitments.

This equipment will be replaced with qualified ecuipment. 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 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.

4.6.16 Equipment Item No. 71 Exhaust Fan Located in the Secondary Contaiment Area New York Blower Model E4966 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; I

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:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic releas 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 beycnd 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.

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. o TER-C5417-12 4.6.17 Equipment Item No. 72 Flow Transmitter Located in the Secondary Containment Area Leeds & Northrup Model 1912-3-21-0-0000-0300-0300 (Licensee References 18 and 19)

Licensee References la 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:

Radiation doses were calculated using conservative, non-mechanistic models. Mechanistic releas models would result in radiation releases which occur several hours after the postulated accident. During ttis 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 redu

• ant system could be activated.

4.6.18 Equipment Item No. 73 Flow Transmitter Located in the Secondary Containment Area Foxboro Model 15A-1 (Licensee References 18 and 19)

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

l 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:

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

needed for coolant injection. This vould result in radiation exposures to only one of two redundant e'.s Lem ent trains. Also actual doses would be less than those calculate' 99~av pach conservative assumptions.

Finally, should the opera. r e- lpment suffer degradation due to radiation exposure, the e p . redundant system could be activated.

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TER-C5417-12 4.6.19 Equipment Item No. 74 Flor Switch Located in the Secondary Containment Area Mercoid Models DA-533-3 and DA-5332R1 (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 stataments 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:

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 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.

4.6.20 Equipment Item No. 75 Temperature Switch Located in the Secondary Containment Chromalex, Model Not Stated (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test repcrts; 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:

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 dcwn redundant systems beyond those needed for coolant injection. This would result in radiaiton 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.

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TER-C5417-12 4.6.21 Equipment Item No. 76 Local Control Panels Located in cne Secondary Containment Area Harlo, Model DWG D12971SH30 (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 states that this equipment is subjected to harsh radiation only, and will be reevaluated and/or shielded to reduce the radiation exposure to a non-harsh level. Although qualification data is not availaole, continued station operation is justified for the following reasons:

R'diation a doses were calculated using conservative, non-mechanistic models. Mechanistic release models would result in radiation releases that 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 exposare, the shut down redundant system could be activated.

4.6.22 Equipment Item No. 77 Solenoid Valve Lccated in the Secondary Containment Area Versa /ASCO Model VNS-23028320A23 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification test reports; therefore, qualification documentation is deficient for this iten. 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 fcr the following reason:

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

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TER-C5417-12 4.6.23 Equipment Item No. 78 Temperature Element Located Inside the Torus Area Pall Trinity Micro 14-T-2H (Licensee Reference 19)

Licensee Reference 19 is not a qualification test report; 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:

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 calcu, lated using such conservative assumptions.

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

4.6.24 Equipment Item No. 81 Fan Motors Located in the NE and NW Corner Rooms General Electric Models 5K213AK2476 and SK184AL2191 (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 ststements 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:

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

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O e TER-C5417-12 During the time available after stabilization of core cooling, additional coolant injection paths could be established, if necessary, to assure long-term cooling.

4.6.25 Equipment Item No. 90 Motor Operated Valve Located in the RWCU Rcom Limitorque Model SMB with Peerless DC Motor (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:

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

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

c. These components undergo per iodic functional testing to verify operability this testing wculd identify age related degradation.

4.6.26 Equipment Item No. 109B 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 Licensee 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 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 those calculated using such conservative assumptions.

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TER-CS417-12

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

4.6.27 Equipment Item No. 121 Motor Operated Valve Located Inside the Drywell Limitorque Models SMB-2 and SMB-000 (Licensee reference not cited, No qualification references have been cited for this item. The Licensee is looking for additional vendor information to resolve outstanding environmental qualification items.

4.6.28 Equipment Item No. 135 Electrical Penetration of the Drywell GE-NEBS, Model Not Stated (Licensee reference not cited)

No qualification references have been cited 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 conditions.

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

l 4.6.29 Equipment Item No.141 Terminal Blocks Located in the Drywell Wall l Allen Bradley, Model Not Stated j (Licensee reference not cited)

No qualification references have been cited 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 l qualification data is not available, continued station operation is justified for the following reasons:

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TER-C5417-12

, a. These components or similar items have been partially tested for environmental conditions.

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

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TER-C5417-12 4.7 NRC Category VI EQUIPMENT FOR WHICH QUALIFICATION IS DEFERRED This section normallf includes equipment items which have been addressed by the Licensee in the eg aipment environmental qualification schmission; however, the qualification review of this equipment has been deferred by the NRC in accordance with criteria presented in Sections 2.2.3 and 2.2.5 of this report.

4.7.1 Equipment Item No. 20 Differential Pressure Indicating Switch Located in the HPCI Room 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 operatin; 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 with NRC criteria presented in Section ? ,2.3 of this report.

4.7.2 Equipment Item No. 25 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 item. The Licensee has indicated that the required operating period is 12 l

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 with NRC criteria I presented in Section 2.2.3 of this report.

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1 TER-CS417-12 4.7.3 Equipment Item No. 66 Pressure Switch Located in the Secondary Containment Area Static-O-Ring Model 12N-AAS-PP (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 environmencal 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.

4.7.4 Equipment Item No. 79 Damper Located in the Control Rooms No Manufacturer and Model 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.

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 with NRC criteria

_ presented in Section 2.2.3 of this report.

4.7.5 Equipment Item No. 85A Level Switch Located in Diesel Rooms 1/2 Magnetrol Model A-10 3F-EP/VP (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 af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

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TER-C5417-12 4.7.6 Equipment Item No. 110 120 V AC Reactor Protection Bus Located in the Electrical Equipment Room General Electzic Type NAB, Style 2A, Plant H (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.

Since the environmental stress remains negligible for this item, 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.

4.7.7 Equipment Item Do. 111 120/240 V AC Bus Located in the Electrical Equipment Room Cutler Hammer Model 6CF65505 (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this

. item. The Licensee has indicated that continuous operation 1s required.

Since the environmental stress remains negligible for this item, FRC concludes that the qualification review can be deferred until after February 1, 198I in accordance with NRC criteria presented in Section 2.2.3 of this report.

4.7.8 Equipment Item No. 112 120/240 V AC Bus FUK3 Set Located in the Electrical Equipment Room General Electric Model SL54404A22T30 (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.

Since the environmental stress remains negligible for this item, 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.

f-h- 4 -f *'

.... Franklin Research Center 4 > a on n re.coom m.ume.

- - ~ --- . -

TER-C5417-12 4.7.9 Equipment Item No. 126 Supply Air Fan Located in the, Control Room Trane Co. Model SO No. KALF575A (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.

Since the environmental stress remains negligible for 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.

4.7.10 Equipment Item No. 127 Return Air Fan Located in the Control Room Joy Mfg. Model 38-21-1750 (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.

Since the environmental stress remains negligible.for 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.

4.7.11 Equipment Item No.130 Solenoid Valves Located in the Control Room

! Manufacturer and Model Not Stated I (Licensee References 18 and 19) l i

Licensee References 18 and 19 are net qualification documents for this item. The Licensee has indicated that ceintinuous operation is required.

l l Since the environmental stress remains neoligible for this item, FRC concludes l

hat the qualification review can be def erred until af ter February 1,1981 in accordance with NRC criteria presented in Section 2.2.3 of this report.

l

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l l

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TER-C5417-12 4.7.12 Equipment Item No.136 Water Chillers Located in the Control Room Trane Cc. Model 3E5H80 (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.

Since 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.

4.7.13 Equipment Item No. 137 Chilled Water Pump Located in the Control Room Ingersoll-Rand Model 0469-4154 (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. .

Sin'e c the environmental stress i: mains negligible, FRC c'oncludes 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.

4.7.14 Equipment Item uo. 83 Fan Motors Located in Diesel Room 1 Manufacturer and Model Not Stated (Liccr.s ne References 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.

Since the enviroamental 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.

Zh 4-64

.... Franklin Research Center 4 :>m a om. r,.r.a in w.

TER-C5417-12 4.7.15 Equipment Item No. 84 Motor-Driven Pump Located in Diesel Room 1 General Electric Model 5Kl82BL315 (Licensee References 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.

Since the environmental stress remains negligible for this item during the stated cperating period, FRC concludes that the qualification resiew can te deferred until after February 1, 1981 in accordance with NRC criteria pres - ^ ad in Section 2.2.3 of this report.

4.7.16 Equipment Item No. 85B Level Switches Located in Diesel Rooms 1 and 1/2 Magnetrol Model A-10 3F-EP/VF (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification dacu'ta.ts for this item. The Licensee has indicated that the required operating period is 30 days. If the environmental stress remains negligible for this item duri*ng the stated operating period 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.

4.7.17 Equipment Item No. 66 Solenoid Valve Located in Diesel Room 1 ASCO Model 8211"89 (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 af ter February 1,1981 in accordance with _4RC criteria presented in Section 2.2.3 of this report.

f-2-. 4-65

...; Fra,idin Research Center 4 Ci*. in of Be France .asatwo

TER-C5417-12 4.7.18 Equipment Item No. 105 Diesel Auxiliary Control Located in Diesel Room 1 Ideal Electric and Manufacturing Model SO No. 267777 (Licensee References 18 and 19)

Licensea References 18 and 19 are not qualification documents for this item. The Licensee has indicated that the required operating period is 30 days. Since the environmental stress remains negligible for this item during the stated operating peri (J 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.

4.7.19 Equipment Item No. 106 Excitation Cabinets Located in Diesel Room 1 .

Electromotive Div. of GM Model 9474 (Licensee References 18 and 19)

Licensee References 18 and 13 are not qualification documents for this .

. rem. The Licensee has indicated that the required' operating period is 30 i

days. Since 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.

4.7.20 Equipment Item No. 107 Diesel Generators Located in Diesel Rooms 1 and 1/2 Electromotive Div. of GM, 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 the required operating period is 30 days. Since 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.

Mh 4-66

.... Frank!in Research Center s .,an c enye neue

TER-C5417-12 4.7.21 Equipment Item No.113 Engine Control Panel Located in Diesel Room 1 Electromotive Div. of GM, 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 the required operation period is 30 days. If the environmental stress r mains negligible for thi- 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.

4.7.22 Equipment Item No. 115 D/G Secondary Control Panel Located in Diesel Room 1 Ideal Electric S.O. No. 267777 (Licensee References 18 and 19)

Licensee References 18 and 19 are net qualification documents for this item. The Licensee,has indicated that the required operation period is 30 days. Since the environmental stress remains negligible for this item 'during the stated operating period, FRC corcludes that the qualification review can be deferred until af ter February 1,1981 in accordance with NRC criteria presented ir. Section 2.2.3 of this report.

4.7.23 Equipment Item No.116 j D/G Neutral Grounding Panel Located l in Diesel Room 1 General Electric Model 208419-68P (Licensee References 18 and 19) j Licensee References 18 and 19 are not qualification documents for this l item. The Licensee has indicated that the required oceration period is 30 f

l 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 2, 1981 in accordance with NRC criteria

! presented in Section 2.2.3 of this report.

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TER-C5 417-12 4.7.24 Equipment Item No. 117 Batt?ry Chargers Located in the Battery Charger Room Gould Models GRF240T100X, GRF1200T100X, and GRF24S25F30X (Licensee References 18 and 19)

Licensee References 18 and 19 are not qualification documents for this i tem. The Licensee has indicated that continuous operation is required. If the enviror.xental stress remains negligible for this item, 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.

4.7.25 Equipment Item No. 118 250 V DC Motor Control Center Located in the Battery Charger Room Cutler Hammer Model 6002H347B (Licensee References 18,19, and 25)

Licensee Reference 25 is a test report for Class,lE de motor control.

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

The Licensee has indicated that continuous operation is required. Since the environmental stress rem'a ins negligible for 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.

4.7.26 Equipment Item No. 119 Batteries Located in the Battery l

Charger Room Gould Models FPS-25, F?R-13, and DPR-9

! (Licensee References 18 and 19)

I Licensee References 18 and 19 are not qualification documents for this item. The Licensee has indicated that continuous operation is required.

Since the environmental stress remains negligible for this item, FRC concludes that the qualification review can be deferred until af ter February 1,1981 in i accordance with NRC criteria presented in Section 2.2.3 of this report.

1. e 4-68

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=cwoa o n.=nterm.-

TER-C5417-12 4.7.27 Equipment Item No. 120 DC Distribution Panel Located in the Battery Charger Room Cutler Hammer. Model Not Stated (Licens2e 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.

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.

1. _2 4-69

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TER-C5417-4004.12

5. CONCLUSIONS 3

Our review of the qualification documentation and other information submitted by Commonwealth Edison Company for these equipment items and their applications in the Quad Cities 1 plant has resulted in the following categories:

NRC- Compliance With The DOR Quantity Of Categorg Guideline Requirements Equipment Items I

I.a Equipment Fully Satisfies 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 0 II.b Equipment Fully Satisfies All -

Applicable Requirements Provided That 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 Satisfactory for Less Than Plant Life Based on Total EEQ Program Review 0 III Equipment is Exempt from Qualification 0 IV.a Equipment has Qualification Testing Seneduled 12 l

l IV,b Equipment has High Likelihood l of Operability; However, Proper Qualification Documentation is Not Available 79 V Equipment is Unqualified 29 VI Qualification is Deferred 27 l

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

TER-C5417-4004.12 In general, the major deficiencies that have been identified are shown in the summary review sheets at the end of the section.

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

The Equipment Environmental Qualification Summary Forms that are presented on the following pages show 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 with respect to compliance with a Guideline requirement. Deficiencies result in equipment items categorized as unqualified or qualification not established.

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

O= NRC Qualification Category.

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

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... Franklin % search Cer.ter a-2 4 cm.ca em r .a #.w.

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FRC TASK AE C CA PLANT NAME  ? AGE N!! Franklin Research Center M' N ##U # I NNebIMD5Y PROJECT UTILITY i

EQUIPMENT ENVIRCNMENTAL 02G C. 9 . (O M O W I M EDIS W OUALIFICATION  !'

OCCKET N,RC_ TAC OATE/ENGIN EER IEB-7H18 So.25V 4347$ l/7 54S

SUMMARY

REVIEW EQUIPMENTITEM NUMBER , j I l 2 l3nl38l 4l 5 l 6 l 7 l t l 9 l sollt l12.lI3 lI4ltsl14l tTl17l ty, GUICELINE REQUIREMENTS, (DESIGNAT;ONS: X - DEFICIENCY, L - LIMITING CONCITION)

EVIDENCE OF OUALlFICATION lX!Xl l Ml l ll lNl l Nl X l/ l !XlN lX l N l X ! N RELATIONSHIP TO TEST SPEC: MEN l l El l NIX lXl l l  ! l l l l l l l l AGING CEGRADATION EVALUATED l l l l l l ll l l l l  ! !l l l l CU ALIFIED LIFE ESTABL!SHED l l I l l I I l I l  !  !  ! I I  !  ! l l I PRCGRAM TO ICENTIFY AGING l l l l l l l l l l l l l l l l l l l l CUAL. FOR STEAM EXPOSURE l l l l l l l l l l l l l l l l l l l l PEAK TEMPERATURE ACECUATE l l l l l l l l l l l l IXl l l l l PEAK PRESSURE ACECUATE- l l l l l l l l l l l l l l l l l l l TESTCURATICN ACECUATE l l l l l  ! l l l l l l l l l l l l l l PECulRED PROFILE ENVELOPED l l l l  ! l l l l l l 1 l lXl l l l l l CU AL. FOR SU EMERGENCE l 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 CUAL. FOR PACIATION l l l l l l lXl lXl l l lXl l l l l l i EETA RACIAT!CN CONSIDERED l l l l l l l l l l l l l l l l l l l l TEST SEQU ENCE l i l l l l l l l l l l l l l l l l l l l

TEST CURATION (1 HOUR - FUNCTION) l l l l l l l l l l l l l l l l l l l l -

CUANTITY CF ECU PMENT l 7 l 4 l Z l 1 l 2 l 6 l'2. l 2 l1 l '2l 4 l / l ) l / l l l } l / l "J l 5 ! 4 ECUIPMENTINSPECTED AT SITE l l l l l l l l l l l l l l l l l l l i CU ALIFiCATION CATEGORY, ' O - CATEGORY CESIGNATiON ll A. CU AL. FCP PLANT LIFE l l l l l ll l l l l l l l l l l l ll-8. CU A L. SY JUCGEMENT l l l l l l l l l l l  : l l l l l l l li.A. CU AL. .:CR < PLANT LIFE l l l l l l l l l l l l I l l l l l I l Il 8. CU AL. PENCING MCClFICATION l l l l l l l l l l l l l  ! l l l l l l I

lIl-C. CU AL. < PLANT LIFE /.:RC REVIEWl l l l  ! l l l l l l l l l l l l l l Ill. EXEMPT FROM 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 l0lO10l l l 1 l  ! l l l  !

llV-8. CUAL. NCT ESTA BLISHED l l l0l0ld!OIOl l l l lCl0l l-l0ldlOlC jOl V. ECUIP. NOT CU ALI.:!ED l0 Ol l l l l l I l l 0l l l0lCl l l l l lVI.CUAL. !S CE: ERRED l l l l l l l l l l l l l l l l i lFEPLACEMENT SCHEDULE l l l l l l l l l lRl Rl l l l l l 1 I i

A FRC TASK AEACTOR PLANT N AME PAGEl Tib Fmnklin Research Center b#% 3Wi ' OVdG C/7'f5 3 A Chison of The Franidin insatute UTIUTY ,

EQUIPMENT ENVIRONMENTAL 02GQ 7-q g,gg,3fgggjg7g g),g,g QUAURCATICN DCCKET NRC TAC DATE/ ENGINEER IEB-79-018 $p-159 kd7i I/7 5 /t 5

SUMMARY

REVIEW EQUIPMENTITEM NUMBER 20l 2/ l22 l13 l24l 25l2/,l27 l 2fl29 l 70l 31 l3 2l7Jl 34 3sl 34l37l 3 rl37!

GUIDELIN E REQUIREMENTS, (DESIGNATIONS: X- DEFIC:ENCY L-LIMITING CCNDITION) i EVIDENCE OF QU AllFICATION X!XlX l lX X!XlXlXIX. Xl lXlXlXlXl 1 .

RELATIONSHIP TO TEST SPECIMEN l l l l l l l l l l l l l l l l 1 AGING DEGRADATION EVALUATED l l l l ll l l l lIl l l lMl CU ALIFIED LIFE ESTABLISHED l l l l l l l l l l lNI l l l lXI I PRCGRAM TO IDENTIFY AGING l l l l l l l l l l l l lN! l l l lXl CUAL. FOR STEAM EXPOSURE l l l l l l l l l l l l l l l l l l l PEAK TEMPERATURE ADEQUATE l l l l l l l l l l l l l l l l l l PEAK PRESSURE ADECUATE l l l l l l l l l l l l l~l l l l l l TEST DURATICN ADEOUATE l l l lXl l l l l l l l l l l l l lX ! !

REQUIRED PROFILE ENVELOPED l l l l l l l l l l l l l' l l l l IXl CU AL. FOR SU BM ERGENCE -1 l l l l l l l l l l l l l l l l l l !

l CU'AL. FCR CHEMICAL SPRAY l l l l l  !  ! l l l l l l l l l l l l l CU AL. FCR RADIATION l l l l l l l l l l l l l l l l l l l l6 EETA RADfAT!CN CONSIDERED l l l I l l l l l l l l l l l l l I I TEST SECU ENCE l l l l l l l l l l l l l l l l l l l TEST DURATICN (1 HOUR - FUNCTION) l l l l l l l l l l l l l l l l l l l l lCUANTITY OF EQUIPMENT 2 l I lI lldlI lM l / l I lI ll l2l I lI l Nl)ll l1l 7l8lI EQUIPMENTINSPECTED ATSITE l l l l l l l l l l l l l l l l l l l l I CUAL!FICATION CATEGORY. ' O - CATEGORY DESIGN ATION l-A. CU AL. FOR PLANT LIFE l l l l l ll l l l l l l l l l l l-B. CUAL. SY JUCGEMENT l l l l l

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

{ ll-A. CU AL. FOR < PLANT LIFE l l l l l l l l l l l l l l l l l l l l 11-8. CU AL. PENDING MCDIFICATION 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 LIFE / FRC REV!EW l l l l l l l l l l l l l  ! l l l l l l

!!!. EXEMPT FRCM CUAL. l l l l l l l l l l l l l l l l l l l  !

IV- A. Q U A L. TEST SCH EDU LE l l l l l l l l l l l l l l l l l l  ! l llV-3. CU AL. NCT ESTABLISHED l lOlCl !Ol lClC!OlOldlCldlClCldlCl l lC-lV. ECUIP. NCT O '.LIFIED l l ldl l i l l l l l l l l l l lClCl i lVI. CUAL. lS CEFERRED 0 l } l0l l l l l l l l l l R EPLACEMENT SCHEDULE l l l l l l l l l l l l l l TRl l l l

A FRC TASK AE CTCR PLANT NAME PAGE iddij Franklin Research Center N' " # #NI'I #

A Onnson of The Franklin Inscrute PROJECT UTILITY EQUIPMENT ENVIRONMENTAL 02G G P , gagmppe,,gjf,7g g 3,gog CUALIFICATiON COCKET N RC, TAC CATE/ ENGl_N E,ER IEB-M-018 S'd .2 5 y MV7T 1h S /t S

SUMMARY

REVIEW EQUIPME_NT ITEM NUMBER 49l98l4A l42l43l44lV5l4/e!47l4fl49l50lS/ l52.l53l5'f jGrl54 lf 7l57 GUIDELINE RECUlREMENTS, (CESIGNATIONS: X - DEFICIENCY, L - LIMITING CCNCITiON)

EV10ENCE CF CUALIFICATICN XlXll(lXl)(lXl l l lXl IX l XlXlXlM IX lM IX RELATIONSHIP TO TEST SPECIM EN l l l l lXlXlXl lXlXl l ll l l l l AGING DEGRADATION EVALUATED l l l l l l l l l l l l l ll l l  !  !

OU ALIFIED LIFE ESTABLISHED l l l l l l l l l l l l l l l l l l l PRCGRAM TO IDENTIFY AGING l l l l l l l l l l l l l l l l l l l l CUAL. FCR STEAM EXPCSURE l l l l l l l l l l l l l l  !  ! l l l l PEAK TEMPERATURE ADECUATE l l l l l l l l l l l  ! l l l l l l l I PEAK PRESSURE ADECUATE I l l l  ! l l l l l l l l l l l l l l l TEST DURATICN ACECUATE l l l l l l l l l l l l l l l l l l l l RECUlRED PROFILE ENVELCPED l l l l l l ll l l l l l l l l l l l l lCU AL. FOR SU BMERGENCE l,  ! l l l l l l l l l l l l l l l l l l CU'AL. FCR CHEMICAL SPQAY l l l l l l l l l l l l l l l l l l  !

CUAL. FOR RACIATION l l l l l l l l l l l l l l l l l l  !

EETA RADIATION CONSIDERED l l l l  ! l l l l l l l l l l l l  !

TESTSECUENCE l l l l l l l l l l l l l l l l l l l TEST CURATION (1 HOUR - FUNCTION) l l l l l l  ! l l l l l l l l l l l l CUANTITY OF EQUIPMENT l 3 l I ll8lldl1l 3 l T l 3 l6 l l l2 l 4l t 12.l4I 6 I 3l 2.! ? W EQUIPMENTINSPECTED AT SITE l l l l l l l l l l l l l l l l l l l l CUALIF!CATICN CATEGORY. ' O - CATEGORY CESIGN ATICN 1-A. QUAL. FCR PLANT LIFE l l l l l l l l l l l l l l l l l

!-8. CU AL. BY JUCG EM ENT l l l l l l l l l l l l l l l l l l l l Il-A. CU AL. FOR < PLANT L!FE l l l l l l l l l l l l l l l l l l l l lIl-B. CUAL. PEN CING MCDIFICATlCN l l l l l l l l l l l l l l l l l l l l II-C. QU AL. DLANT LIFE / FRC HEVIEW l l l l l l l l l l l l l l l l l l l l Ill. EXEMPT FROM CU AL. l l l l l I I l l l l l l l l l l l I i llV- A. CU A L. TEST SCH EDU LE l  ! l l l I l l l l l l l l I lCI l lCI IV-B. CU AL. NOT ESTABLISHED lC l l0l0l l l4l0l0loidlojolojol lCl l !O IV. ECUIP. NOT CU ALIFTEC l0l l l0lo1 l l l l l l l l l l lo! I VI. CU AL. lS CEFERRED 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 l l l l l 1

+ - ._ _ _. .

A FRC TASK AEA CR PLANT N AME PAGE dNO Franklin Research Center 8

3wti- a ao es vist / 4

^,, Dpm n of The Franxjin Insttute PROJECT UTILITY f EQUIPMENT ENVIRONMENTAL 02G G N dam M*.f# E D/58#

CUALIFICATICN CCCKET NRC TAC DATE/ ENGINEER 1E9-401 B 50-25'( 42U g l/ 7 545 ~ .

SUMMARY

REVIEW EQUIPMENTITEM NUM8ER STl 6oj f tlf2M&2d 4 3l4V4f4l458l I 44l67 l 4fl 69l 70l 7/ l71l73l74l75l74 GUIDELINE REQUIREMENTS, (DESIGNATIONS: X - DEFICIENCY, L- LIMITING CCNDITION)

EVICENCE OF CU ALIFICATION XlXlXlXIXlXlXIXlXl IXI X l X I XI)(l X l Xl X l X la RELATIONSHIP TO TEST SPECIMEN l l l l l l l l l l l l l l l l l l l AGING CEGRADATION EVALUATED l l l l l l ll l l l l l l l l l l l l CUAL!FIED LIFE ESTA BLISHED l l l I l l l l Il l l l l l l I l l PPCGRAM To lOENTIFY AGING '

l l l l l l l l l l l l l l l l l l l ICUAL. FOR STEAM EXPOSURE l l l l l l l l l l l  ! l l l l l l l PEAK TEMPERATURE ACECUATE l l l l l  ! l l I l l l l l l l l l PEAK PRESSURE ACECUATE l l l l l l l l l l l l l l l l l l l TEST DURATION ADEQUATE l l l l l l l l l l l l l l l l l l l l RECUIRED PROFILE ENVELOFED l l l l l l  ! l -l l l l l l l l l l I lCUAL. FCR SU BMERGENCE l l l l l }  ! l l l l l l l l l l l l CU'AL. FOR CHEMICAL SP AAY I l l l l l l l l l l l l l l l l l )

CU AL. FOR PAC!ATION l l l l l l  ! l l l l l l l l l l l l EETA RACIATICN CCNSICERED I l l l l l l l l l l l l l I l l  !

TEST S ECU ENCE l l l l  ! l l l l l l l l l l l l l

TEST CURATICN (1 HCUR - FUNCTICN) l l l l l l l l l l l l l l l l l l l CUANTITY OF ECUIPMENT 1l 4 l7 l 4 l 2l l l 7l / l l ll6l fl 1 l 2.l 8l2l 2 l2,l'fl 2 l2 4 ECUIPMENTINSPECTED AT SITE I l l l l l l l l l l l l l l l l l l QUALIFICATION CATEGORY, ' O - CATEGORY DESIGNATICN l-A. CU AL. FOR FLANT LIFE l l l l l l l l l l l l l l l l l l l l

l-8. CUAL. SY JU CGEMENT l l l l l l l l l l l l l l l } l l l l It-A. CUAL. FCR < PLANT LIFE l l l l l l l l l l l l l l  ! l l l l l Il-E. CUAL. PENCING MCCIFICATICN l l l  ! l l l l l l l l l l l l l l l l li-C. QU AL. < ?LANT LIFE / RC REVIEW l l l l l l l l l l l l l l l l l l l l

!!!. EXEMPT FRCM OU AL. l  ! l, l l l l l l l l l l l l l l l l IV-A. C U AL. TEST SCM ECU LE l i i l l l l l l l l l l } l l l l l l IV-8. CU AL. NOT ESTA EL!SHED l0l0l0l l0l0l0l0l lOldl l0l l l l l l i

lV. ECUIP. NOT CU ALIF!ED oL l l {0} l l l l l l l0l l0lCl0ldl0lC*

VI. CU AL. lS CEFERPED l l l l l Ol l l l l l l l l l PE?'.ACEMENT SCHEDULE lR '

l  ! lR l l l l l l 1( j l R l ((l/l j /( ljl l t

A FRC TASK AEACTpA p PLANT NAME PAGE b0 Franklin Research Center b 3N' OW G8N l '

A Diwszon of The Frankin Institute PROJECT UTILITY EQUIPf/ENT ENVIRONMENTAL 02G Q 17 4 c e fac h t(ALT # (D/SO N CUALIFICATION COCKET NRC TAC DATE/ ENGINEER lEB-79-01 B So- 2, S1[ 9[;j l [7 SAS

SUMMARY

REVIEW EQUIPMENTITEM NUMBER 77 l 77 l19 l 70l $1 l 72 l73 l 7'/ !9fM T58l T4l 77 l 9 fl 39 l 90 l 9 / l 92 l 93 GUIDE!JN E RECUIREMENTS, (DESIGNATIONS: X - DEFIC lENCY, L - LIMITING CONDITiCN)

EVICENCE OF QUALIFICATION l[lNl l% l[ l Nl l lK l lXlXl l)(l N l l IXlM RELATICNSHIP TO TEST SPECIMEN l l l l l l ll l l l l l lXl l lXl l l AGlNG CEGRACATION EVALUATED l l l l l l l l l l l l l l l l l l l CUAUFIED LIFE ESTABLISHED l l l l I l l l l l l l l l l l l l  !

PRCGRAM TO IDENTIFY AGING l l l l l l l l l l l l l l l l l l l CUAL. FC A STEAM EXPCSURE l l l l I l I l l l l l l l I l i I PEAK TEMPERATURE ACECUATE l l l l l l l l l l l l I  !  !  ! I l l

~

PEAK PAESSURE ACEQUATE l I l l l l l l l l l l l l l l l l l  !

TEST DURATION ADEQUATE l l l l l l l l l  ! !l l l l l l l l I REQUIRED PROFILE ENVELCPED , l l l l l l l l l l l l l l l l l l l l CU AL. FCR SUEMERGENCE l l l l l l l l l l l l l l ll l l l I CU'AL. FOR CHEMICAL SPRAY l l l l l  !  ! l l l l l l l l l l l l l CU AL. FOR RACIATION l l l l l l l l l l l l l l l  ! l l l l EETA RACI ATION CCNSIDERED l l l l l l l l l l l l l l l l l l l l TEST SECU ENCE l l l l l l l l l l l l l l l l l l l l TEST SURAT:CN (1 HCUR + FUNCTION) l l l l l l l l l l l l l l l l l l l l CU ANTITY OF ECUIPMENT l 7. l 9 l 3 l '2.l 9 ! I l 2-l Z l I l 2.l 2 lS l 5 l 2. l l l 4 l Z lldl 4 P EQUIPMENT!NSP CTED AT SITE l l l l l l l l l l l l l l l l l l l l l CU ALIFICATICN CATEGORY, ' O - CATEGORY DESIGNATION I-A. CUAL. FCR PLANT LIFE l l l l l l l l l l l l l l l l I-8. CU AL. SY JU CGEMENT l l l l l l l l l l l l l l l l l l j ll-A. CU AL. .:OR < PLANT L!FE l l l l l l l l l l l l l l l l l l l  !

11-8. CU AL. PENCING MOCIFICATiCN l l l l l l l l l l l l l l l l l l l l

.II-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 l lil. EXEMPT FRCM CU AL. l l l l l l l l I l l l l l l l l l l l

,lV-A. CU AL. TEST SCH ECULE l I l l l l l l l l l l l  !  !  ! l l l  !

IV-B. CU A L. N OT ESTA BLISH ED l l l lC, lCl l lCl l l0lOl0l l0lO1 lo!c' V. ECUIP. NCT CU ALiF!ED C .C l ldl l l l l l l l l l0l l l l l '

VI. CU AL. !S CE: ERRED l l0 l l lClCl ldl0l l l l l lCl l PEPLACEM ENT SCh ECULE lAl l l l((l l l l l l l l l l l l l l l ,

FRC TASK RE CTCR PLANT NAME PAGE Al) 000 FranMn Research Center b' N C W D C' 7' ' S '

• NOO2IMDEY PROJECT UTILITY EQUIPMENT ENVIRON MENTAL 02G Q N com,mayg gopp CUALIFICATION DOCKET DATE/ ENGI,N EER N RC_ TAC IES-79418 3/7 fo.2$4 i+ 2973 545

SUMMARY

REVIEW EQUIPMENTITEM NUMBER 96 l 17l1T hf licolisill* 21 to?tio4l te5llosl se7l/ofliosliofelss o lis ilis z li/ Jl/s y GUIDELIN E REQUIREMENTS, (CESIGNATIONS: X - DEFICIENCY. L - LIMITING CONDITION)

EVIDENCE CF CUALIFICATION l .4 - Xl5 N [l XlXlXl l l/lXlXl l l

. RELATIONSHIP TO TEST SPECIMEN l lX l l l 1 l l l l l l l AGING DEGRADATICN EVALUATED l l l l l l l l l l l l l CUALIFIED LIFE ESTABLISHED l l l l l l l l l l l l l l l PROGRAM TOICENTIFY AGING l l l l l l l  ! l l l l l l l l CUAL. FOR STEAM EXPOSURE _

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

TEST CURATION ADECUATE l l l l l l l l l l l l l l l l l l  !

REQUIRED PRCFILE ENVELOPED  :

l l l l l l l l l l l l l l l l l l l l CU AL. FCR SU BM ERGENCE l l l l l l l l l l l l l l l l l l OU'AL. FOR CHEMICAL SP9AY I l l l l l l l l l l l l l l l l

CU AL. FOR RADIATION l l l l l l !l l l l l l  ! l l EETA RADIAT;ON CONSIDERED l I l l l I 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 TEST DURATICN (1 HOUR - FUNCTICN) l l l l l l l l l l l l l l l l l l l l CU ANTITY OF ECulPMENT lJlJlsOlIllJl1l11l2l4 2 l 2, l 2 4 l 3 l 7 l2 l 2,l / l 2. l J j ECUIPMENTINSPECTED AT SITE l l l l l l l l l l l l l l l l l l l l CUALIFICATlON CATEGORY ' O -CATEGORY DESIGNATION 1-A. CUAL. 8CR PLANT L!FE l l l l l l l l l l l l l l l l-G. CU AL. SY JU CGEMENT l l l l l l l l l l l l l l l l l l l l

!I-A. CUAL. FOR < PLANT LIFE l l l l l l l l l l l l l l l l l l l l

!!-8. CU AL. PENDING MCDiFICATICN l l l l l l l l l l l l l l l l l li!-C. CUAL. < PLANT LIFE /FRC REVIEW l l l l l l l l  ! l l l l l l l l l lIll. EXEMPT FROM CUAL. l l l l l l l l l l l l l l l l l l l l IV A. CUAL. TEST SCHEDULE l l l l l l l l l l l l l l l l l l l l IV E.CUAL. NOT ESTABLISHED lOl0l0lOl0ldlC Ol0l l l lCl0l l l l l lC.

V. ECUIP. NOT CU ALIFIED l l l l l l l l l l l0l l l l l O OlOl lO OlOlOl VI. CU AL. lS DEFERRED l l l l REFLACEMEN T SCHEDULE  ! l l l l l l l l l l l ,

l

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

A FRC TASK AEACTCR PLANT NAME PAGE I b Franklin Research Center b 3 bk - GUAD clTits J 7 !

A Divmon of The Frsndo insetute PROJECT UTILITY EQUIPMENT ENVIRONMENTAL 02X5@ cong,qm asM CUALIFICATION CCCKET N RC, TAC DATE/ENGIN EER 1EB-79-018 go. 2S y 9-2.4 7 T i/7 SAS  !

SUMMARY

REVIEW EQUIPMENTITEM NUMBER l 115 llf 6 lff 7lll1ll19l# E8lstil122ht3ll29ll25llL4 l127l11TDZ9b3*IIJil132l173!!hl GUIDELINE REQUIREMENTS. (DESIGNATIONS: X - CEFICIENCY, L - LIMITING CONDITION) l EVIDENCE OF CUALIFICATION l l l l l l XlX l[l l l l lM XIM lX l$!

RELATIONSHIP TO TEST SPECIMEN l l l l l l l l l l l l l l l l l l l AGING OEGRADATION EVALUATED l l l l l l l l l l l l lXl l l l l ll lCUALIFIED L!FE ESTABLISHED l l l l l l l l l l l l l l l l l l l PRCGRAM TO IDENTIFY AGING l l l l l l !l Il  !

CUAL. FOR STEAM EXPOSURE l l l l l l l l l l l l l l l l l l l l1 PEAK TEMPERATURE ACECUATE l l l l l 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 l l l l l I l l I !

TEST CURATION ACECUATE l l l l l l l I l l l l l lM I l l  ! I  ! !

REQUIRED PROFILE ENVELOPED l l l l l l l l l l l l l l l  ! l l  ! I CUAL. FCR SU B' MERGENCE l  ! l l l l l I l l l l l l l l l l l lJ CU'AL. FOR CHEMICAL SPRAY  ! l l l l l l l l l l  ! l l l l l l l I CUAL. FCR RADIATION l l l l l l l l l l l l l l l l l l l i l l l l l I l !

SETA RACIATICN CONSCRED l l l l l l l l l l l TESTSECUENCE l l l l l_ l l l l l l l l l l l l lj l TEST OURAT!CN D HOUR - FUNCTION) l l l l  ! l l l l l l l l l l l l l l !

CU ANTITY CF ECUIPMENT l 1l 2 l 6 l 4 l 4 l $ l 6 l l l 3 l 2 l16l t l 1 l4l J l J lXl)( } )tl 4!

EQUIPMENT!NSPECTED AT SITE l I l l l l l l l l l l l l l l l l l l !

CUALIFICATION CATEGCRY, ' O - CATEGORY DESIGN ATION .

I A.CUAL. FOR PLANT LIFE l l l l l l lC l l l l l l l l l l-8. QU AL. EY JU CGEMENT l l l l l l l l l l l l l l l l l l ,

li-A. CU AL. FCR < FLANT LIFE l  ! l l l l l l l l l l l l l l l l l l !

ILS. CU AL. FENCING MCCIFICATICN l l l l l l l l l l l l l l l l l l l l I il-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 Ill. EXEMPT FRCM CU AL. l l l l l l l l l l l l l l l l l l l1 IV- A. CU AL. TEST SCHECULE  !  ! l l l l l l l l 'l l l' l l l  ! Ol CIC !

IV-8. CU AL. NOT ESTA BLISHED I l l l fl l l0lOlOl l l lOl0l l l l lCl V. ECUIP. NOT CU AL!FIED I l l l l l0l l l l l l l l l l l l l l VI. CU AL. IS DEFERRED 0 0 0l0lCl0l l l Ol0l l l0l l l l l REPLACEMENT SCHECULE l l l l l l l l l l l l l l l l l

g FRC TASK AEA CR PLANT NAME PAG 5 d,.lm Ld Franklin Research Center 04. I2. gwg* Qvno cITIis I S (DO/3MM5Y PROJECT UTILIW EQUIPMENT ENVIRCNMENTAL M#MN IU QUALIFICATION DCCKET NRC TAC DATE! ENGINEER

IEB-79-018 5'o - 158t #ITH I/7 545

SUMMARY

REVIEW EQUIPMENTITEM NUMBER 135l736l137lr3f/Ilrygl 3fllWiltjl l l l l l l l l l l l GUIDELINE REQUIREMENTS. (DESIGNATIONS: X - DEFIC lENCY, L - LIMITING CONDITION)

EVIDENCE CF OUALIFICATION )X,l l l XlX l X lXlX, l l l l l l l l l l l RELATIONSHIP TO TEST SPECIM EN l l l l l l l l l l l l l l l l l AGING DEGRADATION EVALUATED l l l l l ll l l l l l l l l l l QUALIFIED LIFE ESTA BLISHED l l l l l l l l l l l l Il l l l l PRCGRAM TO IDENTIFY AGING L l l l l l l l l l l l l l l l l l l QUAL. FOR STEAM EXPCSURE I l l l l l l l l l l l l l l l l l l PEAK TEMPERATURE ADEQUATE l I l l l l l l l l l l l l l l l l l l PEAK PRESSURE ADECUATE l l l l l l l l l l l l l l l l l l  ! l TEST DURATION ADECUATE l l l l l l l l l l l l l l l l l l l l REQUIRED PROFILE ENVELOPED l l l l l l l l l l .l l. l l l l l l  ! l CUAL. FOR SU BMERGENCE l l l l l- l l l l l l l l l l l l l l lCU AL. FOR CHEMICAL SP AAY l l l l l l l l l l l l l l l l l l CUAL. FOR RADIATION l l l l l l l l l l l l l l l l l  ! l t SETA RADIATION CONSIDERED l l l l l l  !  ! l l l l l l l l l l  !

TEST SEQU ENCE l l l l l l l l l l l l l l l l l l l TEST OURATION (1 HCUR + FUNCTION) l l l l l l l l l l l l l l l l l l CUANTITY OF ECUIPMENT X l l l I l)(l XlX lX lX l l l l l l l l l l EQUIPMENT INSPECTED T SITE l l l l l l l l l l l l l l l l l l l

CUALIFICATION CATEGCRY, ' O - CATEGORY DESIGNATICN l

1-A. CUAL. FCR PLANT LIFE l l l l l l l l l l l l l l l l I-3. CU AL. SY JUDGEME{ l l l l l l l l l l l l l l l l l l l II-A. CU AL. FOR < PLAN FE l l l l l l l l l l l l l l l l l l l  !

!!-8. QU AL. PENDING MODIFICATION 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 LIFE /FRC REVIEW l l l  ! l l l l l l l l l l l l l l l l l Ill. 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. C UAL. TEST SCH E DU LE l l l l0l0l0lCl l l } l l l l l l l i j lV-8. CU AL. NOT ESTA BLISH ED l l l l l l l l l l l l l l l l l l l l lV. ECUIP. NOT CUALIFIED lCl l l l l lCl l l l l l l l l l l l l lVI. CUAL. !S OEFERRED O LO l l l l l l l l l l l l l l

RE?LACEMENT SCHECULE l l l l l l lR i l l l l l l l l l

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TER-C5417-12

6. REFERENCES QUALIFICATION REFERENCES

1. PSAR Section 10.10

2. Bechtel Radiation Study

3. FSAR Table 8.2.3

4. FSAR Figures 5.2.15 and 5.2.16

5. FSAR Section 6.2.3.2

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

! 7. Limitorque 600461-P0003 Qualification Test Report I 3. Limitorque 600426-BC0J9 l

9. F-C2232-01

10. F-C3441

11. DV-l*5C3006 Qualification Design verification

12. FSAR Section 6.2.7.2

13. FSAR Table 5.2.1

14. FSAR Section 6.2.4.2.2

15. PEP e42963 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 Valve Motor Operators

21. G.E. Tast Report No. 145C3006, Qualification Design Verification File

22. G.E. Test Report No. DV-1453008 Qualification Design verification File

23. G.L. Test Report No. 1 9C4361, ard Wy.e Test Report No. 43235-1

24. Report No. 338164-FC-2485-01 Tests of Limitorque valve operator

25. Report No. F-C3781 Franklin Institute Fasearch Laboratories

26. G.E. Test Report No. DV-145C3009, Qualification Design Verification File ITT 3arton Rep.

27. G.E. Test Report No. DV-145C3004, Qualification Design verification File ITT

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28. G.E. Test Report No. DV-145C3010, Qualification Design verification and AETL Report 596-0398

29. Letter from G. Lainas, NRC, to A. Schwencer, NRC. Subjects 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. Seyfrit, R. H. Engelken, NRC. Subjects IE Supplement No. 2 to Bulletin 79-01B, Environmental Qualification of Class lE Equipment, dated September 29, 1980.

31. Letter from Normal C. Mosely, NRC, to B. H. Grier, J. P. O'Reilly, J. G. Keppler, K. V. Seyfrit, R. H. Engelken, NRC.

Subject:

IE Supplement No. 3 to Bulletin 79-01B, Envitanmental 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 filed with the NRC on November 4, 1977.

33. Commor. wealth Edison response to NRC IE Bulletin 79-01B Environmental Qualification of Class lE Equipment for Quad Cities 1 and 2, dated November 1, 1980.

34. NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-related Electrical Equipment," Decemoer 1979.

35. Memorardum for V. D. Thomas, NRC, through D. W. Hayes, NRC, from J.

Hughes, NRC;

Subject:

Screening Review of Licensee Responses to IE Bulletin 79-OlB and Summary of Inspections of Installed Systems at Quad Cities Unit 1 and 2 Facility -

Docket No. 50-254; dated April 14, 1980.

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..c., FrahAhn Research Center

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e s TER-C5417-12 APPENDIX A - ENVIRONhENTAL SERVICE CONDITIONS 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 I 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 !7 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 are provided for the following areas:

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

b. Standoy diesel generator room.

c. HPCI room,

d. Low-pressure coolant injections corner rooms.

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• 3 30 la 5

3 Maximum Maximum Helative hG Area Pipe fireak Preusure (psia) _

Tennpe ra ture

(*F) llumidity

(%)

Torus compartment IIPC I steam 27.0 242 100 (reyion of: postutated HCIC Steam Iine break)

, Core spray /ItCIC room IICIC s t.eam tiot evaluated - Equipment in this room not required for HCIC steam Iine break

,ceam tunnel Main steam 27.0 242 100 Feedwater ItCIC steam ItWCli heat exchanger and itWCt1 rJo t evaluated - Only two containment isolation holding pump room valves required to function. Qualification will meet conservatively assumed inside drywell conditions.

lilyh-pressure heater Main steam tiot evaluated - 130 equipment which is required hay Feedwater to lunction is located in this area. o i 9 n

Turbine building Main steam not evaluated - No equipment which is required  %'

el 615'-6" to function is located in this area. O north of Column G, e'.

. hetween Columns 9 and 11 and 15 and 16 8

Etth. :.-

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l

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in sa N

h

$3 Maximum Maximum Relative Pressure Temperature ilumidity In, Area Pipe Ilreak (psia) (*F) (1) c

-R T

Ite ac t o r feed pump Feedwater flot evaluated - rio eqtilpirierit which is required room to function is located in this room.

Turbine building Feedwater flot evaluated - flo equipment which is required el 595'-0" to function is located in this area.

area south of linit I s- Inunp room and north

& of IInit 2 pump room Iliesel generator room Feedwater flo t evaluated - Qualification for the environ-ment due to a postulated feedwater 1ine break is not required since three diesels are available to provide emergency ac power.

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Table A-3 4 4

, ltADI ATIOri I:llVillOriMEllTAl. COr3DITIOriS OllTSIDE

?y][

g I/ DilYWEl.I. POI.I.OWillG Tile l'OSTill.ATED I.OCA EU; MAXIMUM ltADI ATIOff SOllitCES sa R,, -

j$ Integrated Dose I,evels (rads) 29 A__r_e_a_ _ Source

• 1 Day 30 Days 1 Year

,g 7 7 7

[*j

, Torus S t> 1.5x10 3.2x10 3.9x10 5 5 6 itesidual heat removal corner rooms S I' 2.4x10 9.4x10 1.7x10

• 6 Ill>C I room MS 6.6x10 1.6x10 1.7x10 6

Core sl> ray /ItCIC rooms MS 6.6x10 1.6x10 1.7x10

> 5 5 6 L steam tunnel MS 3.1x10 8.5x10 1.6x10 6 6 iteactor tusilding el 595'-0" Itw 2.5x10 7.8x10 1.4x10 6 6 Iteact or liullding el 623'-0" LA 6.8x10 1.6x10 1.6x10 5 6 6 lteact or liullding el 647'-6" CA 6.8x10 1.6x10 1.6x10 6 6 Iteact or l>uilding el 666'-6" C.A 6.8x10 1.6x10 1.6x10 1

• H I' = Silliress ioni [xiol liquid itW = Iteact.or wa ter MS = lteactor steam a CA = Coit ta i nmen t airliorne M A

C b

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o D 4

TT. 25417-12 APPENDIX B - EQUIPMENT ITEM TABLE This appendix contains the list of safety-related electrical items for the Quad Cities Nuclear Generating Station Unit 1 provided by the Licensee in its November 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.

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TER-C5417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION DESCRIPTION LOCATION REFERENCES REFERHNCE3 NO.

1 Temperature Element RWCU 1-6 18,19 No Manufacturer Room or Model No.

2 Motor-Driven Pump NW 7-9 18,19 General Electric Corner 190-193 5K6338XC23A Room 5K6336xC133 Motor Operated Valve NW and SW 10-12 18,19,20 3

Limitorque/ Peerless AC Corner 483 A SMB-0-25 Rooms B: SMB Motor Operated Valve Secondary 13-14 18,19,20 4

Limitorque/ Peerless AC Containment SMB-0-15 Motor operated valve Secondary 15-18, 7 5

Limitorque/ Reliance AC Containment 142-143 SMB-2-40 6 !otor Operated Valve Torus 19-21 7 Limitorque/ Reliance AC Area SMB-000 22-24 19,21

7 Pressure Transnitter NW and SW General Electric Corner Rooms 4532K11001 8 Flow Transmitter NW and SW 25-27 18,19 General Electric Corner Rooms 4532K43001 NW and SW 28-30 18,19,22 9 Flow Switch Barton Corner Rooms 289 d -h-

.... Franklin Researen Center B-2

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• o TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION , REFERENCES REFERENCES 10 Pressure Switch NW and SW 31-34 18,19 Mercontrol Corner Rooms DA-7043-804 11 Stop Valve HPCI Room 35 18,19 No Manufacturer Stated 178250H02D4 12 Motor Operated Valve HPCI Room 36 18,19 Limitorque/ Peerless DC SMB-3 13 Motor Operated valve Drywell 37,38 7 Limitorque/ Reliance AC CMB-1 1 18,19

,14 Motor Operated valve Torus Area Limitorque/ Peerless DC Motor SMB-1 Motor Operated Valve HPCI Room 40 18,19 15 Limitorque/ Peerless DC Motor SMB-0 16 Motor Operated Valve Steam Tunnel 41,42 18 Limitorque/ Peerless DC SMB-3-80 17 Motor Operated Valve HPCI Room 43,44,46 18,19 i Limitorque/ Peerless DC l SMB-2 SMB-3 SMB-4 18 Motor Operated Valve HPCI Room 45,49-52 18,19 l

Limitorque/ Reliance DC SM3-0 19 Solenoid Valve HPCI Room 47-48, 53-54 18,19 ASCO 830281F 8A B-3

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TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTE PAGE QUALIFICATION NO. LOCATION REFERENCES REFERENCES DE_ SCRIPTION

' 20 Differential Pressure UPCI Room 55-56 18,19 Indicating Switch Barton 288 Plow Transmitter HPCI Room 57 18,19 21 General Electric 4532K13001 Pressure Transmitter HPCI Room 58 18,19 22 General Electric 4532K11001 23 Temperature Switch HPCI Room 59-68 18,19 United Electric Controls 88B HPCI Room 69 18,19,21 24 Pressure Transmitter General Electric 50-551032CAAY1 70-72 18,19 25 Pressure Switch Secondary Barksdale Containment B2T-Al2SS 1

HPCI Room 73 18,19 26 Turbine Gland Seal Condensate Drain Pump General Electric 58225A3525 HPCI Room 75 18,19 27 Gland Steam Exhauster Fan General Electric

~

5BC74AB2193 Motor Speed Changer HPCI Room 75 18,19 28 General Electric GE5BC26AC339 HPCI Room 76 18,19 4 .29 Motor Gear Unit General Electric SCD14019Alll620 W-B-- B-4 2... Frank!in Research Center a c. a e n. r,.w.w. -

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TER-C5417-12 i

Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 30 Oil Pump Motor HPCI Room 77-78 18,19 General Electric SCD218E252 SCD326E758 HPCI Motor Control HPCI Room 79 18,19 31 Signal Converter General Electric 357513TC108 Level Switch HPCI Room 80 18,19 32 Mercoid 123-2 33 Level Switch HPCI Room 81-86 13,19,23 Magnetrol 291-SP

~

HPCI Room 87 18,19 34 Flow Switch Barton 289 HPCI Room 88 18,19 35 Pressure Switch Static-O-Ring 6NN-AA21-VRR HPCI Room 89-90 18,19

{ 36 Pressure Swicch Barksdale D2H-M150SS 91-96 18 37 Solenoid Valve Inside Allied Controls-Gould Drywell 320X-39, 320X-30 97-102 15,18 38 Relief Valve and Inside Solenoid valve Drywell i Dresser Industries 1525VX C5450-5 103-104 20,24 39 Motor Operated Valve Inside Limitorque/ Peerless AC Drywell Model Not Stated A --h B-5

../. FranrJin Research Center sonume nerv ewaue i

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TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT

, ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES _

40 Motor Operated valve Steam 159-160 18 Limitorque/ Peerless DC Tunnel 105-106 A SMB-00-7.5 B: SMB-00 41 Differential Secondary 107-116 18,19 Pressure Indicating Containment Switch Barton 278 42 Temperature Switch Steam 117-126 18 Fenwall Tunnel 17002-40 SE Corner 235-237 18,19 43 Pressure Switch Static-O-Ring Room 12NN-KK215-VX ,

Inside 388-389 None given 44 Position Switch NAMCO Drywell EA-08011100 Motor Operated Valve NE and SE 127-134 18,19,20 4 45 Limitorque/ Peerless AC Corner Rooms SMB-0-15 SMB-2-60 SMB-2-40 Motor Operated Valve Torus Area 135-136, 18,19,20 46 Limitorque/ Peerless AC 147-148, SMB-000-5 152-155 SMB-4T-150 SMB-3-100 SMB-0-10 Motor Operated. Valve NE and SE 194-197 7,18,19 47 Limitorque/ Reliance AC Corner Rooms 137-138 SMB-2-40 SMB-0 SMB-1 1

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TER-CS417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 48 Motor Operated Valve SE Corner 139 18,19 Limitorque/ Peerless AC Room No Model No.

49 Motor Operated Valve Secondary 140-141 18,19,20 Limitorque/ Peerless AC Containment SMB-0-15 50 Motor Operated Valve Torus Area 144-146, 7 Limitorque/ Reliance AC 149-151 SMB-5T-150 SMB-2-60 Motor Operated Valve Torus Area 156 18,19 51 Limitorque/ Peerless DC SMB 52 Motor Operated valve Inside 161-162, 18 Limitorque/ Reliance'AC 157-158 SMB-3 SMB 53 Pressure Trsnsmitter NE and SE 163-165, 18,19 General Electric Corner Rooms 186-139 GE/MAC 551 54 Flow Transmitter NE and SE 166-170 18,19 General Electric Corner Rooms GE/MAC 553 55 Level Switch RHR 171-173 18,19

~ Magnetrol Pump Room

)

249C-X-EP-SIMD4DC 56 Differential Pressure NE and SE 174-176 18,19 Indicating Switch Corner Rooms l

Barton j

289 57 Pressure Switch NE and SE 177-182 18,19 Mercoid Corner Rooms GN-L-3 i 8-$h B-7

.... Franklin Research Center 4 ce n r r ra mue

TER-C5417-12 Quad Cities Unit 1 EQUIPMFNT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 58 RHR Service Water RHR 183-185 18,19 Pump Pump Room General Electric SK821167A31 59 Differential Pressure NE 198-200 18,19 Switch Corner Room Barton No Model No.

60 Room Cooler RHR 201-203 18,19 No Manufacturer Pump Room or Model No.

61 Solenoid valve Torus Area 205-206,208, 18,19 214-215,216,226 ASCO HT8316B14 207,209-213, 18,19 62A Solenoid Valve Torus Area Versa VPS-2402 VGS-4422 62B Solenoid Valve Torus Area 218-220 18,19 versa VPS-2502 VGS-4522 VGS-4422 Solenoid Valve Secondary 217 18,19 63 Versa Containment VPS-2302 64 Solenoid Valve Secondary 221-225 18,19 ASCO Containment 8302026F Motor Operated valve SE 204 18,19 65A-Limitorque Corner Room No Model No.

Motor Operated Valve  :."4 490 18,19 65B Limitorque. Corner Room No Model No.

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... 5nklin Research Center 3-8

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TER-C5417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIFTION LOCATION REFERENCES REFERENCES 66 Pressure Switches Secondary 247-250, 18,19 Static-O-Rino Containment 228-234 12N-AAS-PP 67 Position Switch Secondary 238-242 18,19 NAMCO Containment Mark II D1200-G 68 Motor Operated valve Outside 227 18,19 Limitorque Drywell SMS-000 69 Electric Air Heater Secondary 251-253 18,19 E. L. Wiegland Containment No Model No.

Motor Operated Damper Secondary 254-259, 18,19 70 Limitorque Containment 263-264 SMB 71 Exhaust Fan Secondary 260-262 18,19 New York Blower Containment E4966 Secondary 265-267 18,19 72 Flow Transmitter Leeds & Northrup Containment 1912-3-21-0-0000-0300-0300 Secondary 268-270 18,19 73 Flow Transmitter Foxboro Containment 15A-1 Secondary 277-279 18,19 74 Flow Switch Mercoid Containment 271-273 DA-533-3 UA-533-2R1 Secondary 274-276 18,19 75 Temperature Switch Chromalox Containment No Model No.

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TER-C5417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATICN NO. DESCRIPTION LOCATION REFERE!CES REFEPE!CES 76 Local Control Panel Secondary 280-282 18,19 Harlo Containment DW D12971 SH.30 77 Solenoid valve Secondary 283-285 18,19 Versa /ASCO Containment VWS-2302/

8320A23 78 Temperature Element Inside Torus 243-246 19 Pall Trinity Micro 14-T-2H 79 Damper Control Room 398-400 18,19 No Manufacturer or Model No. .

80 Motor Driven Pump RHR 286-287 18,19 General Electric Pump Room SK365AK169 81 Fan Motor NE and NW 288-290,292-294 18,19 General Electric Corner Rooms SK213AK2476 5Kl8AL2151 82 Room Cooler Fan HPCI Room 291 18,19 Buffalo Forge G123-HV 83- Fan Motor Diesel 295-296 18,19 No Manufacturer Room 1 No model No.

84 Motor-Driven Pump Diesel 297-298 18,19 General Electric Room 1 5K182BL315 Diesel Room 299 18,19 85A Level Switch Magnetrol 1/2 A-103F-EP/VP

.... Franklin Research Center S-10 a c~ a ce 3. Frua 6.au.

TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 85B Level Switch Diesel Room 302-303 18,19 Magnetrol 1 and 1/2 A-103F-EP/VP 86 Solenoid valve Diesel 300-302 18,19 ASCO Room 1 8211C89 87 Solenoid Ball Valve Secondary 304-307 18,19 General Pneumatic Containment 608KW106 88 Squib Shear Valve Secondary 308-311 18,19 Pyrodyne Containment No Model No.

Motor Operated Valve Inside 312-313, 20,24 89 Limitorque/ Peerless AC Drywell 464-465 SMB-1-40 SMB Motor Operated Valve RWCU Room 314-315 18,19 90 Limitorque/ Peerless DC SMB 316-319 18,19 91 Solenoid Valve Torus Area ASCO HT831614 Motor Operated valve Torus Area 322-324 20,24 92 Limitorque<eee51ess AC SMB-000-5 Secondary 331-334,338-341, 18,19 93 Solenoid Valve ASCO Containment 345-346 HVA-90-405-2A WPBLX831636 HVA-96-082A HVA-96-081A Secondary 335-337 18,19 94 Level Switch Magnetrol Containment 402 Ah 3-11

.... Franklin Research Center s onuw a ne r s un awwe

- _ . - - - , . - - - ,___ _ __ .-.c - , _ - -

TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT ITEM I E,M SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 95 Position Switches Torus Area 325-328 18,19 NAMCO Mark II D1200G 96 Solenoid Valve Outside 320 18,19 ASCO Drywell No Model No.

97 Solenoid Valve Outside 321 18,19 ASCO Drywell SN-681055 l

98 Pressure Switch Secondary 347-351,365-367, 18,19 Barksdale Containment 369,370 B2T-M12SS B2T-A12SS 99 Level Indicating Secondary 352-364 18,19 Switch Containment Yarway 4418C 4418CE 100 Position Switch RWCU Room 368 18,19 No manufacturer or Model No.

101 Motor Operated Valve Torus Area 329-330 7 Limitorque/ Reliance SMB-2-40 102 Differential Pressure Secondary 371-378 18,19 Indicating Switch Containment Barton 288 103 Radiation Element Turbine 391-392 18,19 GM Tube Building General Electric DWG 194X927GI 104 Solenoid Valve Reactor 393-395 18,19 Versa /Barksdale Building VPS2402 VGS4422/D1H-A150SS A-h- B-12

...e Franklin Research Center

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. o TER-C5417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 105 Diesel Auxiliary Diesel 404-406 18,19 Control Room 1 Ideal Electric &

Manufacturing SO No. 267777 106 Excitation Cabinet Diesel "

407-409 18,19 Electromotive Div. Room 1 of GM 9474 107 Diesel Generator Diesel Rooms 410-412 18,19 Electromotive Div. 1 and 1/2 of GM No Model No.

108 Switchgear Secondary 413-416 18,19 General Electric Containment AMH 4.76-230 AKD-5 109A 480 V Secondary 417-419 18,19 Motor Control Center Containment General Electric 7700 109B 480 V Secondary 436-441 18,19 Motor Control Center Containment General Electric 7700 110 120 V AC Reactor Electrical 420-421 18,19 Protection Bus Equipment General Electric Room Type NA3, Style 2A Plant H 111 120/240 V AC Bus Electrical 422-423 18,19 Cutler Hammer Equipment 6CF55505 Room dh S~13

..;. Franklin Research Center 4 we. s 3. r e .. ,n.umi.

TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES Electrical 424 18,19 112 120/240 V AC Bus MMG Set Equipment General Electric Room SL54404A22T30 113 Engine Control Panel Diesel 425-427 18,19 Electromotive Div. of GM Room 1 No Model No.

114 4 kV Non-segregated turbine 428-429 18,19 Bus Building No Manufacturer or Model No.

115 D/G Secondary Diesel 430-432 18,19 Control Panel . Room 1 Ideal Electric .

S.O. No. 267777 Diesel 433-435 18,19 116 D/G Neutral Grounding Panel Room 1 General Electric 208419-68P Battery 442-443,449-450 18,19 117 Battery Charger Gould Charger 458-461 GRF240T100X Room GRF120T100X GRF24S25F30X Battery 444-447 18,19,25 118 250 V DC Motor Control Center Charger Cutler Hammer Room 6002H347B 119 DC Battery Battery 448,451,456-457 18,19 Gould Charger

-FPS-25 Room FPR-13 DPR-9

1. 2:. ~

... 5nklin Research Center B-14 a cean er ne vrswe e.u.

TER-C5 417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 120 DC Distributor Battery 452-455,462-463 18,19 Panel Charger Cutler Hammer Room No Model No.

121 Motor Operated valve Inside 379-387 None given Limitorque/ Reliance AC Drywell SMB-2 SMB-00J 122 Mecor Operated valve Steam 466-467 18 Limitorque/ Peerless DC Tunnel SMB-00 123 Position Switch NW Corner 342-344 18,19 NAMCO Room Mark II D1200G 124 Differential Pressure NW Corner 470-472 18,19,26 Indicating Switch Room Barton 288 125 Temperature Switch NW Corner 473-482 18,19,27 Fenwal Room 17002-40 126 Supply Air Fan Control Room 396 18,19 Trane Co.

SO No. KALF575A 127 Return Air Fan Control Room 397 18,19 Joy Afg.

38-21-1750 128 Pressure Switch NW Corner 484-487 18,19,28 Barksdale Room 32T-Al2SS 129 Position Switch RNCU Room 390 18,19 NAMCO Mark II.D1200G 2h B-la.

.... Franklin ao, e Re. search o.ne .w.Center

• O TER-C5417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFERENCES REFERENCES 130 Solenoid Valve Control Room 403 18,19 No Manufacturer or Model No.

131 Cable Not Stated 505-506 None given General Electric No Model No.

132 Cable Outside 507-514 None given Simplex Drywell No Model No.

133 Cable, Jacket Inside -503-504 None given Simplex Drywell No Model No.

134 Solenoid valve NW Corner 468-469,488-489 18,19 ASCO , Room

• .830281F 135 Electrical Drywell 517-520 None given Penetration I

GE-NEBS No Model No.

i Control Room 401 18,19 136 Water Chillers Trane Co.

3E5H80 Chilled Water Pump ConMol Room 402 18,19 137 Ingersoll-Rand 0469-4154 138A Cable Polyvinyl Outside 491-492,499-502, None given Chloride Jacket Drywell 515-516 General Electric No Model No.

138B Cable Inside 497-498 No't

• given General Electric Drywell No Model No.

f.3 3-16

.c.. Franklin Research Center 4 %. w '.. n.e mu.

F TER-C5417-12 Quad Cities Unit 1 EQUIPMENT ITEM ITEM SUBMITTAL PAGE QUALIFICATION NO. DESCRIPTION LOCATION REFEAENCES REFERENCES 139 Polyvinyl Chloride Not stated 493-494 None given Jacket Simplex No Model No.

140 Plastic Insulation and Outside 495-496 None given Jacket Drywell Simplex No Model No.

141 Terminal Blocks Drywell 521-524 None given Allen Bradley Wall No Model No. ,

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.... Frank!in Research Center B-17 1

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l TER-C5417-12 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 basic accident.

This information was submitted in response to IE Bulletin 79-OlB and was included in the Licensee's November 1, 1980 response.

i.b5nklin Resencen Center C-1 A om,e ao ne vrun muue

4 .

TER-C5417-12 o Reactor Protection System e Core Spray System o High-Pressure Coolant Injection System e Auto Depressurization Syster, .4ain Steam System o Residual Heat Removal / Containment Spray System o Pressure Suppression System e Standby Gas Treatment System e Service Water System o Diesel Oil Piping System o Containment Isolation System

• e Control Rod Drive Hydraulic System o Reactor (Nuclear Boiler) Recirculation System o Process Radiation Monitoring System o Reactor Building Ventilation System o Control Room, HVAC e Standby Alternating Current Power l

e Standby Direct Current Power e Reactor Core Isolation Cooling System (RCIC) e General Use Electrical Equipment t

l

• Containment isolation includes all ccmponents in various systems performing tb3 containment isclation function.

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TER-C5417-12 1

APPENDIX D EQUIPMENT ITEM CROSS-REFERENCE LIST i

EQUIPMENT FINAL TECHNICAL l

' ITEM NO. EVALUATION REPORT SECTION 1 4.6.1 2 4.6.2 3A 4.5.2.1 3B 4.5.2.2 4 4.5.2.3 5 4.5.2.4 6 4.5.2.5 7 4.5.1.1

' 8 4.5.1.2 9 4.5.1.3 10 4.6.3 11 4.5.2.6

! 12 4.5.2.7 13 4.6.4 .

14 . 4 . 6 . 5, i 15 4.5.2.8 16 4.5.2.9 17 4.5.2.10 18 4.5.2.11 19 4.5.2.12 >

20 4.7.1

' 21 4.5.2.13 22 4.5.2.14 23 4.6.6 24 4.5.2.15 25 4.7.2 26 4.5.2.16 27 4.5.2.17 28 4.5.2.18 29 4.5.2.19 30 4.5.2.20 31 4.5.2.21 32 4.5.2.f2 33 4.5.2.23 34 4.5.2.24 35 4.5.2.25 36 4.5.2.26

! 37 4.6.7 38 4.6.8 39 4.5.2.27

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TER-C5417-12 EQUIPHENT . FINAL TECHNICAL ITEM NO. EVALUATION REPORT SECTION 40A 4.5.2.28 40B -4.6.9 41 4.5.2.29 42 4.5.2.30 43 4.6.10 44 4.6.11 45 4.5.2.31 46 4.5.2.32 47 4.5.2.33

-48 4.5.2.34 49 4.5.2.35 50 4.5.2.36 51 4.5.2.37 52 4.5.2.38 53 4.5.2.39 54 4.5.1.4 55 4.5.2.40 56 4.6.12 s 57 4.5.1.5 58 4.5.2.41 59 4.6.13 60 4.5.2.42 61 4.5.2.43 .

62A 4.5.2.44 62B 4.6.14 63 4.5.2.45 64 4.5.2.46 65A 4.5.2.47 65B 4.5.2.48 66 4.7.3 67 4.5.2.49 68 4.5.2.50 69 4.6.15 70 4.5.2.51 71 4.6.16 72 4.6.17 73 4.6.18 74 4.6.19 '

75 4.6.20 76 4.6.21 77 4.6.22 78 4.6.23 79 4.7.4 80 4.5.2.52 81 4.6.24 82 4.5.2.53

1. D-2

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. e TER-C5417-12 EQUIPMENT FINAL TECHNICAL ITEM NO. EVALUATION REPORT SECTION 83 4.7.14 84 4.7.15 85A 4.7.5 BSB 4.7.16 86 4.7.17 87 4.5.2.54 88 4.5.2.55

89. 4.5.2.56 90 4.6.25 91 4.5.2.57 92 4.5.2.58 93 4.5.2.59 94 4.5.2.60 95 4.5.2.61 96 4.5.2.62 97 4.5.2.63 98 4.5.2.64 99 4.5.2.65 100 4 . 5.2.66 101 4.5.2.67 -

102 4.5.2.68 103 4.5.2.69 104 4.5.2.70 105 4.7.18 106 4.7.19 107 4.7.20 108 4.5.2.71 109A 4.5.2.72 109B 4.6.26 110 4.7.6 111 4.7.7 112 4.7.8 113 4.7.21 L

114 4.5.2.73 115 4.7.22 116 4.7.23 117 4.7.24 118 4.7.25 119 4.7.26 120 4.7.27 121 4.6.27 122 4.5.2.74 123 4.5.2.75 124 4.5.2.76 125 4.2.1.1 126 4.7.9

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I TER-C5417-12 EQUIPMENT FINAL TECHNICAL i ITEM NO. EVALUATION REPORT SECTION 127 4.7.10 128 4.5.2.77 129 4.5.2.78

-130 4.7.11 131 4.5.1.6 132 4.5.1.7 133 4.5.1.8 134 4.5.2.79 135 4.6.28 13 6 4.7.12 137 4.7.13 138A 4.5.1.9 138B 4.5.1.10 139 4.5.1.11 140 4.5.1.12 141 4.6.29 l

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.... Frank'in Research Center .

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