ML20079G503

Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60), Technical Evaluation Rept

ML20079G503
Person / Time
Site:	Robinson
Issue date:	07/08/1982
From:	Crane C FRANKLIN INSTITUTE
To:	Le N, Shemanski P NRC
Shared Package
ML14190A687	List: ML20079G503
References
CON-NRC-03-79-118, CON-NRC-3-79-118 TAC-42466, TER-C5257-511, NUDOCS 8207130575
Download: ML20079G503 (401)

Text

{{#Wiki_filter:Please Send Copy of XA to PDR TECHNICAL EVALUATION REPORT REVIEW OF LICENSEES' RESOLUTION OF OUTSTANDING ISSUES FROM NRC EQUIPMENT ENVIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (F-11 and B-60) CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON UNIT 2 NRC DOCKET NO. 50-261 FRC PROJECT C5257 N RC TAC NO. 42466 FRC ASSIGNMENT 13 NRC CONTR ACT NO. NRC-03-79-118 FRC TASK 511 Prepared by Franklin Research Center 20th and Race Streets Philadelphia, PA 19103 FRC Group Leader: C. J. Crane Prepared for Nuclear Regulatory Commission

Washington, D.C. 20555 Lead NRC Engineer

N. B. Le P. Shemanski i

July 8, 1982 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or impiled, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. l Please Send Copy of XA to PDR g 8dCdX3658] l M wh l S. Franklin Research Center l A Division of The Franklin institute The Bengtrun Franahn Parkway. Phela . Pa 19103(215)448 100o

l TECHNICAL EVALUATION REPORT l REVIEW OF LICENSEES' RESOLUTION OF OUTSTANDING ISSUES FROM NRC EQUIPMENT ENVIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (F-11 and B-60) CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON UNIT 2 N RC DOCKCT NO. 50-261 FRC PROJECT C5257 l NRC TAC NO. 42466 FRC ASSIGNMENT 13 NRC CONTRACT NO. NRC-03-79-118 FRC TASK 511 Prepared by Franklin Research Center 20th and Race Streets Philadelphia, PA 19103 FRC Group Leader: C. J. Crane Prepared for Nuclear Regulatory Commission j Washington, D.C. 20555 Lead NRC Engineer: N. B. Le P. Shemanski July 8, 1982 This report was prepared as an account of work sponsored by an agency of the United States l Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not Infringe privately owned rights. 1 Reviewed by: Approved by: 00 k (A L hroup Leader a r 4-45epartrnent reeg A

                                                .1 Franklin Research Center A Division of The Franklin Institute The Bengrrun Frankhn Parkway. Phda Pa 19103 (215)448 1000

TER-C5257-511 CONTENTS Section Title P_ age 1 . INTRODUCTION . . . . . . . . . . . . . 1-1 1.1 Purpose of the Evaluation . . . . . . . . 1-1 1.2 Scope of the Evaluation . . . . . . . . . 1-1 1.3 Generic Issue Background. . . . . . . . . 1-2 1.4 Specific Issue Background . . . . . . . . 1-10 2 NRC CRITERIA FOR ENVIRONMENTAL QUALIFICATION . . . . . 2-1 2.1 Criteria Provided by the NRC. . . . . . . . 2-1 2.2 Staff Positions and Supplemental Criteria . . . . 2-1 2.2.1 Requirements and Applicable Criteria . . . . 2-1 2.2.2 Application of Requirements and Criteria to TMI Lessons Learned Implementation Equipment . . . 2-3 2.2.3 Equipment Not in the Scope of the Qualification Review . . . . . . . . . . . 2-4 2.2.4 Clarification of Qualification Requirements . . 2-5 2.2.5 Additional Clarification of Qualification Requirements . . . . . . . . . . 2-8 3 METHODOLOGY USED FOR THE EVALUATION . . . . . . . 3-1 3.1 Introduction. . . . . . . . . . . . 3-1 3.2 Methodology . . . . . . . . . . . . 3-2 3.3 NRC Qualification Categories and Definitions. . . . 3-8 3.4 Implementation Guide for Fulfilling NRC Criteria. . . 3-12 4 TECHNICAL EVALUATION . . . . . . . . . . . 4-1 4.1 Introduction. . . . . . . . . . . . 4-1 4.2 Sununary of the Evaluation . . . . . . . . 4-2 4.3 Methodology Used by the Licensee. . . . . . . 4-10 4.3.1 Completeness of Safety-Related Equipment List. . 4-10 4.3.2 Environmental Service Conditions . . . . . 4-11 4.3.3 Submergence . . . . . . . . . . 4-16 4.3.4 Chemical Spray . . . . . . . . . 4-18 4.3.5 Aging . . . . . . . . . . 4-18 4.4 Equipment Environmental Qualification Evaluation. . . 4-20 iii nklin Research Center A DMoon of The Franhan inseewe

l 1 i TER-C5257-511 I CONTENTS (Cont.) Section Title Pg , l 5 CONCLUSIONS . . . . -. . . . . . . . . 5-1 ; 6 REFERENCCS . . . . . . . . . . . . . 6-1 APPENDIX A - ENVIRONENTAL SERVICE CONDITIONS APPENDIX B - LISTING OF SAFETY-RELATED ELECTRICAL EQUIPMENT APPENDIX C - PLANT SAFETY-RELATED SYSTEMS AND DISPLAY INSTRUE NTATION APPENDIX D - REVIEW OF LICENSEE'S RESPONSE TO NRC EEQ SER CONCERNING JUSTIFICATION FOR INTERIM OPERATION APPENDIX E - REQUEST FOR ADDITIONAL INFORMATION APPENDIX F - EQUIPMENT WHICH IS EXEMPT OR NOT IN SCOPE OF THE REVIEW 1 I l F l l nklin Research Center A Duman of The Frareen insature

a TER-C5257-511 FOREWORD This Technical Evaluation Report was prepared by Franklin Research Center under a contract with the U.S. Nuclear Regulatory Commission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance

           'in support of NRC operating reactor licensing actions. The technical
           .svaluation was conducted in accordance with criteria established by the NRC.

Principal contributors to the technical preparation of this report were C. J. Crane, J. A. Murphy , K. E. Weice, D. J. Schmitz, and K. J. Iepon of the Franklin Research Center. T. J. DelGaizo from WESTEC Services, Inc., R. Garrison from ORFI Systems, Inc. , and M. A. Fedele from Evaluation Associates, Inc. , also contributed to the technical preparation of this report through subcontracts with Franklin Rasearch Center. I s l i n v dau Franidin Research Center A Dhessen of The Frenten bushde

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TER-C5257-511 IDENTIFICATION OF PROPRIETARY INFORMATION Some of the information in this technical evaluation report was obtained from manufacturers' proprietary test reports. All propriet'ary test reports i cre identified as such in Section 6, References, of this report. Checksheets in Section 4 containing proprietary information have been replaced with a checksheet page stating that the proprietary information has been removed. S^ I I L i i 9 Vii 000 ranklin Research Center A OMaon of The Fransen W

TER-C5257-511

1. INTRODUCTION 1.1 PURPOSE OF THE EVALUATION The purpose of this report is to:

o evaluate licensees' resolutions of outstanding issues related to safety-related electrical equipment environmental qualification (EEQ) discussed in the Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs) in accordance with NRC criteria. The objective is to identify all cases where a licensee's response has not resolved the significant qualification issues. o evcluate licensees' qualification documentation of safety-related electrical equipment located in harsh environments in accordance with criteria established by the NRC and to identify (1) equipment for which qualification documentation is adequate, i.e., substantiates that the equipment is capable of performing its specified design basis safety function when it is exposed to a harsh environment and (2) equipment for which. qualification documentation is deficient, i.e.,

          'does not give reasonable assurance that the equipment is capable of performing its specified safety function.

o evaluate licensees' qualification documentation of safety-related electrical equipment located in harsh environments required for TMI Lessons Learned Implementation. The objective is to evaluate qualification documentation of equipment within the scope of IE Bulletin 79-01B, Supplement 3 (item 2) [9],* in accordance with criteria established by the NRC in a manner identical to the evaluation of all other safety-related electrical equipment. I 1.2 SCOPE OF THE EVALUATION The scope of this report is limited to the evaluation of environmental qualification of electrical equipment that must function to mitigate the consequences of a loss-of-coolant accident (LOCA) or high energy line break (RELB) and whose environment is adversely affected by that event.

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

nklin Research Center A Dhanson of The Franhan homewe

TER.-C5257-511 With respect to TMI Action Plan Implementation, the scope of this report is limited to those sections of NUREG-0737 [13] applicable to equipment having an installation implementation date of January 1,1981. Where applicable, a review is to be performed on installed equipment with implementation dates af ter January 1,1981 if adequately identified by the Licensee. The NRC has determined that the evaluation of environmental qualification of equipment items (1) located in plant areas whose environment is not adversely affected by the design basis event (DBE) (e.g., equipment located in

 " mild" environments) or (2) required to achieve and maintain cold shutdown, is not to be included within the scope of this report. However, where the Licensee has identified these equipment items in the EEQ submittals to the NRC, these items have been listed in NRC evaluation Category III.b in this report (see Section 3 of this report for definition of NRC evaluation categories).

Qualification aspects not included within the scope of this evaluation are: o seismic and dynamic qualification j o equipment protection against natural phenomena o equipment operational service conditions (e.g., vibration, voltage, and frequency deviations) o equipment-located where it is subjected to the outdoor environment o equipment protection against fire hazards o equipment protection against missiles o equipment located in plant areas whose environment is not adversely affected by the design basis event o equipment required to achieve and maintain cold shutdown. 1.3 GENERIC ISSUE BACKGROUND Safety-related electrical equipment must be capable of performing design safety functions under all normal, abnormal, and accident :onditions. 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. i 1-2 UOh Franklin Research Center A DMason of The Freredn insende

TER-C5257-511 Of particular concern is the assurance that equipment will remain cparable during and following exposure to the harsh environmental conditions (i.e., temperature, pressure, humidity [ steam], chemical sprays, radiation, cnd submergence) imposed as a result of a design basis accident. These harsh anvironments are generally defined by the limiting conditions resulting from l tha complete spectrum of postulated break sizes, break locations, and single failures consequent to a LOCA, main steam line break (MSLB) inside the reactor l centainment, or a HELB outside the reactor containment (such as a main steam l or feedwater line break). In addition, depending on specific plant design ! features, other postulated RELB locations may be associated with: o the chemical and volume control system (CVCS) letdown line o the steam supply piping to the auxiliary feedwater (AFW) pump turbine the reactor core isolation cooling (RCIC) pump turbine the high pressure core injection (RPCI) pump turbine the isolation condenser o steam generator blowdown. The NRC criteria for reviewing the safety of nuclear power generating stations include the requirement that the. qualification of safety-related elsetrical equipment be substantiated by auditable documentation of the program that establishes the ability of the equipment to function as specified in the station design. This report is restricted to a technical evaluation of thn equipment's ability to function in harsh environments resulting from DBEs. Qualification criteria applied during the licensing of the older nuclear pswer plants have been modified over the years, and specific industry standards concerning qualification have baan revised as the design of reactor cystems has changed and as regulatory and operating experience has cccumulated. Examples of such standards are IEEE Standards 279-71, 323-74, 383-74, 317-76, 334-80, 381-77, 382-80, 535-79, 627-80, 649-80, and 650-79. NRC NUREG documents 0413 and 0588 have been developed to address this topic. In particular, NUREG-0588 (published for comment in December 1979 and reissued es Revision 1 in July 1981) formally presented the NRC staff positions regarding selected areas of environmental qualification of safety-related elsetrical equipment in the resolution of General Technical Activity A-24, 1-3 4UO0d Franklin Research Center A DMemn of The Frenten ineueuse

TER-C5257-511 ) l

 " Qualification of Class IE Safety Related Equipment." The positions documented j therein are applicable to plants that are or will be in the construction permit or operating license review process.

Although qualification standards and regulatory requirements have

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undergone considerable development, all of the currently operating nuclear power plants are required to comply with 10CFR50, Appendix A, General Design Criteria for Nuclear Power Plants, Section I, Criterion 4. -This criterion states in part that " structures, systems and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing and postulated accidents, including loss-of-coolant accidents." Qualification requirements are also embodied in (1) 10CFR50 Appendix A, General Design Criteria 1, 2, and 23 and (2) 10CFR50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Criteria III, " Design Control," and XI, " Test Control." These requirements are applicable to safety-related equipment located outside as well as inside containment.. The NRC staff has evaluated the licensees' equipment qualification programs by reviewing the qualification documentation of selected safety-related equipment as part of the operating license review for each plant. The NRC staff has also used a variety of methods to assure that these general requirements are met for electrical safety-related equipment. In the oldest plants, qualification was based on the fact that electrical components were of high industrial quality. After 1971, qualification was judged on the basis of IEEE Std 323-71; however, no regulatory guide was issued adopting this standard. For plants whose SERs were issued af ter July 1,1974, the Commission issued Regulatory Guide 1.89, which in most respects adopted the most recent standard, IEEE Std 323-74. In November 1977, the Union of Concerned Scientists petitioned the NRC Commissioners to upgrade current standards for the environmental qualification of safety-related electrical equipment in operating plants. Subsequently, the NRC staff instituted the Systematic Evaluation Program (SEP) to determine the degree to which the older operating nuclear power plants deviated from current nklin Research Center A DMoon of The Frenten insotwo

TER-C5257-511 1 licensing criteria. The subject of electrical equipment environmental qunlification (SEP Topic III-12) was selected for accelerated evaluation as pcrt of this program. Seismic qualification of equipment was to be addressed co a separate SEP topic. In December 1977, the NRC issued a generic letter to all SEP plant licensees requesting that they initiate reviews to determine the l edaquacy of existing equipment qualification documentation. Preliminary NRC review of licensee responses led to the preparation of j NUREG-0458, an interim NRC assessment of the environmental qualification of ,

- electrical equipment. This document concluded that "no significant safety dsficiencies requiring immediate remedial actions were identified." However, it was recommended that additional effort should be devoted to examining the installation and environmental qualification documentation of specific alsctrical equipment in all operating reactors.

iI On May 31, 1978, the NRC Office of Inspection and Enforcement issued IE L 7 Circular 78-08, " Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants," which required all licensees of operating . plcnts (except those included in the SEP) to examine their installed oefety-related electrical equipment and ensure appropriate qualification i documentation for equipment function under postulated accident conditions. Subsequently, on February 8,1979, the NRC Office of Inspection and Enforce-ment issued IE Bulletin 79-01, which was intended to raise the threshold of IE Circular 78-08 to the level of Bulletin, i.e., action requiring a licensee response. This Bulletin required a complete re-review of the environmental quslification of safety-related electrical equipment as described in IE Circular 78-08. The review of the licensees' responses indicated certain deficiencies within tha scope of equipment addressed, definition of harsh environments, and adequacy l of support documentation. It became apparent that generic criteria were needed 4 for evaluating 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 satitled " Guidelines for Evaluating Environmental Qualification of Class IE Elsctrical Equipment in Operating Reactors" [5]. (The document is hereafter 1-5 000 Franidin Research Center A Dhienen of The Frenten Insehme

o TER-CS257-511 referred to as the " DOR Guidelines.") The document was prepared as a screening standard for reviewing all operating plants, including SEP plants. It was originally intended that the licensees evaluate their qualification documentation in accordance with the DOR Guidelines. However, initial NRC review of this documentation, which was compiled to support licensee submittals, revealed the need for obtaining independent evaluations and for accelerating the qualifi-cation review program. In October 1979, the NRC awarded Franklin Research Center a contract to provide assistance in the " Review and Evaluation of Licersing Actions for Operating Reactors," which included an assignment for review of equipment environmental qualification documentation under SEP Topic III-12. The assign-ment was to review equipment environmental qualification documentation and to present the results in the form of a Technical Evaluation Report for the 11 oldest plants (included in the SEP review). The plants included within the assignment were the Palisades, Oyster Creek, Ginna, Haddam Neck, Yankee Rowe, Lacrosse, and Big Rock Point plants and Zion Station Units 1 and 2, Indian Point Units 2 and 3, Millstone Unit 1, Dresden Unit 2, and San Onofre Unit 1. (This assignment was completed in April 1981.) On January 14, 1980, the NRC Office of Inspection and Enforcement issued the DOR Guidelines and IE Bulletin 79-01B, which expanded the scope of IE Bulletin 79-01 and requested additional information on environmental qualifica-tion of safety-related electrical equipment at operating facilities, excluding the 11 facilities undergoing the SEP review. This Bulletin cited the DOR Guidelines as the criteria to be used in evaluating the adequacy of the safety-related electrical equipment qualification. The scope of the review was expanded to include HELBs (inside and outside containment) in addition to equipment aging and submergence. The NRC advised the licensees that the criteria contained in the DOR Guidelines would be used in its review of licensee submittals; NUREG-0588 would be used as a guide in cases where the DOR Guidelines do not provide sufficient detail. In early February 1980, the NRC decided that Indian Point Units 2 and 3 and Zion Station Units 1 and 2 should be included within SEP Topic III-12 for the purpose of equipment environmental qualification review. hranklin Research Center A DMnen of The Fransen insatute

TER-C5257-511 On February 21, 1980, the NRC and representativas of the SEP Plant Owners Grcup held an open meeting at NRC headquarters to discuss an accelerated review pr gram in accordance with the DOR Guidelines. Representatives of the Indian Point Units and Zion Station also attended this meeting. The NRC formal'y iccued to all licensees represented at the meeting the DOR Guidelines document which included a second document, " Guidelines for Identification of That Ssfety Equipment of SEP Operating Reactors for Which Environmental Quclification Is To Be Addressed" [5], together with the request that the l licensees review their plant systems and provide additional equipment environ-mental qualification information to the NRC on an accelerated schedule. For non-SEP plants, the NRC Office of Inspection and Enforcement formed a tcsk force including a principal reviewer in each region and a task leader from headquarters. The regional members were assigned responsibility for the tschnical review of the licensees' responses to IE Bulletin 79-018, and the task leader was assigned responsibility for the overall coordination of the r3 view effort with NRC staff to assure overall consistency. The regi0nal raviewers held meetings'with the licensees in their respective regions, which rasulted in staff positions being issued in a supplement to IE Bulletin 79-01B dated February 29, 1980. In April 1980, the NRC organizational structure was modified and the Equipment Qualification Branch was formed within the new Division of Engi-l naaring. Responsibility.for reviewing the status of equipment qualification for all plants was assigned to this branch. l On May 23, 1980, the NRC issued Memorandum and Order CLI-80-21 (10], cpscifying that licensees and applicants must meet the requirements set forth in the DOR Guidelines and NUREG-0588 regarding environmental qualification of ocfaty-related electrical equipment in order to satisfy 10CFR50, Appendix A, Ginaral Design Criteria, Section I, criterion 4. This Order also established that the SERs on this subject, to be prepared by the NRC staff, must be issued cn February 1, 1981 and that all subsequent actions to be taken by licensees to cchieve full compliance with the DOR Guidelines or NUREG-0588 must be completed no later than June 30, 1982. The Memorandum and Order establishad tha DOR Guidelines and NUREG-0588 as acceptable interpretations of the General 1-7 d Franklin Research Center A DMomn of The Fransen kweswee

k TER-C5257-511 s Design Criteria for an interim period. Rulemaking was proposed for the purpose of establishing a permanent interpretation of the General Design-Criteria. The staff held regional meetings with the licensees and interested parties during the week of July 13, 1980. The staff issued a second supplement to IE Bulletin 79-01B, a response to significant questions raised i 'during the public meetings, and two Orders. The Order dated May 30, 1980 required the licensees to comply with the previorsly issued Commission-Memorandum and Order of May 27, 1980 (CLI-80-21). The above orders required 3 the licensees to complete the tasks identified in IE Bulletin 79-OlB no later than November 1, 1980 to allow the staff to compif with the February 1, 1981 , date imposed by the Commission Order. The responses to the questions were issued on February 29, 1980; and the second and third supplements to IE Bulletin 79-01B, highlighting the staff positione affecting the licensees' I responses, were issued on September 29 and October 24, 1980, respectively. In October 1980, EG&G Idaho, Inc., awarded Franklin Research Center a contract to provide assistance in the equipment environmental qualification review for 13 of the plants whose licensees responded to IE Bulletin 79-OlB. The assignment was to evaluate the licensees' equipment environmental qualifi-

cation submittals and to present the results in the form of a Technical t Evaluation Report for each plant. The objective of this Technical Evaluation Report was to review the licensees' submittals to determine if safety-related electrical equipment was reviewed for environmental qualification in accordance with the DOR Guidelines and NUREG-0588 as required by IE Bulletin 79-OlB. The NRC was to perform an audit of the qualification documentation references as part of its Safety Evaluation Program. If discrepancies were found, the audit was to be extended. The plants included within this assignment were Nine Mile Point Unit 1, Millstone Unit 2, Salem Unit 1, Browns Ferry Units 1, 2, and 3, Brunswick Units 1 and 2, Hatch Units 1 and 2, Dresden Unit 3, and Quad Cities Units 1 and 2. (This assignment was completed in June 1981.)

In mid-1981, the NRC issued SERs on environmental qualification of safety-related electrical equipment to licensees of all operating plants. A 1-8 Obranklin Research Center A Chmon of The Frerden insatuse

TER-C5257-511 Whsre additional qualification information was required, the licensees were directed to respond to the NRC within 90 days of receipt of the SER. > In May 1981, under the licensing action assistance contract, NRC l cuthorized Franklin Research Center to proceed with the review and evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments, required for TMI Lessons Learned Implementation en 71 operating plants. In July 1981, the NRC conducted extensive meetings with the nuclear l industry to address concerns and questions regarding qualification of safety- . ralated equipment. In addition, the NRC provided licensees with detailed information with respect to the format and expected content of the licensees' 90-day responses to the NRC SERs. Draft outlines of the following proposed programs were also presented to the industry: environmental qualification of

aquipment located in " mild" environments, seismic and dynamic qualification, i cnd environmental qualification of mechanical equipment.

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On September 23, 1981, the NRC Commissioners considered a petition (SECY-81-486) to extend the deadline for actions to be taken by licensees to cchieve environmental qualification of all safety-related equipment. On Ssptember 30, 1981, the NRC Commissioners extended this deadline to the second rafueling outage af ter March 31, 1982.

       'In October 1981, the NRC authorized Franklin Research Center to include within the scope of the existing EEQ assignment (TMI Lessons Learned l  Irplementation Equipment) the evaluation cf licensees' resolutions of out-stending issues related to equipment environmental qualification discussed in tha NRC SERs in accordance with NRC criteria. The assignment was to reviev l

l ths qualification documentation and to present the.results in the form of a Tschnical Evaluation Report for 71 operating plants. (This report was devel-cpsd within the scope of this assignment.) On January 7, 1982, the NRC Commissioners approved the issuance of the proposed rule, " Environmental Qualification of Electric Equipment for Nuclear Pcwer Plants," for public comment. The proposed rule was published in the Fsderal Register (Volume 47, No. 13) dated January 20, 1982. A 1-9 ( UOOIFranidin Research Center A Dhisson of The FranMu kuutute

TER-C5257-511 In February 1982, Proposed Revision 1 to Regulatory Guide 1.89,

  " Environmental Qualification of Electric Equipment for Nuclear Power Plants,"

was issued for public comment. This regulatory guide was issued to (1) reflect current NRC positions on equipment qualification and (2) provide guidelines for meeting the NRC Commissioners proposed rule on equipment qualification. The final rule, " Environmental Qualification of Electric Equipment for Nuclear Power Plants," was subsequently issued on April 16, 1982 by the NRC (to be published in the Federal Register) to clarify and strengthen the criteria for environmental qualification of electrical equipment. The final rule is to be incorporated into 10CFR50 as section 50.49, " Environmental Qualification of Electric Equipment for Nuclear Power Plants." The significant features of the rule are: o Requalification of electrical equipment in accordance with the rule will not be required for equipment qualified or being qualified in accordance with the DOR Guidelines and IE Bulletin 79-01B or NUREG-0588, provided the qualification program commenced within 90 days after the effective date of the rule. o The requirement to qualify equipment needed to complete one path of

;            achieving and maintaining a cold shutdown condition has been deleted.

I o A new section has been added, covering the qualification of equipment , located in mild environments. t o The Commission deadline for actions to be taken by licensees to achieve environmental qualification of all safety-related equipment is extended to the second refueling outage after March 31, 1982. On April 20, 1982, the NRC staff issued Generic Letter No. 82-09 [11] to all licensees, presenting the NRC's position and clarification of certain aspects of the environmental qualification requirements. 1.4 SPECIFIC ISSUE BACKGROUND On May 31, 1978, the NRC Office of Inspection and Enforcement issued IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants," which required all licensees of operating plants to examine their installed safety-related electrical equipment and 1-10 4000ll Franklin Research Center A Dwman of The Frer*hn Inseeme I

TER-C5257-511 ansure appropriate qualification documentation for equipment function under pestulated accident conditions. Subsequently, on February 8,1979, the NRC Office of Inspection and Enforcement issued IE Bulletin 79-01, which was intended to raise the threshold of IE Circular 78-08 to the level of Bulletin, i.o., action requiring a licensee response. On Tanuary 14, 1980, the NRC Office of Inspection and Enforcement issued tha DOR Guidelines and IE Bulletin 79-01B,-which expanded the scope of IE Bulletin 79-01 and requested additional information on environmental qualification of safety-related electrical equipment at operating facilities. On March 15, 1980, CP&L provided the NRC with a submittal in response to IE Bulletin 79-01B for the H. B. Robinson Steam Electric Plant Unit 2 [22]. On July 7,1980, CP&L submitted to the NRC further information [1, 2] in rarponse to IE Bulletin 79-01B. The NRC Office of Inspection and Enforcement performed (1) a preliminary evaluation of the Licensee's response, documented in a technical evaluation raport (TER) and (2) an onsite verification inspection (August 25-29, 1980) of , selected safety-related electrical equipment. The reactor coolant, safety injection, auxiliary cooling, and heating, ventilation, and air conditioning systems and electrical penetration assembly were inspected. All the equipment inIpected is located inside containment. The inspection verified proper installation of equipment, overall interface integrity, and manufacturers' n2zeplate data. The manufacturer's name and model number from the nameplate data were compared to information given in the component evaluation work j shsets of the Licensee's report. The site inspection is documented in report IE 50-261/80-20. No deficiencies were noted. On November 21, 1980 [3, 4], CP&L submitted to the NRC Revision 1 and Rsvision 2 to the previous response to IE Bulletin 79-01B. On January 30, 1981 [14, 15], CP&L submitted to the NRC Revision 3 to the prsvious response to IE Bulletin 79-01B. The NRC issued a Safet7 Evaluation Report (SER) to the Licensee on May 21, 1981 [16]. A l-11 du Franklin Research Center A DMoon of The Frannen Insamme

TER-C5257-511 On July 21, 1981, with NRC approval, FRC requested from CP&L additional technical information regarding the 79-OlB Revision 3 submittal [33]. On July 31, 1981, CP&L provided FRC with (1) Analysis of High Energy Line Break Outside Containment, (2) 45-day response to I&E Bulletin 79-01B, (3) General Plant Procedure No. 6, and (4) Reference 52 of CP&L's response to Supplement 3 to I&E Bulletin 79-01B [17]. 00 August 31, 1981, CP&L transmitted to the NRC the response to the SER [20]. Requests for qualification documentation were transmitted to the NRC on November 24, 1981 [30], February 1, 1982 [31], and April 7, 1982 [32]. By letter dated March 1, 1982, CP&L stated that the most efficient and productive way to deal with the FRC request for qualification documents was to have an audit / meeting with the NRC and FRC at Raleigh [24]. t nklin Research Center A DMoson of The Franhan insatute

TER-C5257-511

2. NRC CRITERIA FOR ENVIR0l#1 ENTAL QUALIFICATION 2.1 CRITERIA PROVIDED BY THE NRC

! The screening guidelines used to evaluate the electrical equipment snvironmental qualification program were: , o DOR Guidelines, " Guidelines for Evaluating Environmental' Qualification of Class lE Electrical Equipment in Operating Reactors," November 1979 [5] - o NUREG-0588, Revision 1, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," July 1981 [12]. Other appropriate references used in the review of the licensees'~ electrical equipment environmental qualification submittals are: o IE Bulletin 79-OlB, " Environmental Qualification of Class lE Equipment," January 14, 1980; Supplement No. 1, February 29, 1980; Supplement No. 2, September 29, 1980; and Supplemer.t No. 3, October 24, 1980 [6, 7, 8, 9] o NUREG-0737, " Clarification of TMI Action' Plan Requirements," November 1980 [13]. This document is applicable for the selection of equipment for the evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments l required for TMI Lessons Learned Implementation. The scope of the j review is limited to equipment associated with specific sections of l NUREG-0737 which have an instellation implementation date of January l 1, 1981. Where applicable, a review is to be performed on installed l equipment with implementation dates after January 1, 1981 if t adequately identified by the licensee. 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 screening guidelines. i 2.2.1 Requirements and Applicable Criteria l Items 3 and 17 of Supplement 2 to IE Bulletin 79-01B [8] describe the l cpplication of the DOR Guidelines and NUREG-0588 to operating reactors (ors), A 2-1 UO0hranklin Research Center A Dhesian d The Frm m t

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

TER-C5257-511 , near term operating license applicants (NTOLs), and construction permit applicants (cps). The qualification requirements and applicable criteria are i stated as follows: [ Question 3]

                    " Define the requirements and applicable criteria for ors, NTOLs, and OLs. Specifically address the NTOLs whose CP SER is prior to July 1974                                                           '

and after July 1974. Can a CP whose SER is prior to 1974 use the DOR guidelines?" (NRC Answer to Question 3]

                    " Table 1 describes the application of each document. All operating reactors as of May 23, 1980, will be evaluated against the DOR guidelines.            In cases where the DOR guidelines do not provide sufficient detail, but NUREG-0588 Category II does, NUREG-0588 will be used.

3 TABLE 1 REQUIRENENTS ors OLs cps CP SER CP SER DOR GUIDELINES Before 7/1/74 After 7/1/74 USE NUREG-0588 NUREG-0588 NUREG-0588 NUREG-0588 AS NECESSARY (CAT. II) (CAT. I) (CAT. I) or NEW RULE WHEN IN EFFECT REPLACEMENT COMPONENTS USE NUREG-0588 (CAT. I) All plants licensed after May 23, 1980, shall conform to NUREG-0588. In accordance with Regulatory Guide 1.89, all such operating licenses for ' facilities whose construction permit SER is dated July 1, 1974 or later,

                   .are to be reviewed against IEEE Std. 323-1974. Thus, for these licensees, the operating license applicant is to qualify equipment to the Category I column in NUREG-0588. For operating licenses issued after May 23, 1980, whose construction permit SER is dated before July 1,1974, the operating license applicant is to qualify equipment to at least Category II column of NUREG-0588;* unless the licensee made commitment in the construction permit record to use the 1974 standard, or unless the operating licensee application record indicates that the 1974 standard is to be u' sed, in such cases Column I of NUREG-0588 is to be used.

While there are differences between the Category II column of NUREG-0588 and the DOR guidelines, the differences are in details and in the 2-2 , OOOEranidin Research Center A DMaan of The Frenten insames

                                                                                  -g u - - u~.           ..-+----m.x. .n--a           1 - s- a.   - - - - - - ~ . _ . . -

2 TER-C5257-511 4 4 l optional part of the documents. The miniarm requirements set forth by j .these documents are general and compatible. Thus, the minimum standards

                       . set by either of the two documents are equally applicable to ors and                                                                             i l

NTOLs."

[ Question 17] l t

i " Define the requirements for ' replacement parts. ' Are they the same for

                             ' spare' parts? Clearly discuss the alternatives for existing inventories of parts / components.                 If equipment is ordered to meet IEEE Std. 323-1974 standard but lead time exceeds June 1982, can we use IEEE Std. 323-1971 qualified components in the interim?"                                                                                 '

[NRC Answer to Question 17]

                          "The requirements for ' replacement' and ' spare' parts are the same for the purposes of complying with the Commission order and memorandum.

After May 1980, all parts used to replace presently installed parts shall be qualified to Category I of NUREG-0588 'unless there are sound reasons i to the contrary.' Nonavailability and/or the fact that the part to be used as a replacement is a spare part purchased prior to May 23, 1980, and is in stock are among the factors to be considered in weighing whether there are ' sound reasons to the contrary. ' All replacement parts shall as a minimum conform to the requirements described in the answer to question 3. Justification for deviation from Category I of NUREG-0588 shall be documented by the licensee and records shall be available for audit, upon request by the NRC." i 2.2.2 Application of Requirements and Criteria to TMI' Lessons Learned Implementation Equipment The NRC requested an evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments required for TMI Lessons Learned Implementation in accordance with criteria established by i; I '\ ths NRC 'in a manner identical to the evaluation of all other safety-related "s elsctrical equipment. Additionally, Item 21 of Supplement 2 to IE Bulletin l<

    -s 01B [8[* states:
      ?        ,
                       "TMI Lessons Learned instrumentation will be considered in the February 1,
                  .1981 SERT This equipment is subject to the same requirements as other safety-related electrical equipment. The guidance and requirements of NUREG-0588 referenced daughter standards, and Reg Guides will be used by the staff in assessing the adequacy of the qualification information."

, Item 2 of Supplement 3 to IE Bulletin 79-01B [9] states: s "IEB 79-01B required a' 90 day response which was due in mid-April 1980. Supplement l'-(Feb.1980) informed licensees that equipment which was anklin Research Center A Dhtman of The FrentenIneshoe - w s

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

TER-C5257-511

              ' planned' to be installed as a result of lessons learned need not be addressed in that. response.      Some of this equipment has since been installed.       Supplement #2 (Q.5, Q.21) identified that the staff position was that equipment which is installed should be treated in a manner similar to all other safety-related electrical equipment and be addressed in the November 1, 1980 submittal. This position represents no change in staff position regarding the scope of the review. However, since the staff position on this issue was unclear the following will apply:

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

b. Qualification information for future TMI Action Plan equipment (ref.

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

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

d. Qualification information for TMI Action Plan equipment not yet installed which does not require pre-implementatio'n review should be submitted to NRC for review by the implementation date."

2.2.3 Equipment Not in the Scope of the Qualification Review i Supplement 2 of IE Bulletin 79-01B [8] 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 high energy line break (HELB) or to nuclear radiation emanating from circulation of fluids containing radioactive substances. Supplement 3 of IE Bulletin 79-01B [9] permits deferment of the review of environmental qualification for all equipment required to achieve and maintain the plant in a cold shutdown i I condition. Supplements 2 and 3 of 79-01B originally permitted deferment until af ter February 1,1981 of the qualification review of equipment located in a mild environment or required to achieve and maintain the plant in a cold shutdown condition. Since the issuance of Supplements 2 and 3, the NRC has determined that the review of environmental qualification for this equipment is not within the scope of the present review program. i

                 --nklin-Research
                             - -.r Cen e

4 TER-CS257-511 2.2.4 Clarification of Qualification Requirements 2.2.4.1 Service Conditions Inside Containment for a Loss-of-Coolant Accident (DOR Guidelines Section 4.1) I j For pressurized water reactors (PWRs), the DOR Guidelines state that the centainment temperature and pressure conditions as a function of time should bo based on the most recent NRC-approved service conditions specified in the , Final Safety Analysis Report (FSAR) or other licensee documentation. In the cpscific case of pressure-suppression type containments, the following minimum high temperature conditions may be used: (1) boiling water reactor (BWR) drywells -- 340*F for 6 hours and (2) PWR ice condenser lower. compartments -- 340*F for 3 hours. As stated in Supplement 2 to IE Bulletin 79-01B [8],

       "these values are a screening device, per the Guidelines, and can be used in lisu of a plant-specific profile, provided that expected pressure and humidity

ccnditions as a function of time are accounted for."

Service conditions should bound those expected for coolant and steam line i breaks inside containment with due consideration given to analytical uncertainties. The steam line break condition should include superheated ccaditions, the peak temperature, and subsequent temperature / pressure profiles ce functions of time. If containment spray is to be used, the impact of the cpray on required equipment should be assessed. l The adequacy of a plant-specific profile depends on the assumptions and dzsign considerations at the time the profiles were developed. The DOR Guidelines and NUREG-0588 provide guidance and considerations required to l dstermine if the calculated plant-specific temperature / pressure profiles sncompass the loss-of-coolant accident (LOCA) and HELB accidents inside I' containment. i 2.2.4.2 Submergence (DOR Guidelines Section 4.1, Subitem 3; and Sec' tion 4.3,2, Subitem 3) Equipment submergence (inside or outside containment) should be addressed whsre the possibility exists that submergence of equipment may result from HELBs or other postulated occurrences. Supplement 2 to IE Bulletin 79-01B [8] provides the following additional criterion: If the equipment satisfies the 2-5 b Franidin Research Center A Dhausen of The Fransen Inseaune

TER-C5257-511 guidance and other requirements of the DOR Guidelines or NUREG-0588 for the LOCA and HELB accidents, and the licensee demonstrates that its failure will not adversely affect any safety-related function or mislead the operator after submergence, the equipment can be considered exempt from the submergence portion of the qualification requirements. 2.2.4.3 Simulated Service Conditions and Test Duration (DOR Guidelines Section 5.2.1) The Guidelines require that the test chamber environment envelop the required service conditions for a time equal to the period from the initiation of the accident until the service conditions return to normal. Supplement 2 to IE Bulletin 79-01B [8] 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 I hour in excess of the time assumed in the accident analysis. The staff has indicated that time is the most significant factor in terms of the margins required to provide an acceptable confidence level that a safety-related function will be completed.       The 1-hour qualification requirement is based on the acceptance of a type test for a single unit and the spectrum of accidents (small and large breaks) bounded by the single test."

2.2.4.4 Test Sequence (DOR Guidelines Section 5.2.3) Supplement 2 to IE Bulletin 79-01B [8] provides the following additional criteria:

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

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

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

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

nklin Research Center A DMemn of The FrentenInseawee

'l TER-G5257-511 2.2.4.5 Radiation (DOR Guidelines Sections 4.1.2, 4.2.2, and 4.3.2, Subitem 2) Supplement 2 to IE Bulletin 79-01B [8] provides the following additional j criteria: , "Both the DOR Guidelines and NUREG-0588 are similar in that they provide i the methods for determining the radiation source te m when considering LOCA events inside containment (100%-noble gases /50% iodine /1%

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

NUREG-0578 provides the radiation source term to be used for determining the qualification doses for equipment in close proximity to recirculating fluid systems inside and outside of containment as a result of LOCA. This method considers a LOCA event in which the primary system may not depressurize and the source term inventory remains in the coolant. NUREG-0588 also provides the radiation source term to be used for qualifying equipment following non-LOCA events both inside-and outside containment (10% noble gases /10% iodine /0% particulates). When developing radiation source terms for equipment qualification, the licensee must ensure consideration is given to those events'which provide the most bounding conditions. The following table summarizes these considerations: ) LOCA Non-LOCA HELB Outside Containment NUREG-0578 NUREG-0588

(100/50/1 (10/10/0 l in RCS) [*] in RCS) l Inside Containment Larger of NUREG-0588 NUREG-0588 (100/50/1 (10/10/0 4

in containment) in RCS) or NUREG-0578 (100/50/1 in RCS)

,    *The numbers in parentheses represent % noble gases /5 iodine /% particulates.
       - RCS means reactor coolant system.

2-7 u00u ersnioin Rese.,ch center A Dhamon of The FranienInsehne

TER-C5257-511 Ganesa equivalents may be used when considerati~ o n of the contibutions of ' beta exposure has been included in accordance with_the guidance given in the DOR Guidelines and NUREG-0588. Cobalt 60 is one acceptable ganana radiation source for environmental qualification of safety-related equipment. Cesium 137 may also be used." 2.2.5 Additional Clarification of Qualification Requirements The NRC has worked with a number of licensees, at their requests, to provide further clarification on environmental qualification requirements. .On January 20, 1982, the NRC issued Generic Letter No. 82-09 [11] presenting

;             staff positions on certain aspects of the qualification requirements. Generic

Letter No. 82-09 states

a "1. Operator Display Instrumentation Q. Given the interrelated activities associated with display instrumentation (e.g., NUREG-0700, NUREC-0799, proposed Regulatory Guide 1.97 and Equipment Qualification efforts), what display instrumentation referenced in emergency operating procedures must be identified in licensee submittal to the NRC? A. All display instrumentation referenced in the emergency procedures need not be identified. The NRC requires that licensees need only identify and have available qualification documentation on those operator display instruments which are safety-related (see Question 2). If licensees have previously supplied a listing of all display  ; instrumentation referenced in emergency procedures, licensees may identify (such as by the use of an *) which of those instruments are safety-related. The staff will defer review of the basis'for this safety-related classification until other NRC activitiesl have been implemented. When these other activities are implemented, additional instruments presently not requiring qualification may require upgrading to a safety-related status and/or may require qualification. Licensees will be required at that time to qualify this instrumentation in accordance with the following criteria: o For new or upgraded instrumentation with a required operation date prior to the equipment qualification deadline, qualification must be accomplished by the equipment qualification deadline. 1 Such activities include preparation of new emergency procedures (NUREG-0799), control room design reviews (NUREG-0700), and upgrading of accident monitoring instrumentation (Reg. Guide 1.97 and NUREG-0737). nklin Research Center A Deween of The Frereen ineswe

                                                                                                         .-   ~

TER-C5257-511 o For new or upgraded instrumentation with a required operation date after the equipment qualification deadline, qualification must be accomplished prior to equipment operation and plant acceptance.

2. Safety-Related Equipment Q. For Equipment Qualification purposes, what constitutes all safety-related electrical equipment?

A. The Commission, in CLI-80-21, required the environmental qualification of only safety-related electrical equipment. Identification of the safety-related equipment installed at specific plants can be obtained from FSARs, Technical Specifications and other docketed correspondence setting forth NRC requirements or licensee commitments. Identification of safety-related equipment installed in harsh environments at specific plants must be supplied by the licensee. The necessity for upgrading nonsafety-related system to safety-related status will be the subject of other NRC reviews.

3. Replacement Parts Q. Please clarify the NRC requirements on replacement parts.

A. In CLI-80-21, the Commission stated that unless there were sound reasons to the contrary, replacement equipment should be qualified to the standards set forth in Category I of NUREG-0588. The Commission's position was designed to promote the policy of upgrading the environmental qualification and reliability of installed safety-related electrical equipment. To meet this overall goal, licensees must institute internal policy practices consistent with the Commission's statement. l l Situations may arise in which upgrading to NUREG-0588, Category I of replacement equipment qualified to NUREG-0588, category II or the DOR Cuidelines will not be compatible with overall station safety l and performance goals. Licensees must review such situations on a case-by-case basis and determine that 'sound reasons to the contrary' do, in fact, exist which warrant the use of replacement equipment (not necessarily in-kind) qualified to the DOR Guidelines or NUREG-0588, Category II. For equipment located in,a harsh , environment, licensees' procedures must provide for documentation and substantiation of such determinations, i nidin Research Center A Demmon of The Frenten insumane y , - , - -

( 1 TER-C5257-511 Conditions which reflect sound reasons why qualification standards for replacement of equipment in a harsh environment need not be upgraded to NUREG-0588, Category I include the following:

1. The licensee has replacement equipment in stock that meets the DOR Guidelines or NUREG-0588, Category II, and procurement actions regarding such replacement equipment had commenced prior to May 23, 1980.

2. Replacement equipment qualified to the NUREG-0588, Category I standards does not exist.

3. Replacement equipment qualified to the NUREG-0588, Category I standards is not available to meet installation and operation schedules. Equipment qualified to the DOR Guidelines or NUREG-0588, Category II may be used for an interim period until Category I equipment is obtained and an outage of sufficient duration is available for replacement. Justification for use of the non-Category I qualified replacement equipment beyond this interim period must be submitted to the NRC for approval prior to the end of the interim period and in sufficient time for reasonable NRC review.

4. Replacement equipment qualified to NUREG-0586, category I standards would require significant plant modifications to accommodate its use.

5. Operating performance and reliability data for the Category I equipment indicates poor overall equipment performance. For example, mean time to failure is significantly shorter for the Category I replacement equipment.

6. The use of replacement equipment qualified to NUREG-0588, Category I standards has a significant probability of creating human factor problems that will negatively affect plant safety and performance, e.g., (1) knowledge, skills and ability of existing plant staff require significant upgrading to operate or maintain the specific Category I replacement equipment; (2) the

, use of equipment qualified to Category I standards creates a one-of-a-kind application; or (3) maintenance, surveillance or calibration activities are unnecessarily complex.

5. Submergence outside Containment Q. For equipment qualification purposes, what are the staff requirements concerning submergence of equipment outside containment?

nidin Research Center A Deveson of The Fransen insuouse

4 TER-C5257-511 A. The Staff requires that the licensee submit documentation on the qualification of safety-related equipment that could be submerged due to a high energy line break outside containment.

        . 6. Radiation Q. Is the staff screening value of 4 x 107    rads applicable to all operating reactors?                                                      i 4

A. No. This screening value is applicable only to PWRs with dry type containments. However, for PWRs with dry type containments, the licensee may choose to use plant specific analysis instead of the screening value. For plants with other containment types, the licensee must use plant specific analysis. Acceptable to the Staff for equipment qualification purposes are

 ,            radiation values developed as part of the plant licensing process-provided that they are based on the TID 14844 source terms and are conservatively performed. In order to assure that the methodologies
   ,          are appropriate, the Staff requests two component specific sample calculations (one for inside and one for outside containment), and a brief written description of each of the methodologies used, their application and associated conservatisms.      Such sample calculations and a statement by the licensee that the values of radiation exposure of components so derived are appropriate for environmental qualification of equipment will satisfy the Staff's concern on the
               ' Radiation Specification Value' used during the qualification reviews.

7. Containment Service Conditions

, Q. Must the Staff value (identified in the SERs) of TSAT for PWRs and i TSAT + 20*F for BWRs be used as the maximum in-containment ! temperature for the purpose of equipment qualification? A. No. The Staff will accept the use of these values. However, an l acceptable alternative to the NRC staff's temperature criterion used

• l for the service conditions must base that service condition on the FSAR analysis or other NRC approved analysis, provided that the specific analysis, or a summary of that analysis, together with reference to the previous NRC acceptance of the analysis is submitted by the licensee. In addition, some of the information in the associated safety evaluation may require clarification.

l

8. One Hour Minimum Operating Time Q. The Staff has previously indicated that certain exceptions to the one hour minimum operating time rule are permitted. Can further clarification be provided?

l

_ranidin_Rese_

_ arch._

                                 . Center

4 TER-C5257-511 A. With regard to plants subject to the qualification requirements of the DOR Guidelines or Category II of NUREG-0588, for those pieces of equipment tested prior to May 23, 1980, the test data and analysis j may be used to qualify the equipment to the required operating time plus an appropriate margin. The one hour margin requirement need not be applied. However, subsequent failures should be shown not to be detrimental to plant safety. , The one hour time margin rule is not applicable to equipment whose safety function is performed prior to significant changes in the environment at the equipment location. , 9. Q Q. Must a qualified life be developed for all safety-related electrical equipment located in harsh environments? A. Section 7 of the DOR Guidelines and Section 4.2, Category II of NUREG-0588, do not require a qualified life to be established for all safety-related electrical equipment located in harsh environments. A qualified life, in accordance with the provisions in IEEE 323-1974, is required for equipment, including replacement parts, qualified to Category I of NUREG-0588 that is located in a harsh environment. An acceptable method for addressing in-service degradation is through a preventive maintenance / surveillance program with equipment and component refurbishment and/or replacement based on known susceptibility to aging degradation, the results of inspections, or manufacturers recommendations. These elements of the program lead to an understanding on a device specific basis of the nature and extent of the increased stress levels encountered during Design Basis Accidents and resultant degradation (if any) which may occur. Arrhenius or other appropriate accelerated aging methodologies may_be used to establish replacement and refurbishment schedules if the component's design and materials application are sufficiently simple and the necessary data are available to allow a meaningful applica-tion. In plants subject to the qualification requirements of either the DOR Guidelines or NUREG-0588 Category II, for equipment that has been identified as being susceptible to significant degradation due to thermal and radiation aging, the schedule for inspection of and/or replacement of the susceptible components in that equipment must be incorporated into the preventive maintenance and surveillance programs, and that information should be incorporated into the system component evaluation worksheets (SCEWS). For other equipment, the aging column in the SCEWS should be marked 'No Known Susceptibility'." nklin Research Center A Dhesson of The Fransen buteuse

TER-C5257-Sil

3. METHODOLOGY USED FOR THE EVALUATION

3.1 INTRODUCTION

As discussed in Section 1.3 of this report, the NRC issued Safety Evaluation Reports (SERs) on environmental qualification of safety-related equipment to licensees of all operating plants in mid-1981. The SERs identified various equipment qu.nlification deficiencies as indicated below: LEGEND: DESIGNATION FOR DEFICIENCY R - Radiation M - Margin T - Temperature I - HELB Evaluation Outside QT Qualification Time Containment Not Completed RT - Required Time QM - Qualification Method P - Pressure RPN - Equipment Relocation or Replacement, H - Humidity Adequate Schedule Not Provided CS - Chemical Spray EXN - Exempted Equipment Justification A - Material Aging Evaluation, Inadequate Replacement Schedule, Ongoing SEN - Separate Effects Qualification Equipment Surveillance Justification Inar', equate S - Submergence QI - Qualification Information Being (R) - Licensee has committed Developed to replace equipment RPS - Equipment Relocation or Replacement Schedule Provided-The SERs directed licensees to "either provide documentation of the missing qualification information which demonstrates that safety-related equipment meets the DOR Guidelines or NUREG-0588 requirements or commit to a corrective action (re qualification, replacement [etc.]) to establish qualification by June 30, 1982." Licensees were required to respond to the NRC within 90 days l ! of receipt of the SER. As' stated in Section 1.1, the purpose of this report is (1) to evaluate ! licensees' . resolutions of outstanding issues related to safety-related electrical equipment environmenta1' qualification (EEQ) discussed in the NFf,'s j SERs in accordance with NRC criteria, and (2) to evaluate licensees' qualification documentation of safety-related electrical equipment, including i 3-1 00hranidin Research Center -i A m otne rawen m , t nwe m ., . ,. y.- , . . < ~ . . , _ , . - - - , - - - - , . , , , , . ,a , , , , , . , , , , , , . , -

TE R.-C5257-511 - TMI Lessons Learned Implementation equipment, located in harsh environments in accordance with' criteria established by the NRC (see Section 2 of this report). The methodology used to evaluate (1) the Licensee's response to the NRC SER and (2) the equipment environmental qualification is presented herein. 3.2 METHODOLOGY The Licensee, Carolina Power and Light Company, provided a response to the SER and additional qualification information in its submittals [17, 20] to the NRC for the Robinson Unit 2 Nuclear Power Plant. The following bases provided by the NRC were used to determine the relative completeness of the Licensee's submittals: o Determine whether the Licensee provided specific responses to the SER Concerns. o Determine whether the Licensee proposed corrective actions and a

                                                             ~

schedule for completion of the actions. o Determine whether the Licensee addressed the NRC's concern for margin

;          with respect to the containment environmental conditions.

o Determine whether the Licensee revised the environmental parameters. o Determine whether the Licensee's System Component Evaluation Work Sheets (SCEWS) were updated to correct deficiencies and add

supplemental information.

l

       .o Determine whether the Licensee provided justifications for interim operation for all unqualified equipment.

o Determine whether the Licensee addressed aging and incorporated the results into the equipment maintenance program. The extensive list of safety-related electrical equipment

• in various i

locations of the plant identified by the Licensee was analyzed, and all identical equipment located within plant areas that are exposed to the same environmental service conditions was grouped together and designated an

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

nklin Research Center A OMemn of The Frenten m

TER-C5257-511 'hquipment item." In this report, the term " equipment item" refers to a specific type of electrical equipment, designated by manufacturer and model, which is representative of all identical equipment in a plant area exposed to the same environmental service conditions (e.g., Flow Transritter, Fischer & Porter, Model 10B2496, located within containment). This analysis resulted in c reduced listing of equipment (equipment items) that formed the basis for the review. Appendix A contains the environmental service conditions for each 1ccation. Appendix B contains the tabulation of the equipment items, locations, function, plant identification numbers, required operating time, cud applicable qualification documentation references. Appendix C lists the plant systems identified by the Licensee and the NRC as being essential to cafety. Each item in the list of safety-related electrical equipment items was rsviewed in relation to: o the Licensee's response to the SER concerns o technical information received from the Licensee as a result of requests for additional information (Appendix E) o technical data derived from the Licensee's submittal o NRC DOR Guidelines or NUREG-0588 Revision 1 criteria o the Licensee's definition of harsh service environments ( Appendix A) o documentation cited by the Licensee as evidence of qualification o applicable and available qzalification documentation associated with the overall equipment environmental qualification program o the Licensee'e analysis ard/or justification of qualification o Licensee-proposed corrective action for qualification deficiencies o the Licensee's equipment /part replacement schedules o the Licensee's technical arguments concerning the adequacy of equipment, based on system operational considerations o the Licensee's rationale concerning exemption of equipment from qualification. A 3-3 UO0hranklin Research Center A Ofwesion of The Frenhan ensseuse

TER-C525 7-Sil Topics not within the scope of the evaluation are: o completeness of the Licensee's listing of safety-related equipment o acceptability of Licensee-provided environmental service conditions. The NRC requested an evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments required for TMI Lessons Learned Implementation. Theobjectiveistoevaluatequali5ication documentation of equipment within the scope of IE Bulletin 79-01B, Supplement 3 (item 2), in accordance with criteria established by the NRC (see Section 2 of this report) in a manner identical to the evaluation of all other safety-related electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with those sections of NUREG-0737 which have an equipment installation implementation date of January 1,1982 (sections are identified below). Where applicable, a review was to be performed on installed equipment with implementation dates after January 1, 1981 if adequately identified by the licensee. II.B.3 ( ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment II.D.3 ( ALL/1-1-81) Direct Indication of Relief and Safety Valve Position II.E.1.2 (PWR/1-1-81) Auxiliary Feedwater System Automatic Initiation and Flow Indication II.E.3.1 (PWR/1-1-81) Emergency Power Supply for Pressurizer Heaters (Safety-Grade Interfaces) II.E.4.1 (ALL/7-1/81) Dedicated Hydrogen Penetrations II.E.4. 2 ( ALL/1-1-81) Containment Isolation Dependability II.F.2 (PWR/1-1-81) Instrumentation for Detection of Inadequate Core Cooling II.G.1 (PWR/1-1-81) Emergency Power for Pressurizer Equipment (Safety-Grade Interfaces) II.K.2.10 (PWR/B&W/7-1-81) Safety-Grade Anticipatory Reactor Trip II.K.3.9 (PWR/W/1-1-81) PID Controller Modification (If Hardware Change Involved) . nklin Research Center A Duman of The Frankan insMule

                                                                                                        ,g TER-C5257-511 II.K.3 12 (PWR/W/1-1-81) Anticipatory Reactor Trip upon Turbine Trip II.K.3.13 (PWR/GE/7-1-81) Separation of HPCI and RCIC Initiation Signals II.K.3.15 (BWR/GE/7-1-81) Prevention of Spurious Isolation of HPCI and RCIC Systems

, II.K.3.19 (BWR/GE/7-1-81) Interlock on Recirculation Pump Loop l II.K.3.21 (BWR/CE/7-1-18) Restart of Core Spray and LPCI Systems (If - Hardware Changed Out) II.K.3.27 (BWR/GE/7-1-81) Provide Common Reference Level for Vessel Level Instrumentation (If Hardware Changed Out) Licensees whose plants were included within the NRC Systematic Evaluation Prcgram received a Technical Evaluation Report (TER) in addition to the SER. Thi TER was based on a review of equipment environmental qualification dccumentation associated with the Licensee's EEQ submittals. The qualification dsficiencies identified in the SER were derived from the TER. Plants included within this program were the Palisades, Oyster Creek, Ginna, Haddam Neck, Yankee Rowe, Lacrosse, and Big Rock Point plants and Zion Station Units 1 and 2, Indian Point Units 2 and 3, Millstone Unit 1, Dresden Unit 2, and San On:fre Unit 1. For these plants, the evaluation presented herein is based on (1) the result of the initial TER, (2) the Licensee's response to the NRC SER and the TER, and (3) the Licensee's updated EEQ submittal (s). l TERs were also developed for the following plants: Nine Mile Point Unit 1, Millstone Unit 2, Salem Unit 1, Browns Ferry Units 1, 2, and 3, Brunswick Units 1 and 2, Hatch Units 1 and 2, Dresden Unit 3, and Quad Cities Units 1 cnd 2. The objective of those TERs was to review the Licensee's submittals to datermine if safety-related electrical equipment was reviewed for environmental qualification by the Licensee in accordance with the DOR Guidelines and NUREG-0588 as required by IE Bulletin 79-01B. For these 13 plants and all other plants, excluding the 14 plants associated with the Systematic Evaluation Program, the evaluation presented herein is based solely on (1) the Licensee's response to the NRC SER and (2) the Licensee's revised EEQ submittal (s). This technical evaluation was conducted to identify (1) whether the Licensee provided an adequate response to the SER concerns (and TER concerns, nidin Research Center A Dhamon of The Frenten insense

i TER-C5257-511 where applicable), (2) major deficiencies within the equipment' qualification program, and (3) whether the Licensee proposed adequate corrective actions to resolve qualification deficiencies and provided a schedule for completion of the corrective actions. The TER was written primarily to address deviations from the NRC criteria and requirements. Technical data or test results that satisfy the qualification criteria are not discussed herein. The evaluation presented in Section 4 of this report includes completed equipment environmental qualification review checksheets (partially handwritten) which compile both the technical information necessary to conduct the review and the results of the evaluation. Parameters listed on these checksheets were derived from the appropriate NRC screening criteria. The evaluation of each equipment item includes several checksheet pages. Only those checksheet pages necessary to complete the evaluation for each equipment. item are included in this report. A complete listing of the checksheet pages is shown on the bottom of Checksheet -la, reproduced here as Figure 3-1. The checksheets contain the following information: o Equipment item information (see Figure 3-1), for example: Solenoid Valve Located in Turbine Building (Area #7) Automatic Switch Co. (ASCO) Model LB8300B61U Actuates Feedwater Control Valves (V-4269, V-4270) Licensee Reference 839 Required Operating Time: Short term (SI signal) TER Cheeksheet No.1 Reference 59, Section 4.5.2.6 Licensee Submittal: Page 9 (62]; Table 3, Page 1 [1]; SCEW 1 o Qualification deficiencies identified in the SER (see Figure 3-1) o Licensee's response to the SER o Licensee's statements and rationale for qualification o Licensee's corrective action and replacement schedule

o Evaluation of qualification including identification of all deficiencies o Evaluation of system considerations presented by the Licensee as a rationale for excluding equipment from qualification.

The results of the evaluation are summarized on Checksheet 2 (Equipment Environmental Qualification Summary Form) for each equipment item. Checksheet nklin Research Center A Dhmon of The Frenahn hanuse

            .       . . - .            -                  .-. _   . _ - . ~ . .   , --        .-.:-_.-   ,- --   ,._.__a_

TER-C5257-511 3 &llU0U Frenidin Reeeeech Center NMC Conweet No.NHC43 75118 FRC Project No.C83By Page A Dewsten of N Franhaninessues FRC Aggionment No.13 la 3Dih and Rase Semes. PMe.. Pe.195e3 Gill 441 con FRC Task No. < EQUIPMENT ENVIRONMENTAL QUAUFICATION REVIEW OF EQUIPMENT ITEM NO. _ Equipment Item No. 1 Solenoid Velves Located in Turbine Building (Area #7) Automatic Switch Co. (ASCO) Model LB8300561U Actuates Feedwater Control Valves (V-4269, V-4270) Licer see Reference 1617 Required Operating Time: Short teru (SI signal) TER Checksheet No.1 Reference 59, Section 4.5.2.6 Licensee Submittal: Page 9 [62]; Table 3 Page 1 [1]; FRC SCEW 1 . DESI"** ION FOR DEFIC- "'8TIFIED BY TEM NRC SEE - CISCLED ITBt(S) ONLYs (See Section 3 of this TER for Legend) R, T, QF, Et, F, M, CS, A, S, (R), M, I, WI, RPN, EMN, SEN, QI, RFS, Mone, Not stated, Not applicable LISTING OF APPLICABLE CHERSEEETS: Contents checksheet Fese No. Equipment Item la Summery of Licensee Responses to the NRC SER lb Fquipment Environmental Qualification Summary Forme 2 Licensee Response to MRC SER 3a, 3b, 3c, 3d System Consideration Review 4a, oh, ec, 4d, de, 4f Equipment Environmental Qualification Review Se, 5b, Sc, 5d, Se, 5f, 5g, 5h, 51, 5j Installed TMI tassons Learned Implementation 6a, 6b Equipment Summary , M&intenance and Replacement Schedule Summary 7a, 7b, 7c Figure 3-1. Sample Checksheet Page la

                                                                                  " Equipment Item" 000 ranidin Research Center 4

A 08desen af N Frannen buseuse

TER-C5257-511 2 specifically identifies any qualification deficiencies determined by the evaluation and identifies the NRC qualification category to which the equipment item wcs assigned. A sample Checksheet 2 is presented in Figure 3-2. All information was reviewed for conformance to the NRC criteria referenced in Section 2 of this report. As requestad by the NRC, all appli-cable and available qualification documentation associated with the overall Equipment Environmental Qualification (EEQ) program was used by .he reviewers, whether referenced by the Licensee or not. Upon completion of the review for each equipment ites, an overall evaluation of the component and a specific conclusion with respect to its qualification was developed. Based on the evaluation, each equipment item was assigned to one of the generic qualification categories provided by the NRC. The NRC category descriptions are presented in Section 3.3 of this report. 3.3 NRC QUALIFICATION CATEGORIES AND DEFINITIONS o NRC Category I.a EQUIPMENT THAT SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES OR NUREG-0588, OR HAS ACCEPTABLE DEVIATIONS FROM THE DOR /NUREG CRITERIA I )' This category includes equipment items which are fully acceptable on the basis that all applicable criteria defined in the DOR Guidelines or i NUREG-0588 are (1) satisfied and the' equipment has been found to be

qualified or (2) sufficient information has been presented to determine j that deviations from the criteria are acceptable or insignificant.

  ~

o NRC Category I.b i EQUIPMENT FOR WHICH DEVIATIONS FROM THE DOR GUIDELINES OR NUREG-0588 ARE JUDGED CONDITIONALLY ACCEPTABLE PROVIDED THAT SPECIFIC MODIFICATIONS ARE MADE This category includes equipment itene that do not satisfy one or more of the applicable criteria defined in the DOR Guidelines or NUREG-0588; however, the Licensee has stated that specific modifications will be made on or before a designated date. . This equipment is considered by NRC to be conditionally acceptable provided that the specific modifications are made l by the Licensee. When the modifications are completed as proposed, the l Licensee states that the equipment will satisfy all applicable NRC l requirements. Examples of specific modifications are (1) replacement of unqualified equipment with qualified equipment, (2) equipment hardware A 3-8

                $"nW*EE

i TER-C5257-511 h NRCContract No.NRC4349118 HM Frenivan Rossamh Center PRC Preiset No. Cagy PeGe

A Dhama es N F=enn hohee FRC Aeolenment No.13 sgeandRoseSense6PMe Pe.19:0312tN44 ces 2 l PRCTasit No.

EQUIPMENT ENVIRONMENTAL QUNTION REVIEW OF EQUIPMENT ITEM NO. _ i EQUIPMENT SWIE0letBIFFAL QUALIFICATICII SGINARY FORN DESIGNATION: i NBC REQUZBEMEIPIB I = DEFICIENCY l Documented Evidence of Qualification Adequate Adequate similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately ~

Qualified Life or Replacement Schedule Established (If Required)

+ Progra'4 Established to Identify leging Degradation Criteria Regarding Aging simulation Satisfied (If acquired) Criteria negarding Temperature /F essure Exposures o Feak Temperature Adequate o Feak Pressure Adequate o Duration Adequate o acquired Profile Enveloped Adequately o Steam Esposure (If Required) Adequate Criteria Regarding Spray satisfied Criteria negarding Submergence Satisfied Criteria negarding Radiation satisfied Criteria Regarding Test Sequence Satisfied Criteria Asgarding Test Failures or Severe Ancealies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria negarding Instrument Accuracy satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-05SS, Cat. I) DESIGMATION: NRC QUALIFICATION CATEGORY I = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Estipment Emespt From Qualification III.b Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available Figure 3-2. Sample Checksheet Page 2

                                                " Equipment Environmental Qualification Summary Form" 0     ranklin Research Center A Oheolon of N Frenten ansunde

TER-C5257-511 modification, (3) equipment relocation above submergence level, '(4) 4 relocation or shielding of equipment from radiation source, L(5) verifica-

  ..          tion of qualification by additional testing, (6) equipment relocation to a mild environment, and (7) qualification testing of equipment in progress.

o ~NRC Category II.a EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION IS INSUFFICIENT TO ESTABLISH THAT THE EQUIPMENT IS OR IS NOT QUALIFIES IN ACCORDANCE WITH THE DOR GUIDELINES OR NUREG-0588 The qualification of equipment items in this category, in accordance with the requirements of the DOR' Guidelines or NUREG-0588, is significantly deficient or inconclusive based upon review of (1) the documentation provided by the Licensee or (2) applicable and available qualification

documentation associated with the overall equipment environmental qualification program. The qualification Jecumentation indicates signifi-cant deficiencies, which can be categorizea as follows: (1) appropriate documentation reflecting qualification has not been. cited and made available

for review by the Licensee and there is no knowledge of applicable docu-mentation; (2) the Licensee is awaiting qualification from the equipment vendor; or (3) the qualification documentation indicates significant deficiencies; however, where testing was conducted, no reported failures or

! severe anomalies were observed which would unquestionably affect the ability of the equipment to perform its design basis safety function (s). o NRC Category II.b - EQUIPMENT THAT IS UNQUALIFIED This category includes equipment items whose qualification documenta-e tion has been judged to be seriously deficient based upon review of (1) the l documentation provided by the Licensee, or (2) applicable and available l qualification documentation associated with the overall equipment ! environmental qualification program. The qualification documentation indicates serious deficiencies reported during testing; for example, severe , anomalies or failure of the test specimen, which could affect the ability I of the equipment to perform its safety function. NEC has requested immediate written notification when an equipment item is placed in this category during the course of the review. o NRC Category II.c EQUIPMENT THAT SATISFIES ALL APPLICABLE REQUIREMENTS OF THE DOR GUIDELINES OR NUREC-0588 WITH THE EXCEPTION OF QUALIFIED LIFE This category includes equipment items that are acceptable on the basis

             - that all applicable criteria defined in the DOR Guidelines or NUREG-0588 are satisfied with the exception of the qualified life criterion.       The Licensee (1) has not evaluated qualified life or replacement schedule, (2) has not adequately evaluated qualified life or replacement schedule, or (3) has not adequately intepreted qualified life in terms of calendar time.

[ Note r The component replacement schedule discussed in Section 7.0 of the 3-10 4Nb FranWin Remen:h Cemer A Ohmen of The FrenMn ineende >

TER-CS257-511 DOR Guidelines is, in effect, a qualified life. It is not essential to use the term " qualified life," but the replacement schedule must be justified.] o NRC Category III.a

EQUIPMENT THAT IS EXEMPT FROM QUALIFICATION This category includes equipment items that are exempt from qualification on the basis that (1) the equipment does not provide a safety i

function (i.e., should not have been included in the equipment list, submitted by the Licensee), or (2) the specific safety-related function of the equipment can be accomplished by some other designated equipment that is fully qualified and satisfies the single failure criterion. In addition, any failure of the exempt equipment must not mislead the operator

or degrade the ability of qualified equipment to perform its required' safety-related function.

, o NRC Category III.b EQUIPMENT NOT IN THE SCOPE OF THE QUALIFICATION REVIEW This category includes equipment items addressed by the Licensee in the equipment environmental qualification submittals which are (1) required to achieve and maintain the plant in a cold shutdown condition or (2) located in a mild environment. Supplement"2 of IE Bulletin 79-01B 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 high energy line break (HELB) or to nuclear radiation emanating from circulation of fluids containing radioactive substances. Supplement 3 of IE Bulletin 79-01B permits deferment of the review of environmental qualific.ation for all equipment required to achieve and maintain the plant in a cold shutdown condition. Supplements 2 and 3 of IE Bulletin 79-01B originally permitted deferment until af ter February 1,1981 of the qualification review of equipment located in a mild environment or required to achieve and maintain the plant in a cold shutdown condition. Since the issuance of Supplements 2 and 3, the NRC has determined that the review of environmental qualification for this equipment is not within the scope of this report. o NRC Category IV l EQUIPMENT FOR WHICH QUALIFICATION DOCUMENTATION HAS NOT BEEN MADE AVAILABLE FOR REVIEW This category includes equipment items for which qualification documentation in accordance with the requirements of the DOR Guidelines or NUREG-0588 has been cited by the Licensee as evidence of qualifica-tion; however, this documentation has not been made available for review. Therefore, a conclusion cannot be reached with respect to qualification of this equipment. nklin Research Center A Dhenson of The Fransen m

                                                                                                            - ~.

e l TER-C5257-511 3.4 IMPLEMENTATION GUIDE FOR FULFILLING NRC CRITERIA The NRC has requested that a detailed implementation guide for fulfilling NRC criteria be prepared as part of this assignment. The implementation guide will present a fully detailed discussion of the principal qualification criteria presented in the DOR Guidelines and NUREG-0588. The primary emphasis will be to clarify technical points, eliminate possible misconceptions, and clearly provide definitive guidance to enable licensees to understand and resolve, in an expeditious manner, qualification deficiencies identified as a result of this TER.' The implementation guide (TER-C5257-532) has been prepared and issued to the NRC. The implementation guide is either appended to this TER or will be forwarded to the Licensee by the NRC under a separate letter. The Licensee is encouraged to review that document. l l l i 3-12 000J Franklin Research Center A o m.onorTh.rrman m .

TER-C5257-511

4. TECHNICAL EVALUA1 ION

4.1 INTRODUCTION

The technical evaluation presented in this section represents the squipment environmental qualification (EEQ) assessment for each equipment item -listed in Appendix B in accordance with the methodology presented in Section 3 of this report. The evaluations were conducted to identify any major deficiencies within the Licensee's equipment qualification program and to datermine whether the Licensee (1) provided an adequate response to the SER concerns, (2) proposed adequate corrective actions to resolve qualification daficiencies, and (3) provided a schedule for completion of the corrective cetions. The evaluations are based on the available qualification documentation provided by the Licensee, complemented in several cases by other relevant tachnical information. The major qualification deficiencies that have been idsntified and the results of the evaluation are shown in the Equipment Environmental Qualification Summary Forms (Tables 4-1, 4-2, 4-3, and 4-4) prssented in Section 4.2. Observations concerning the Licensee's qualification methodology prasented in response to the NRC SER are presented in Section 4.3. Technical evaluations of the environmental qualification of the equipment =itzms are presented in Section 4.4. 4-1 M Ub) Franklin Research Cemer 4 Omsson of The Franen insatues

TER-C5257-511 4.2

SUMMARY

OF THE EVALUATION The following tabelations represent a summary of the results of the equipment environmental qualification evaluation conducted in accordance with the methodology presented in Section 3. Table 4-1 summarizes the number of equipment items assigned to each NRC qualification category as a result of the evaluation. Table' 4-2 summarizes the number of equipment items found to have a specific qualification deficiency. Table 4-3 summarizes the number of equipment items for which the Licensee has proposed a specific corrective action to resolve a qualification deficiency. Table 4-4 consists of Equipment Environmental Qualification Summary Forms for the equipment items, identifying (1) compliance with the qualification requirements defined in Section 2, (2) the resultant NRC qualification category, and (3) the Licensee-proposed corrective action. f I 4-2 dUdd Franklin Research Center

           ^ % anw. rr. nun %.

TER-CS257-511 TABLE 4-1 NUMBER OF EQUIPMENT ITEMS IN EACH QUALIFICATION CATEGORY NUMBER OF NRC CATEGORY EQUIPMENT CATEGORY DESCRIPTION ITEMS cason==========================================================ru=============== I.A EQUIPMENT QUALIFIED---------------------------------------- 6 ( EQUIPMENT ITEM N0(S).: 2, 3, 4, 26, 27, 28 1 I.B EQUIPMENT QUALIFICATION PENDING MODIFICATION--------------- 5 ( EQUIPMENT ITEM N0(S).: 19, 20, 21, 31, 32 ) II.A EQUIPMENT QUALIFICATION NOT ESTABLISHED-------------------- . 12 ( CQUIPMENT ITEM N0(S).: 1, 5, 6, 7, 8, 9, 10, 11, 18, 22, 23, 25 ) II.B EQUIPMENT NOT QUALIFIED------------------------------------ 6 ( EQUIPMENT ITEM N0(S).: 12, 13, 14, 15, 16, 17 ) II.C EQUIPMENT SATISFIES ALL REQUIREMENTS EXCEPT QUALIFIED LIFE OR REPLACEMENT SCHEDULE JUSTIFIED----------- 2 ( EQUIPMENT ITEM N0(S).: 29, 30 ) III.A EQUIPMENT EXEMPT FROM QUALIFICATION------------------------ 0 l III.B EQUIPMENT NOT IN THE SCOPE OF THE REVIEW------------------- 0 IV DOCUMENTATION NOT MADE AVAILABLE--------------------------- 1 ( EQUIPMENT ITEM N0(S).: 24 ) TOTAL 32 cocean=====s=====================================================xz============= l l l 4-3

        -eCh1, UOdd Franklin Research Center 4o- onorTw.rr w nm.au.

TER-C5257-511 TABLE 4-2 QUALIFICATION DEFICIENCY

SUMMARY

NUMBER OF DEFICIENT - EQUIP'4ENT NRC REQUIREMENT ITEMS 0n==============================================================================

1. DOCUMENTED EVIDENCE OF QUALIFICATION ADEQUATE---~~-------- 11

( EQUIPMENT ITEM N0(S).: 1, 5, 6, 7, 8, 16, 17, 18, 19, 22, 23 ) -

2. ADEQUATE SIMILARITY BEThEEN EQUIPMENT AND TEST SPECINEN ESTABLISHED--------------------------------- 10

( EQUIPMENT ITEM N0(S).: 7, 8, 9, 10, 11, 16, 22, 23,' 31, 32 1

3. AGING DEGRADATION EVALUATED ADEQUATELY-------------------- 19

[ EQUIPMENT ITEM N0(S). 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 22, 23, 25, 29, 30 ) '

4. QUALIFIED LIFE OR REPLACEMENT SCHEDULE ESTABLISHED (IF REQUIRED)--------------------------------- 19-

[ EQUIPMENT ITEM N0(S).: 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 22, 23, 25, 29, 30 1 >

5. PROGRAM ESTABLISHED TO IDENTIFY AGING DEGRADATION--------- 0

( EQUIPMENT ITEM N0(S).: 5, 6, 7, 8,' 16, 17, 22, 23 1

6. CRITERIA REGARDING AGING SIMULATION (17 REQUIRED)---------------------------------------- 4 ,

C SQUIPMENT ITEM N0(S).: 5, 6, 16, 17 ) i l 7. CRITERIA REGARDING TEMPERATURE / PRESSURE EXPOSURE: l . A. - PEAK TEMPERATURE ADEQUATE----------------------- 0

8. - PEAK PRESSURE ADEQUATE-------------'------------ 0 C. - DURATION ADEQUATE------------------------------- 3

( EQUIPMENT ITEM N0(S).: 16, 17, 25 ) D. - REQUIRED PROFILE ENVELOPED ADEQUATELY----------- 4 [ EQUIPMENT ITEM N0(S).: 16, 17, 18, 25 ) t

 =c=======================a======================================================

l l l l 1 4-4 d1d Franklin Research Center A Deween of The Frer*hn hsature

                                                                           .           TER-C5257-511-     l 1

.' ~ Table 4-2 (Co't.)n QUALIFICATIO?jDEFICIENCY

SUMMARY

NUMBER OF DEFICIENT EQUIPMENT NRC REQUIREMENT ITEMS snosos===== ====================================================================

E. - STEAM EXPOSURE (IF PEQUIRED) ADE00 ATE----------- 0

         ~

8. CRITERIA BEGARDING SPRAY SATISFIED ~~---------------------- 4

( EQUIPMENT ITEM NO(S).: 16, 17, 18, 25 )

                     ~
                                                                       ^

9. CRITERIA REGARDING SUBHERGENCE SATISFIED------------------

                ~

3

                      ' t EQUIPMENT ITEM N0(S).:                 13, 16, 17 1

10. CRITERId'3EGARDING RADIATION SATISFIED-------------------- 2

( EQUIPMENT ITEM N0(S).: J5, 61

11. CRITEFIA REGARDING TEST SEQUENCE 1 SATISFIED---------------- 8

( EQUIPMENT ITEM NOCS).:- 5, 6, 12, 13, 14, 15, 16, 17 ]

12. CRITERIA.REGARDING TEST FAILURES OR SEVERE ANOMALIES (IT ANY) SATISFIED---~~-----------------------~~------

4 L EQUIPMENT ITEM N0(S).: 12, 13, 14, 15 ]

13. CRITERIA REGARDING FUNCTIONAL TESTING SATISFIED-----------

                  ^                                                                                  3

[ EQUIPMENT ITEM N0(S).: 16, 17, 18 3 1

14. CRITERLA PEGARDING INSTRUMENT ACCURACY" SATISFIED----~~~~-- 6

[ EQUIPMENT ITEM N0(S).: 9, 10, 11, 16, 17, 18 1

     .15. TEST DURATION MARGIN (1 HOUR + FUNCTION IIME)' SATISFIED---
      '                                                                                              1

{ EQUIPMENT ITEM N0(S).: 6 ] LO. CRITERIA REGARDING MARGINS SATISFIED (NUREG-0588, CAT. 1)- 6 [ EQUIPMENT ITEM N0(S).: 12, 13, 14, 15, 16, 17 ) acaccsa=================================eh====================================== 4 4 4-5 MMU Fr sn'Jin Restarch Center . r

e. % aaerrh. r e ,a.oaa.

3 TER-c5257- 511' '

                                                                                        ., ' N TABLE 4-3 LICENSEE CORRECTIVE ACTION 

SUMMARY

                                                            /

t 14 UMBER OF CORRECTIVE ACTION EQUIPMEtlT .s DESCRIPTION ITEMS c===============================================================================- see

1. EQUIPMENT REPLACEMENT WITH QUALIFIED EQUIPMENT----------------- 0

2. EQUIPMENT MODIFICATION-------------------------------- ,=b------ 0 1 .-

1 - + 3

                                                                                                          ,                        w

3. EQUIPMENT RELOCATION ABOVE SUBMERGENCE LEVEL------------------- O' N

4. RELOCATE OR SHIELD EQUIPMENT FROM RADIATION SOURCE------------- 0

5. VERIFY QUALIFICATION BY ADDITIONAL TESTING / ANALYSIS------------ 0 5-3

6. EQUIPMENT RELOCATION TO A MILD ENVIRONMENT--------------------- 0 -

7. QUALIFICATION TESTING OF EQUIPMENT IN PROGRESS----------------- 4

( EQUIPMENT ITEM N0(S).: 20, 21, 31, 32 )

8. OTHER (FOR DETAILED DESCRIPTION SEE SPECIFIC EQUIPMENT ITEMS)-- 5

( EQUIPMENT ITEM N0(S).:

                                                                                                                               ~

12, 13, 14, 15, 19 J SCHEDULE FOR COMPLETION OF CORRECTIVE ACTION (S) HAS BEEN PROVIDED (SEE SPECIFIC EQUIPMENT ITEM FOR COMPLETION 3 ATE)--+----- 0 an==========================================================================='=== 4 k 4

                                                                                                                                         +

L 4-6 A l U$U4 Franklin Research Center om.on a n. n.ne,au. .- '

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                                    /              I Table 6-4. ,,
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EQUIPutNT FNVIRDM.F97AL QUALIFICAT!bN SUMPApf FORM

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   $3_.((               *l NRC REQUIPEWENTS                                     (tiESIGNATIONt E 3 DEFICIENfy)
                                                                                ...---*=-====.'=.----*===--... >

I i i t t l t i 1 1 3 l l 3 i  ! I t E ,- y;p .. ,  ! -..- ..==-=.-- i  ! I  !  ! 3 8 1 3 8 8 8 I 3 t I( 3 u . t 1. DOCUmFNTFD EVIDENCE OF QUALIFICATION ADEOUA1E-======== ,*========5 x i  !  ! 1X t I !X $X !  !  ! 1 1 1 e G$' t 2. IQFOUATE SIMILARITY BETmFEN ECHIPMFNT AND  ! I I t i I I I t t  ! I I t 'l . [g 8 Test SPECIMEN rs?AnLisnEn.-==-====--==-==-------===--==----*=-===t t t I t  ! x!x3x!x!x! t i I i , , r* I 3. A G I N G Df GR A D A T I ON E V A LU A TLD A Deus a!? 8-V ==---==-====-*===========* 3 1 I I tI 1I II IX $I II IX lX II 1I II I 3 4. QUALIFIED LIFE OR PEPLACEMENT SCHEDULL 1 1 8 8 8 8 3 1 8 i si t i l 8 i {g o3 f i EstAnLISHED (Ir BE0UInED)==.---===-==--== --*==-=----==.-=-======3  : I  ! $x: x 8 x ! x 3 xd: x!x: x8x!x: x! ,,

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  *3                       4     5. P90GRAW ESTABLTSMED TO IDENTIFY AGING DEGRACATION===========--===8                                 8    8   3     3X ! I tI IX 3                   3     3      1    3 I

8 i 8

• t 6. CRIVEpaA RFGARDING 4GING SIMULATIDN SATISFIED (IF REQUIRED)======8 8 i !I IX I I I I i i  !  !

                           ! 7. CRITERI A REG 4RDING T6MFLR ATURE/ Ppt 55URE EXPOSURCI ;                             ,           I     t   e    l     8     i    i     i     3   3     8     I      I    t  8     I                       ,

8 A. - FLAR TEMPE1ATURE ADL0UATE*===========**==qr-?-*==----==t I I I I I I I I t  ! 'I t  ! I I t 8. - FEAR PREF 30pt ADEQUATE =======-====-========**==========3 I $ 8 I l 3 1 4 i  !  !- I 1 l J j* 3 C - DUWATION ADE00 ATE ===========-=**==============*========8 8 8 8 i  !  !  ! 1 l l 8 't' t 1 .1, ' ,

                                                                                                                                                                                                                                    / , *I              ,

8 i D. = REQUINED FROFILE ENVELOPED ADE0UATELT==================l E. - STEAN FIP03URE (IF REQUIRED) ADE004TE==================8 8 8 8 1 I 3 i 1 8 1 8 8 l# t 3 1 i 3 3 1 1 1 1 4 1 8 t # t 8. CRITFRIA REGAPDING SPRAY SATI5FIED=======================0=====--! 3 I l ,I l' I 1' t 1 3 8 1 3 8 i r., I 9. CRITERIA PFSAEDING SummFPGENCE 8ATISFIFD================**=======8 1 3 8 I I t  ! t l 8 I I .8 s t 10. CR ITER I A PFG A R D f 4G B A DI ATION S A TI5 PIED =======***== ======= ?=i i=== l 1 3 8 II II I I i  !  ! I i 3 I I e i St. CRITERIA REG 4f0!NG TFST SROUFhCE SATF5FIED==========-========**==$ 8 i  ! tX 3I t t i i I 3I II tX 3I ! g, I $2. CRITERIA REGARDIN -sEST FAILURF5 GB' SEVERE ANOMALIES l 3 8 I t I i i i  ! 3 l l 3 8 8

             ,            I                (IF ANT) 64715FIED===*--=======*===============--============8                             8    8   8     8     I    I     t     t   I      t    31 1X !x!X 8
            %a            i 33. CRITgaga RFGARDING FUNCTIONAL TESTINJ SATI5FIED==================l                                    3    i   !     !     I    I     i     i   1      3    8      I    l  t     !

I 14. CRITERIA REGARDING INSTRUPENT ACCUBACT SATISFTED=================t t  : I t 3 1 3 4X tI !X i 8 8 8 I i 15. TEST DURATION MARGIN (I HOUR + FUNCTIOE TIMEF8ATI2FIED=-========l i t  ! I 3X i  ! I t  ! I I I t i i 16. CpITERIA PEGANDING MARGINS SATISFIED (NUREG-0588 CAT. 1)======-el  ! I  ! t I I I I I i y 8A fI tX! mass.a.......sss e.ss. .sses.es..es sssss es. essa.a.a ss es ..es.a.sma.s.m. asses.essnes..as.essemos..ssenessess...sssa. essa.es.esa.. sses I NkC QUALIFICATION CATEGORY (DESIGNATION: I e CATEGOFT)  ! I i 1 1 1 1 I i  !  ! l I  ! I I --=--============--===-=== ===========--=========-**-- I e 3 I  !  ! I 3 I I I 1.4 EQUIPMFWT 0UALIFIED====-=====-===========================-===3 43 3X IX 1 l 3 1 1 g 3 3 1 3 l t i 1.8 EQUIPMENT nUALIFICAfl0N PENDING MODIFICATION ====v============8 8 .  !  ! 1  ! l 8 l t  ! I l i*

                           ! II.A          EQUIPMENT OUALIFICATION NDT ESTABLI5MED===================*--I X !                              !   I     tX II I2 3x!X IX II I                         t    I  1     1 I II.B          EQUIPMENT NOT 0UALIFIED=======--=========-=================--I                             !    !   !     !     !    I     i     1   8    *t         I II tI tX t t II.C           FOUIPMENT SATISFIFS ALL pt0UIREMFhTS EXCEPT                                           I    1    8   t     t     3    8     8     8   3      I    I      I    t  I     !
                          !                OUALIFIED LIFE OR DEPLACEMENT SCHEDULE JUST!FIFD=======-=====t                             !    I   3     4     4    3     8     l   3      3    3      3    l  t     t I     III.A EQUIPMFNT EXEMPT FROM 0UALIFICATION=----=========-=== y===---!                                 i    3   4     I     I    3     8     l   t      !    I      t    !  I     I I !!!.B EQUIPMFNT NOT IN THE SCOPE OF THE DEVIEN==========--=========l                                      t    i   !     3     8    1     3     3   I      I    t      I    t  l     l 3 IV             DOCffMENTATIOd MUT NAPE AVAlt.A9fE=========*-==================l                           !    8   3     I     I    t     t     t   t      I    I      t    t  !     3
                          ..s s a...... .a s s.          ......s..s s s.a s..ss e..a s s..ss e........s.e s s e....s. .s s e.a se s.s s.s.es s.a s.. ..s.a..s...s..ss o s ss e s..ss e ne s as s e s.a.m.m.                         ;g I CDRpFCTIVE ACTION SPFCIFIED                         (DESIGNATInN3 X . ACTtDN SPECIFIED) I*                t    t   l     t     t    3     3     3   3      I    t      3    3  3     3                  po
                               ======-**=-=====-=---==--==                      ------=---==----------------*=-=-==                   t    I   I     t     !    I     t     3   :                  :    :  t     t                   I t     I                  f3 i 1. r0UIPMENT PEPLACFMENT WITH QUALIFIED L0DIPMENT===================t                                     I    !   !     !     !    !     I     t   !      I    I           !

8 2. EQUIPMFNT MUDIFICAT10N=--===========-==================-======*-=3 I 3. EQUIPMENT RELOCATION AROVE THE SUB8LPGENCE LEVEL ==-==========-===t 3 8 8 I I 1 l 3 3 1 I 8 l 8 t 8 8 I $ 8 3 I 1 l 3 t

                                                                                                                                                                                                                                     ]

(n 1 4. RELOCATE OP SHIELD EQUIPMENT FROM RADIATION S0UpCE=====--========t I t i  !  ! I I I i I l t 3 3  ! %J l 5. VERIFT GUALIFICATION BT ADDITIONAL TESTING / ANALYSIS--============l 1 8 8 8 8 8 8 1 1  !  !  !  !  ! l 1 I t  !  ! I t i l I I Ln 1 6 EQUIPMENT DEf0 CATION TO A MILD FNVIRON4FMT===============-=======8 8  ! 1 g g 1 7. QUALIFICATION TESTING OF EQUIPMENT IN Pp0GRESS---*=====--========l 3 I t l l t 1 1  ! I I  ! I t  ! [$ 1 8. OTHER (--.SEE SPECIFIC EQUIPMENT ITEM IF CHECKED )==--=========!  ! I t  ! I  !  ! t I I !X tX 3I tI I I l I 1  ! I I I  ! I I t  ! I I  !  !

                          ! SCHEDUIE FOR COMPLETION OF CORRECTIVE ACTIO4(S) HAS BFEN PROVIDFD===f                                     8    1   !     !     !    !     I     t   !      I    I      I    I  3     3 mass.asssas.msomassa.s..ssamassa.s. ass.ssssssssssses.asssas.ssassas...s.es.m.ssssssssssssssssa.esassassessesasssse.asssamassessa.es.

t Table 4-4 (Cont.) FOUIPMENT ENVIDDNMENTAL 004ttFICATInN SUMMART FDRs (( sesassomassessamassassesssssssssssssssssssssssssas

            ,EU.y                                                                                                   sensemassenessnessnesassenessa.essssssssssssssssssssssssssoas g                                                                                                     I                     fpC FOUIPPFd? ITFN NUNRESS                          4 3                                                                                                     sassssssssssssssssssssssssssssssssssssssssssssssssssssssssses 2[                                                                                                    1016:017303030393020 n2310223023302420253026t0278020302980304 gy       sessssssssssssssssssssssssssssssssssssssssssssssenesssssssssssssssssssssssssemassessassassammanusssssmassumessamesassemassensssemens t NRC pt00!PEsENTS d 30                                                             (OESIGNATION I e DEFICIENCTI           (     l  l    8    8      1   1    1  3   3      3    3    3    1    3    3 su       I =====-= ========                                      ======--=====*----===========          1     1  3    3    1      3   3   t   t   t      t    !    I    t    i    I m$       3     1. DOCUMENTFD EVIDENCE OF QUALIFICAfl0N ADE0UATE====================g                       I lI gI II l           3  3I II g      3      g              g    g    g 4             y      8     2. ADEQUATE SINILARITT BETNEEN EQUIPMENT AND                                             I     I  I    I    I      I  3     3  3   3      3 i

3 i I i 1 1 n i TEST SPECIPEN ESTA8LISHED=-*====-================================l I l  ! l 3 3 1I II I l 3 3 1 1 3 3

,           y :7     3     3, aggNG DEGRADATION EVALHATED ADE0UATELT**=***=====================t                        I II II I       4     4   8I I I !    II I        t    i    !I  II 1-g {}     t     4. QUALIFIFD LIFE OR REPLACEMENT SCMLDULE                                                l      I  L   i     1     1  3     3  3   1      I    I    I    I    !    3
            ,E3      1 ESTABLISNED (IF REQUIRE 01========*==============================-3                 3 3I 1I I       I     I   II II I     II t        i    3    II  II I p      1     5. PROGRAN ESTApLISHED TO IDENTIFT ACING DEGBADAT!0N===*============l                       I lI l     5     1     8   1I II t     i      I    I    I    I    t    4                       i

• I 6. CRITERI% REGannING AGING $1MULATION SATISFIED (IF DEOUIRED)--====t I II I I t  ! t  ! t I I I 3 3 I I T. CRITERIA REGARDING TEMPERATURE /PPESSURE EXPOSURE: 3 3 3 5 8 I I I 3 I I i 1 1 I I I A. - PEAK TEMPEpATURE APT 0UATE======*-=-==-=================l 3 1 1 1 $ l 1 3 3 3 3 I t t .

                     !                         8

• PEAK PRESSURE ADE00 ATE =**==========*===================t i 3 8 8 8 8 I I I 8 I i t I i

                     !                         C. = DURATION ADE0UATE======*====*==*=======*========*======l           I II 1     1    1     1   1    1   I   II I        I    I    i    !    3 I                         D. = REQUIRED FROFILE ENVELOPED ADE0UATELT==================t           I II II   I     I     I   I    I       1I I        i    :    t    t    i
                     !                         E. = STEAN EXPOSupE (IF REQUIRED) ADEQUATE ==================8             3  I    I    I         1    1  1    3     3     3         3        3 8     8. CRITERIA ArGARDING SPRAF SATI3FIED===============================1                       I lI lI   l     l     1   l    l  I   II I         I    i    t    1    i I 9. CRITERIA RFGARDING SUBNERGFNCE SATISFIED =*=======================t                          I II I     I    I     I   I    I  I    t     t     3    i         I    3 8 10. CRITERIA REGARDING DADIAT10N SATI3FirD===========*-==========*===t                             i  3    I    t     3   3    3  3    I     I     I    !    i    i    i i 11. CRITERIA REGARDING TEST SEQUENEE 3ATISFIED========---============8                          I II I     I    I     I   I    I  3   3      :     1    I    I    I    t to I $2. CalTERIA ptGARDING TEST FAILUBES OR SEVERE ANONALIES                                     I     i  l    i    l     i   I    I  I   I      I     I    I    I   I     t i I                        (IF ANY) SAT!3FIED=======================*===**=======*======3              3  3    3    3     i   t    I      3      3     i 00                                                                                                                                     i                     3    3   3     3 t II. CRITERIA REGARnING FUNCTIONAL TESTING SATISFIED-=================t                          I II lI 1       l     l   !    !  3   I      I    I    1     l    t   3 3 14. CRITERIA REGARDING INSTRUMENT ACCURACY SATISFIED================-t                          I II II I       t     3   i    !  3   l      t    t     t    t   t    3 i 15. TEST DHRATION NARGIN (t HOUR + FUECTION TINF) 3ATISFIED==========l                             I  t    3    3     3   3    3  3   I      I    i     !   3    3    3 8 16. CalTERIA REGARDING MARCINS SATISFIED (NUREG=0500. CAT. 1)========l I 1I i                              1    l     I   i    i  t          I    I    I    3    3    I a s s en s e n e s s m u s s s e n es sa m a s ss ss s s sss s s s ss ss s sss s ss s s sss sss s s ssss s s s ssss s s s s ss s ssss        ss ss s s s s s e s es s oa s s s s s ss ss ss s!

ssssssssssssssssssssenes 8 NPC OUALIFICATION CATECORY (DESIGNATIONI I e CATEGOST) I t t t t i 3 I l i 3 I t t l 3 4========...=============== ==========.......===.====== 3 g g i 8 I g g g g g g g g g i I.A EQUIPNFNT 0UALIFIED==========================================l 8 8 1 3 1 1 3 I I 3I II II I i t

                     ! I.5                    EQUIPMENT GUALIFICATION PENDING MODIFICAT10N=================t              i  I    II 3I II 3          8  I   J      t    3    3    3    3    3 8     II.A               EQUIPPENT CUALIFICATION NOT FSTABLISMED======================t              i  3I I      t     l   8I II I     II I        l    l    1    3    3 3     11.5               EQUIPMENT NOT 0UALIFIED===--=================================l I II l               3    3     I   I    I  3   3           i    i    g    i    3 8     II.C               EQUIPMENT SATISFIES ALL pE0UIREMENTS EXCEPT                           l     t  8    I    I     i   t    t  t   I      I    I    I    I    I    3 I                        OUALIFIED LIFE OR REPLACEMENT SCNEDULE JUST1FIED=============l              l  t    i    l     i   !    I  I   I      I    I    I    3I  II   I I III.A EQUIPMFNT EIEMPT rp04                         0UALIFICATION==========================t       8  I    I    I     I   I    I  I   I      i    i    t    i    I    I I III.8 EQUIPNF47 NUT IN TMC SCOPE OF THE REVIEb=====================t                               t  I    I    I     t   3    8  8   I      t    t    i    t    t    3 I IV                     DOCUMENTATION NOT MADE AVAILASLE=============================l              l  I         I                 II t       I    I         3-l           1   4    3 samassesse massessassamassuammesassessssssssssssssssumassomassssanassessemassmesmesssemssesseessamsamssonessemassessesssssessasssenes                    3         3    3           pg pg i CURRECTIVE ACTILM SPECIFIED                           (DFSIGNATIONS I a ACTION SPECIFIED) I        t  t   i     l     i   I    I  i   1      1    1    3    3    3    3           pd 1 --==== ===================                            ===-==============-==---=====-====- t        3      :               3    8      3      3    3    I    3    8    I            8

1. EQUIPNzMT REPLACEMlNT NITH OUALIFIED EQUIPhENT-==================$ l 1

l 2. EQUIPMENT N0DIFICATION-======================================-. =1 1 1 I t 1 I 1 i I 3 I t t 3 I I I l-l t 3 8 I 8 g ( pa 3 3. FOUIPMENT RELOCATION AROVE THE SURhERGFhCE LEVFL=================8 3 1 3 3 3 3 3 I I I I 3 3 3 3 Ln 4 4. RELOCATE OR SHIELD EQUIPMENT FROM RADInff04 SOURCE===============3 I I I I I t t t t t 3 3 3  : I 'J I 5 VERIFT GUALIFICAftDN ST ADDITIOhAL TESTING / ANALYSIS =============3 3 8 3 3 I I l 8 3 3 I I I I t I t 6 FOUIPMENT REl,0 CATION TO A PILD ENdIRonsENT=======================l- t I T. QUALIFICATION TESTING pr EQUIPPENT IN PROGRES$===================3 1 3 3 3 8 3 3 3 3 3 1 I t g f$ 1 1 3 !I II i ;l i I 3 I I I t >e

8. OTNER (-= SEE SPFCtric FAUIPMENT ITEN IF CNFCAED---)===========--t 3

1 i I II I I I I I I I I t t t t

                     !                                                                                              t     I  3   5     3     3   8    8  8   i     I     i    t    i    t    t t SCHFDDLE FDM C0"Pf.EftDN OF CURRECTIVE ACTION (S) HAS BEEN PROVIDFD===t                            8  i   i     t     i   I    I  I   I     3     3    3    3         I seemssessnessasseressesassasassassassassessamassassammassassassumsmasammassansmessammasassenessemassammassassessassaammassamasassses

Table 4-4 (C:nts) SEs F018tPMENT ENVIRONNENTAL QU ALIFICA rloN SUusARY F0pm sg32 sessoassenmassessammessssssssssssssamassessessesas

 %                                                                                                                                 asessasseossosassessamassmemassessmammessnessassesssssesasona y  /

I FNC EQUIPsFNT ITER NHERFRS I 2[ sesesssesosessansammasassoassenessassessessessemassammessesse g!i 803130321 1-4,3 sesessessnesseseassassa amassessessassessessoasssammessassomassesessemosessassessosssenesessssassessemasssesammensasessanssassoasses s I WRC REQUIREMENTS (DESIGNATIONS I e DEFICIENCT) i I I i 'MH i ================ ============================= 1 8 8 I 1. DOCUFFNTED EVIDENCE OF QUALIFICATION ADE0UATE====================l I t t 5 3 2. ADEOUATE SINILARITT SETWEEN EOUIPMENT AND l 8 1 8 y :T I TEST SPECINEN FSTA8LISHED========================================8 3 4X 1 3 [(} g3 I 3

3. AGING DECRADATION EVALUATED ADE0UATELT*=====**===================8

4. QUALIFIED LIFE OR REPLACEMENT SCHEDULE I 8

i 8 i 3 t p i ESTABLISMED (IF RE0UIRED)========================================l I $ 1

 '         I   5. PROGRAN ESTABLISMED TO IDENTIFT AGING DEGRADATION================8                                                     I       I                                                                                          I I   6. CRITERIA REGARDING AGING SIMULATIDW SATISFIED (IF RE0UIRED)======l                                                      i      I                                                                                          i 3   7. CNITERIA REGARDING TEMPERATURE / PRESSURE EXPOSURE:                                                              I     I       I                                                                                          I i                 A.

• PEAK TFmPERATURE ADE0UATE=================' ===========8 4 I l 8 8 - PEAK PRESSURE ADE0UATE=================================8 8 4 3 i C. - DURATION ADE0UATE======================================8 I I I 1 D. = REQUIRED PROFILE ENVELOPFD ADEOUATELT==================8 I I $

3 E.

• STEAN EXPOSURE (IF REQUIRED) ADEOUATE==================8 I I i I 8. CRITERIA REGARDING SPRAT 8ATISFIED===============================8 8 8 8 8 9. CRITERIA REGARDING SUSWERGENCE SATISFIED =========================8 8 8 I i 10. CRITERIA REGARDING RADIATION SATISFIED ===========================8 8 I- 1 S> 1 St. CRITERIA REGARDING TEST SE0utNCE SaflSF1ED=======================8 2 3 3 I i 12. CRITERIA REGARDING TFST FAILURES OR SEVERE ANONALIES $ $ 8 3 W3 8 (IF ANT) SATISf!ED===========================================8 8 4 3 8 13. CRITERI A REGARDING I UNCTIONAL TESTING S ATISFIED================== 8 I l 8 I 14. CRITERIA REGARDING INSTRUMENT ACCURACT SATISF1 eda ================l  ! I t i 15. TEST DURATION NARGIN (1 MOUR + FUNCTION TIME) SATISFIED ==========t i I t i 16. CRITERIA prGARDING MApCINS SATISFIFD (NUREG= esse, CAT. 1)========t i I I sessmassosssenesessemass===sessemassommessnessassasenesses ssessas sessemassessnesene amesmessessess ms.ame. ass..s.es.amesessammense i NRC QUALIFICATION CATEGORY (DESIGNATION: 3 e CATEGORT)' t I I I l ========================== =========================== 1 3 g g 8 I.A EQUIPMENT GUALIFIED==========================================g i  ! I I I.B EQUIPMENT GUALIFICATION PENDING N0DIFICATION=================I X tI I 'I II.A EQUIPMFNT GUALIFICATION NOT ESTA8LISHED======================8 8 I I I 11.0 EQUIPMENT NOT OUALIrigD======================================4 3 4 8 I II.C EQUIPMENT SATISFIES ALL REOUIREMENTS EXCEPT I i t  !

I OUALIFIED LIFE OR RFPLACENEkT SCNEDULE JUSTIFIFD=============8 I I t i III.A EQUIPMENT FIEMPT FROM 0UALIFICATION==========================t 8 8 8 3 III.B EQUIPMENT NOT IN THE SCOPE OF THE REVIFN=====================8 I I I ,4 I IV DOCUMENTATION NOT MADE AVAILABLE=============================t $ 8 8 pq s maa s sa m m as s m aa s ss sa m ane a s s s m e e s s e ma s s o mm e s s enes s a s s a m a s a m o s ssa asses s m a m e m a s e s s em an e sse s m e ss as se s e m es se m a s s e ne ss uo m es ene s s e s s m e s es s e pa t CORRECTIVE ACTION SPECIFIED (DESIGNATIONg X e AC?!ON SPECIFIED) ! I I I I i =========================== =================================== 1 , 3 , gg i 1. EQUIPsENT REPLACEMENT NITH OUALIFIED E0UIPMENT*==================$ $ 1 I g3 1 2. EQUIPMENT MODIF1 CATION =========================a=================4 I t 3 (n 3 3. EQUIPMENT DELOCATION ABOVE THE SUePERGENCE LEVEL =================t i t t 'J t 4. RELOCATE OR SHIELD EQUIPMENT FR0s RADIATION SOURCE ===============8 8 I I I I 5. VERIFY 00ALIFICATInN ST ADDITIOhAL TESTING /ANALISIS-=============t i 1 I h3 3 6. EQUIPMENT DELOCATION TO A MILD ENVIR0NMENT=======================$ I 3 8 pa I T. QUALIFICATION TEbTtNG OF EOUIPMENT IN PROGRESS===================l X !X l 8 8 8. OTHER (===SEE SPFCIFIC EQUIPM NT ITEM IF CHECKFD ==)=============t t 3 ,I I I I $ I

           $ SCHFDULE FOR COMPLETION OF CORRFCTIVE ACTION (S) HAS REF.N PROVIDFD===5                                                      8      1                                                                                          3-seamassessesassssssssssenessammassessssssssssssssssssssssssssssssassumssummassmamasemassoassessassassnessnessassenssmassassammessses e
                                                                      . _ _                                         M '          %

r

                                            .                           TER-C5257-511 ~

4.3 METHODOLOGY USED B,Y THE LICENSEE This section includes observations concerning the Licensee's. qualification methodology presented 'in the response [20] to the NRC SER. 4.3.1 Completeness of Safety-Related Equipment List Section 3.1 of the NRC SER [16] identified the following concern:

              " Display instrumentation which provides information for the. reactor operators to aid them in,the safe handling of the plant was not specifically identified by the licensee. A complete list of all display instrumentation mentioned in the LOCA and HELB emergency procedure's must

{' be provided. Equipment qualification information in the form of summary sheets should be provided for all components of the display instrumentation exposed to harsh environments. Instrumentation which is j not considered to be safety related but which is mentioned in the emergency procedure should appear on the list. For these instruments, (1) justification should be provided for not considering the instrument . safety related and (2) assurance should be provided that its subsequent failure will not mislead the operator or adversely affect the mitigation of the consequences of the accident.- The environmental qualification of post-accident sampling and monitoring and radiation. monitoring' equipment is closely related to the review of the TMI Lessons-Learned modifications

   !          and will be performed in conjunction with that review."

In response to this concern, the Licensee stated [20]:

              "The reference to display instrumentation requirements within the SER appears to limit the current need to instrumentation within the harsh environment and/or as mentioned in the LOCA and HELB emergency?

procedures. Instrumentation within harsh environment would be limited to those transmitters, switches, and RTD's already reported on SCEWS. i At present, CP&L is to develop new Emergency Instructions. incorporating i TMI emergency guidelines as 'part of a TMI action item requirement. These new instructions are scheduled for 1983 implementation. When reviewed and accepted for plant operational use, they will be reviewed for components and display instrumentation within plant harsh environment.

If new instrumentation is required to meet these emergency procedures or i if additional instrumentation is referenced by these procedures, a list will be compiled and SCEW's'provided to the NRC."

, It is concluded that the Licensee has satisfactorily responded to the SER r concern. 4-10 _nklin Rese_ arch,_ Center .

TER-C5257-511 4.3.2 Environmental Service Conditions 4.3.2.1 Containment Spray System Section 3.2 of the NRC SER (16]-identified the following concern:

                  " Commission Memorandum and Order CLI-80-21 required that the DOR guidelines and the 'For Comment' NUREG-0588 'are to be used as the .

4 criteria for establishing the adequacy of the safety-related electrical equipment environmental qualification program. These documents provide the option of establishing a bounding pressure and temperature condition based on. plant-specific analysis identified in the licensee's Final Safety Analysis Report (FSAR) or based on generic profiles using the

                . methods identified in these documents.

On this basis, the staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes relative to the temperature, pressure, and the containment spray caustics, has been performed in accordance with the requirements stated above. The staff has reviewed the qualification documentation to ensure that the qualification specifications envelop the conditions established by the i licensee. During this review, the staff assumed that for plants designed and equipped with an automatic containment spray system which satisfies the single-failure criterion, the main-steam-line-break (MSLB) environmental conditions are enveloped by the large-break-LOCA environmental conditons. . The staff assumed, and requires the licensee to verify, that the containment spray system is not subjected to a disabling single-component failure and therefore satisfies the requirements of Section 4.2.1 of the DOR guidelines." In response to this concern, the Licensee stated [20):

                 "The SER requires the licensee to verify that the containment spray system is not subjected to a disabling single-component failure and therefore satisfies the requirements of Section 4.2.1 of the DOR

! Guidelines. H. B. Robinson FSAR Section'6.4.3, Design Evaluation, l describes the capabilities of the containment spray system and addresses j the single failure analysis for this system within Table 6.4-4 entitled, Single Failure Analysis - Containment Spray System, (see Appendix A). As this system is not subject to a single component failure affecting its performance, the MSLB accident environment is not the limiting parameter for qualification per the DQR Guidelines Section 4.2.1. To further support this conclusion, a study performed for'NRC IE Bulletin 80-04, Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition, indicates a maximum containment pressure of 34.4 psig and a . temperature of 257'F for the feedwater augmented MSLB." It is concluded that the Licensee has provided a satisfactory response to I- the NRC concern. 4-11

.r$3ds bObd Franklin Research Center Ao,-nasn.r mnau.

4 TER-C5257-511

              - 4.3.2.2              Temperature, Pressure, and Humidity Conditions Inside Containment
                     .Section 3.3 of the NRC SER [16] ider.tified the, following~ concern:
                      "The licensee has provided the results of accident analyses as 'follows:

Max Temp (*F) Max Press (psig) Humidity (%) LOCA 265 42 .100 MSLB not provided not provided 100 The staff has concluded that the minimum temperature profile used in the specifications for equipment qualification purposes should include a margin to account for higher-than-average temperatures in the upper F regions of the containment that can exist due to stratification,

especially following a postulated MSLB. Use of the steam saturation

;.                    temperature corresponding to'the total building pressure (partial pressure of steam plus partial pressure of air) versus time will provide                                                              -

an' acceptable margin for either a postulated LOCA or MSLB, whichever is

controlling, as to' potential adverse environmental effects on equipment.

4 The licensee's specified temperature (service condition) of 265*F dose not satisfy the above requirement. Furthermore, the licensee's specified pressure is low as compared to plants of similar design. The licensee is requested.co verify that the pressure profile in the FSAR was calculated 4 based on the Code requirements defined in NUREG-0588. If by using these codes the peak containment pressure is still 42 psig, then a saturation temperature corresponding to the pressure profile (289'F peak tempeature

at 42 psig) should be used. If, however, the calculated peak pressure is

,                    higher.than 42 psig, the saturation temperature corresponding to the new pressure profile should be used. The licensee should update his equipment summary tables to reflect this change. If there is any' equipment that.

, does not meet the staff position, the licensee must provide either s justification that the equipment will perform its intended ~ function under j the specified conditions or propose corrective action." In response to NRC concern, the Licensee stated [20]:

                     "The SER questions the pressure value as stated in our submittals and found within the H. B. Robinson FSAR. Apparently, a comparison with other plant's specified pressure values is used as the basis for this l                     questioning. As reported in our prior responses to IE Bulletin 79-01B, the H. B. Robinson containment volume is 2.1 X 106 ft 3 This effectively accounts for both a lower pressure value and radiation level when defining LOCA parameters. Therefore, it is not practical to use

! comparisons in determining H. B. Robinson adequacy. Our TSAR has been i reviewed by the U.S. Atomic Energy Commission and after several' exchanges l requiring amendments to this document, a Safety Evaluation Report was ! issued on May 18, 1970 accepting the LOCA evaluation as presented for

operation. Further review of LOCA conditions was performed by the AEC-i 4-12

,i _r nklin _.m.Res_earch.~. Center l

E 4

;                                                                                                     TER-C5257-511' i'             when the-plant requested permission to increase _ power. A Safety                                           ,
 !             Evaluation' Report was issued on May 20, 1974 accepting the LOCA conditions
 ;             and approving power increase. _ Per the DOR Guidelines Section'4.1.1, Service Conditions Inside Containment for a Loss of Coolant Accident j              (LOCA), Temperature and Pressure Steam Conditions, the FSAR analysis for

. containment temperature and pressure conditions is used for establishing _ thel qualification of electrical equipment located within containment. The service condition analysis was performed by Westinghouse Electric i Company.and the method utilized was reported to the AEC and subsequently I enclosed-as a Status Report by the Directorate of Licensing, dated October 15, 1974_within the Safety Evaluation Report by the Directorate of Licensing, U.S. Atomic Energy Commission for CP&L H.B. Robinson Unit

               #2,-dated December 27, 1974. (See Appendix B, Westinghouse ECCS Evaluation Model).

d- Of further note, the H. B. Robinson calculated maximum pressure associated with a double-ended break is 38 psig (peaking at 12 seconds after LOCA and reducieg to 32 psig after 3000 seconds). The stated 42 psig within our IE Bulletin 79-01B responses refers to the containment design i pressure; therefore, a margin of approximately 11% above the conservative value of the blowdown peaks is available. H. B. Robinson Unit 2 FSAR, Section 14.3.4, Containment Integrity Evaluation, contains data and parameters associated with containment pressure. See Figure 14.3.4-2, l Containment Pressure Transients for a Range of Break Sizes, Figure 14.3.4-4, Structural Heat Transfer Coefficient and Figure 14.2.4-6, Containment Capability Study, All Available Energy, for graphic I presentation of H. B. Robinson LOCA profiles. l Per the above, we do not believe it is justified to recalculate the LOCA pressure and temperature profiles. The conservatisms involved with the values and the tested values for equipment as recorded on the System

Component Evaluation Work Sheets indicate there are no conflicting or i questionable pressure and/or temperature' values involved.

t Addressing' stratification within Containment, the upper regions where stratification may affect temperature do not contain any instrumentation or equipment related to IE Bulletin 79-01B. Only the containment fans , are located on the' crane deck level (elevation 275') and their test temperature exceeds LOCA temperature by 16% (11% if the saturation [ temperature associated with LOCA is considered)." l It appears that the Licensee has not resolved the NRC concern. Since the Licensee is responsible for identifying the environments, the parameters 1 i' idsntified by the Licensee have been used in the evaluations contained in this + Tshnical Evaluation Report. These parameters are reproduced in Appendix A. i l l'

. 4-13 1 adC218

.            Edli Franidin Research Center

j. A cw=n a N n.run m.uw.

l

                                                                                                              . __-     .-     .       _      m -           ..
                                                                                                                              . TER-C525 7-511' i

4.3.2.3 Temperature, Pressure, and Humidity Conditions Outside Containment-

                              ..Section 3.4 of'the NRC SER (16] identified the following concern:
                                "The licensee has provided the temperature, pressure, and humidity associated with an-HELB outside containment, as well as applicable radiation levels associr*ed with equipment in the proximity of
                              -recirculating fluid lines.                                         The following area outside containment has                          ,

l. 1-been addressed: (1) Auxiliary building The licensee has used ambient temperature conditions in some areas outside containment. The staff considers saturation temperature at the , peak pressure resulting from a HELB as the minimum level for acceptance. The licensee should update his summary tables to reflect this change. If !- there is any equipment that does not meet the staff position, the I licensee must either provide justification that the equipment will perform its intended function under saturated conditions or propose corrective action." 5' In response to the NRC concern, the Licensee stated [20): -

                               "As stated in the SER, ambient temperature conditions'have been used in some areas outside containment. As H. B. Robinson 2 has master listed equipment located on the turbine deck which is an open air area, it is impractical an to utilize an arbitrary value such as ambient saturation

} temperature for qualification purposes. Therefore, the System Component Work Sheets listing turbine Deck Area location will not be summarily } revised. ! Considering the Auxiliary Building, the following quote from the Report l entitled: H. B. Robinson No. 2 Postulated Pipe Failure Analysis Outside of Containment, Section 10.0 Description of Compartment Environmental

Effects Analysis, indicates only one enclosed volume subject to pressure 2

and temperature buildup following rupture. This is the pipe penetration gallery. An analysis indicates a calculated pressure buildup of 0.2 psi and a maximum temperature - increase o_f 2.4*F. This consequence is the , result of the limiting postulated steam generator blowdown line rupture. These limiting environmental conditions will have no effect on the j; structural adequacy of the auxiliary building or on plant operation. It j, would be arbitrary to assume the ambient saturation temperature for i equipment qualification purposes. Review of th'e System Component Work - 4 Sheets designated within the Reactor Auxiliary Building show [ qualification temperatures well in excess of the area requirement. 1 Therefore, the System Component Work Sheets for the Reactor Auxiliary { Building will not be changed to reflect a screening number when actual conditions have been calculated." i

It is concluded that the Licensee has provided a satisfactory response to the NRC concern.

r

_nklin Rese_ arch..C. enter

I-TER-C5257-511 4.3.2.4 Radiation-(Inside Containment) Section 3.8 of the NRC SER (16] identified the following concern: l "The licensee has provided values for the radiation ~1evels postulated to exist following a LOCA. The application and methodology employed to-l determine these values were presented to.the licensee as part of the NRC staff criteria contained in the DOR guidelines, in NUREG-0588, Land in the guidance provided in IEB-79-01B, Supplement 2.- Therefore,-for this

review, the staff has assumed that, unless otherwise noted, the values provided have been determined in accordance with the prescribed criteria. The staff review determined that the values to which equipment

was qualified enveloped the requirements identified by the licensee. i The value required by the licensee inside containment ranges between 9.5 x 105 to 1.5 x 108 rads for'the integrated dose. These values do not '

envelop the DOR guideline (4 x 107 rads) requirements and therefore are not acceptable. The radiation service condition provided by the licensee is lower than provided in the guidelines for gaansa and beta radiation. i The licensee is required to either provide justification"for using the lower service condition or use the. guidelines for both gamma and beta radiation. If the former option is chosen, then the analysis, including the basis, assumptions, and a sample calculation, should be provided. 1 A required value outside containment of 1.1 x 106 rads bas been used by

 ;       the licensee to specify limiting' radiation levels within the RHR pump area of the auxiliary building. This value appears to consider the

. radiation levels influenced by the source term methodology associated with post-LOCA recirculation fluid lines and is therefore acceptable."

l- { In response to the NRC concern, the Licensee stated (20):

"The SER second paragraph for Section 3.8 states that the values j submitted within CP&L's H. B. Robinson 90-day response do not envelop the DOR Guidelines (4 X 107 rads) requirements and therefore are not j acceptable.

i Radiation values listed on the submitted System Component Evaluation Sork Sheets within the specification column reflect a series of calculations I based upon containment volume, internal shielding, and instrumentation / equipment location. These calculations follow the procedures referenced as acceptable in the DOR Guidelines and provided within Appendix B. Sample calculations and representative nomogram use were presented as Appendix A within CP&L 90-day submittals; Rev. O, Rev. 1, Rev. 2, and Rev. 3. Of note is the reduced level radiation number due to oversized containment volume (2.1 X 106 gg3) and shield wall thickness (36 inches) when using the nomograms. Each instrument or equipment as represented on the work sheets was dimensioned by level within 4-15 Os Ubd Franklin Research Center A om a.m. %na m w.

i TER-C5257-511 containment or Reactor Auxiliary Building and located by compartmentfor shield wall to. determine the maximum radiation level experienced.under

                       .LOCA. conditions. This figure was added to the normal operating radiation dose-(40 year life) and a-margin assigned. Section 1.3.2 of the H. B.

Robinson 90-day Rev. 3 report provides additional insight into the-assigned radiation levels. Individual dosages used on the work' sheets 4 are summarized and listed in Table 1.3.3 of the above mentioned. report. For review purposes, response submitted figures ~and tables are included in this . section to aid in evaluation -of our radiation- assignments. j

                       -When operating time.for equipment / instrumentation was less than'one (1) 7                       . hour, a minimum of one (1) hour was picked for establishing dosage
                       -reduction based on the' nomogram entitled,-30 Day Dose Connection Factor vs. Time Required to Remain Functional (HRS). This should establish sufficient margin and encompass existing test data.

For items located close to sump water flooding levels an additional radiation dosage was assigned based on actual operating time. As stated in Table 1.3.3 Notes (8)-& (9), data used can be found in NUREG-0588,

 ;'                      Appendix D. Table D-8, Containment Sump Gamma Dose Rates and Integrated                                                                   -

- , -Dose Versus Time.

Beta radiation was considered using Appendix D, Table D-6, Beta Dose Rates and Integrated Doses at the Containment Center Versus Time in Air. Based on the time of operation, equipment-location, shield wall absorption, compartment wall absorption, insulation thickness, instrumentation housing absorption, motor case shielding, et al., beta contribution is less than 10% of the total gamma dose experienced by the : . listed' equipment. This is a conservative assumption based on the DOR Guidelines requirement of the. beta dose to be'less than or equal to 10% of the total gamma dose to which an item of equipment has been qualified.. , The above is the basis, assumptions, and basic analysis of the option i chosen to justify the choice of lower service conditions than the 7 generalized screening radiation service value stated in the SER and presented at the NRC 79-01B meeting held in Bethesda, Maryland on July r 7-10, 1981. Sample calculations as included in our 90-day, Revision 3 2 1-response to IE Bulletin 79-018 are repeated as Appendix C-of this report." 4 I It is concluded that the Licensee has provided a satisfactory response to

j. the NRC concern.  ;

j 4.3.3 Submergence Section 3.5 of the NRC SER (16] identified the following concern:

                         "The licensee's value for maximum submergence is 231.2 ft elevation inside containment. Equipment below this level has been identified by                                                                     ,

the licensee. The licensee identified three safety-related level ( 4-16 f.% nter Jl ..d!I A o- on Franklin or Tw. Fr.n.na in. Research C.e.wi. i

      --   _ ,. -- ,_, _ ._ ,._ ~ ,__-_.-_.,_ __ _ .                                      m.____,,      , . , . _ _ , _ , , , , .        _-...,,,m_,.,_.. -,.m..+,

TER-C5257-511 transmitters mounted on the shield wall as having the potential for becoming submerged af ter a postulated event. The licensee stated that these transmitters are not the only source of data for operator assessment and decision needed for HELB and LOCA situations; therefore, their assumed failure upon submergence does not necessitate relocation or replacement. In this regard, lice .see should provide an assessment of the failure modes associated with the submergence of these transmitters. The licensee should also provide assurance that the subsequent failure of these components will not adversely affect any other safety functions or mislead an operator. Additionally, the licensee should discuss operating time, across the spectrum of events, in relation to.the time of su bmergenc e. If the results of the licensee's assessment are acceptable, then these transmitters may be exempt from the submergence parameter of qualification. It is not clear from the information submitted that submergence of safety-related electrical equipment outside of containment was addressed. The licensee should address this area more specifically in the 90-day response and upgrade the CES as appropriate." In response to the NRC concern, the Licensee stated [20):

 "The safety-related level transmitters (LT 459, LT 460, and LT 461) referred to in this paragraph provide pressurizer water idVel indication and are mounted in an instrument rack on the shield wall at elevation 230 f t within containment. These transmitters have been replaced with Rosemount Model 1153A transmitters during the August, 1980 outage at H.

B. Robinson Unit 2. Instruction was given to remount as high as possible and practical in the instrument rack. A new measurement is required for re-evaluation of submergence level for these instruments. Additional study indicates their need time within the LOCA to be the first 30 minutes. A study will be performed to evaluate the ef fect of new mounting, the rate of flood to determine useful time, and the effects of new emergency procedures on these instrumentation reading requirements. At this time, the statement that their assumed failure under submergence will not affect accident mitigation is still a valid one. This study will be completed by the date established by the NRC for completion of qualification of safety-related electrical equipment. Submergence of new equipment outside of containment will also be studied. New modification of Auxiliary Building areas due to fire protection requirements need to be evaluated to establish drain paths and/or water accumulations. Existing reports indicate no detrimental water buildups due to HELB or small pipe breaks, but they de not account for building modification performed in recent months. A report on submergence of safety-related electrical equipment within harsh environment areas in the Auxiliary Building will be completed and submitted by the date established by the NRC for completion of qualification of safety-related electrical equipment." g 4-17 LLL Franklin Research Center Mw of he Fremen methre

TER-C5257-511' - It is concluded that the Licensee has not resolved the NRC concern but is'

,                     currently in the process of evaluating the concern.

4'3.4

                        .               Chemical Spray Section 3.6 of the NRC SER (16] identified the following concern:
                            "The licensee has specified that boric acid solution constitutes the plant's chemical spray; however, the exact. volume percent, concentration, and pH values were not provided. Therefore, for_the purpose of this review, the effects of chemical spray will be considered unresolved. The staff will review the licensee's response when it is submitted and 4-discuss the resolution in a supplemental report."

In response to the NRC concern, the Licensee stated [20):

                            "The chemical spray consists of sodium hydroxide, boric acid, and refueling water. Mixing of the refueling water.from the refueling water storage tank, the boric acid from the boric acid tank, the borated water contained within the accumulators, and primary coolant will bring the concentration of sodium hydroxide in the containment to approximately 0.6 weight percent solution caustic and 1.7 weight percent boric acid. This-maintains a pH of at least 9.3. Spray additive eductors are designed to provide enough sodium hydroxide in the mixture so as not to exceed pH 10 during the injection phase."

It is concluded that the Licensee has provided a satisfactory response to i the NRC concern. , 4.3.5 Aging l Section 3.7 of the NRC SER [16] identified the following concern:

                            "Section 7 of the DOR guidelines does not require a qualified life to be established for all safety-related electrical equipment. However, the following actions are required:

(1) Make a detailed comparison of existing equipment and the materials identified in Appendix C of the DOR guidelines. The first supplement to IEB-79-01B requires the Licensee to utilize the table and identify any additional materials as a result of their effort. ! (2) Establish an ongoing program to review surveillance 'nd amaintenance

y. records to identify potential age-related degradations, i 1 i (3) Establishment component maintenance and replacement schedules which j include considerations of aging characteristics of the installed components.

4-18 arR21, dbd Franklin Research Center A Oms.on of The Frannhn Insthme

t TER-C5257-511 1 l The licensee identified a number of equipment items for which a specified

                    . qualified life was established (for examples, 5 years 15 years,- or 40
 !                   years). In.its-assessment of these submittals, the staff did not review-

[ the_ adequacy of the methodology nor the basis used to. arrive at these.

 !                   values; the staff has assumed that the established values'are based on l                   . state-of-the-art technology and are acceptable.
 ,                   For this review, however, the staff requires that the licensee submit supplemental information to verify and identify the degree of conformance to the above requirements.                             The response should include all'the equipment identified as required to maintain functional' operability in harsh environments.

j The licensee indicated that this phase of the response is outstanding and that the review is in progress. The staff will review the licensee's

 ,                   response when it is submitted and discuss its evaluation in a i

supplemental report." In response to the NRC concern, the Licensee stated [20]:

                     " Electrical equipment identified within harsh environments were reviewed against existing test data to determine if a 40 year life was established.

j When so established, this was recorded on the Component Evaluation Work Sheet.. Also noted was the period within the test program when aging was ~ addressed if this information was available from the test reports. i' l Section 4.0, Conclusions, of our 90-day response, Revision 3, dated February 1,1981 reviewed the actions to be taken when less than 40 year life is realized for components and/or equipments. - These actions are i again summarized within Section III-of this report. l To assure that aging is adequately covered under equipment qualification, it is our intent to establish aLqualified life for a11' components in a harsh environment and to identify the component part or parts that limit qualified life. This will be the plant data base into which new safety equipment required by future modifications and replacement parts required by operation will be entered when evaluated and approved. This data base will form the baseline'for a component inspection and replacement program. Comparisons of predicted age vs. actual age will modify the limiting life of either components or equipments. Factored into.this program will be supportive elements such as elastomers, lubricants, mountings, and supplier conditions which are necessary to assure both operational life and qualification level. I- This program will be compiled, evaluated, reviewed, approved, and l~ operational by the date established by the NRC for completion of-qualification of safety-related electrical equipment." ! It is concluded that the Licensee has proposed a program which, if properly implemented, will resolve the NRC concern. 4-19 _nklin_Resear_ch _ _ . C_ enter If L _. _ . . - - _ . . . . _ _ . . . _ _ _ _ . ._ _ _ _ . _ _

TER-C5257-511 4.4 EQUIPMENT ENVIRONMENTAL QUALIFICATION EVALUATION The evaluation presented in this section of the report includes, for each equipment item, completed' equipment environmental qualification review checksheets (partially handwritten) which present both the technical information necessary to conduct the review and the results of the evaluation. g 4-20 UdUd Franklin Research Center A Omneon of The Frankhn insatute

i EU ? Ed"

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' pj i EQUIPMENT ENVIRONMFNTAL QUALIFICATION l s i FOUIPNENT ITEM CHECNSHFET INDEX I (( t .H 2 3

    . 2a                                                                        ................. B. ROBINSON

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-     ,5 ([     ...     ...CO4PONENT......................................CTURER I

1 SOLEROID VALVE ASCO L90320A195 REACTOR AUXII.IARY PLDG. h(f C 3 2 SOLFNOID VALVE ASCO NP031665E CONTAINMENT. ELEV. 203*=0* 3 SOLENotD VALVE ASCn NP0336E35E CONTAINNFNT. EI.E V . 203'=0* 4 SOLENGID VALVE ASCO 20630I2U CONTAIN*ENT FLEV. 203'=0* 5 MOTORIEFo VALVE ACTUATOR LIMITDROUE SN800 CONTAINNENT FI.EV. 24t'=0* 6 NOTORIEFD VALVE ACTUATOR LIMITOROUE, SND3 3 i 7 CONTAINNFNT. ELFV. 245' MOTORIZED VALVE ACTUATOR LIMITOROUE' SMan0 REACTOR AUXILIARY BLDC. . O MOTORIZED VALVE ACTUATOR LIMITOROUE SMB3 REACTOR AUXILIARY BLDG.

!                     9      FLON TRANSMITTER                        FtSCHEN AND PORTER                   1082496PPBABBB                    REACTOR AURILIART RLDC.

10 PRESSURE TRANSMITTER FISCHER AND PORTER 50EP304tPCIA REACTOR AUXILIART BLDG. Il PRESSURE TRANSMITTER FISCHFR AND PORTER 50EP1041 REACTOR AUXILIARY RLOG. 12 PRESSURE TRANSMITTER ROSEMOUNT 11534 CONTAINMFMT 13 LEVEL TRANSNITTFR ROSEMOUNT 1853A CONTAINNENT 45 14 FLON TRANSMITTER ROSFMOUNT 1953A 8 CONTAIN.ENT

15 PRESSURE TRANSMITTER ROSEMOUNT 1153GA9 CONTAINNENT h$ 16 LEYFL TRANSMITTER GEMS XM52495 CONTAINMFNT 17 LEVFL TRANSNITTER GFMS XM36495 CONTAINMENT 10 TEMPERATURE ELEMENT ROSFMOUNT 176EF CONTalNMENT. FLFV. 243'=0*

l! 19 LEVEL SWITCH MADISON 5402 CONTAIN4FNT, ELEV. 220*=0* 20 ACCELEROMETER ENDEVC0 2273AM20 CONTAINNENT 21 APPLIFIER UNHOLTE= DICKIE 22CA2TR CONTAINNENT 22 ELECTRIC NOTOR NESTINGHOUSE 506pPE REACTOR AUXILIARY PLDC. 23 ELECTRIC NOTOR NESTINGHOUSE 605.53 . CONTAINNENT, FLEV. 275*=0* 24 ELECTRICAL PENETRATION . CROUSE= HINDS 1.2.2(745).t.2.2(747).l.2.4t74 CONTAINMENT ELEV. 234'=246' 25 ELECTRICAL CABLE CONTINENTAL NIRE CC2115 CONTAINNFNT 26 ELECTRICAL CABLE RFRITE HT/FR CONTAINNENT 27 ELECTRICAL CARLE ROCRBESTOS VARIOUS CONTAINNFNT 20 ELECTRICAL CARLE RDCRBESTOS' VARIOUS REACTOR AUXILIARY BLDC. 29 ELECTRICAL CARLE SAMUEL MOORE THERMOCOUPLE EXTENSION CONTAINNENT 30 ELECTRICAL CARLE SPLICE RATCHEN VARIOUS CONTAINpFMT, F l.E V , 234'=246' 31 ELECTRICAL CONNFCTOR AMP 535401, NIRF SIZE 16 CONTAINMENT. ELEV. 234'=0* - 246'=0 32 ELECTRICAL. TAPE 3N/ ELECTRO PRODUCTS SCOTCH 70 (SII.! Cow RURRFR)

                                                                                                                                                                                ,g CONTAINNFNT                         pq      i 50

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A NRC Contract N2. NRC-03-79-118 dEFrtnklin Rrse:rch Cznter FRC Project Nr. C5257 P g3 _ A Dmwn of The Frankhn Institute FRC Assignment No.13 lc 20th and Race Streets. Phila.. Pa. 19102 (215) 448-1000 FRO Task No. SU EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. l EQUIPMENT ITEM NO.1 (TMI ACTION PLAN ITEM II.E.4.2) SOLENDID VALVE LOCATED IN THE REACTOR AUXILIARY BLDG. ASCO MODEL LB8320A185 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO.1 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): FUNCTION AND PLANT ID NOT STATED LICENSEE SUBMITTAL: SCEW(S): 8 OF 15 [15] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (S;e Section 3 of this TER for Legend) R, T, Q1', RT, P, H, CS, A, S, (R) , M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not, applicable Neis- E m - LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Cummary of Licensee Responses to the NRC SER lb l Equipment Environmental Qualificat. ion Summary Forms 2 Licensee Response to NRC SER 3a, 3b, Om, 2d-System Consideration Review *?. 'b, tc, id, 0;, 4f Equipment Environmental Qualification R view 5;, 55, 5;, 52, 5., 51, 5;, Sh, 51, Sj Installed TMI Lessons Learned Implementation 6a, 6b Equipment Summary Maintenance and Replacement Schedule Summary 72, 'b, M I -- .---

A NRC Contract N:. NRC-03-79-118 Paga 000hrinklin Rise rch Ccnter FRC Project N3. C5257 A Divison of The Fr:nklin Instruti FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa. 19103(215) 448 1000 FRC Task No. 8 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /

SUMMARY

OF LICENSEE RESPONSES 'IV THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. j The Licensee (has/ hee-not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions.

                                                                                   ~

The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the I.icensee'for this equipment-item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

 - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt ~[T"1.a Qualification Not Established l III.b Not in Scope II.b Not Qualified IV Documentation Not Available

NRC Contract Nr. NRC-03 79-118 phr:nklin UO0 R: search Ccnter FRC Project No.C5257 Page - A Divmon of The Franklin Institute FRC Assignment No.13 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-10m FRC Task No. 8// EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. / EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate 1 Adequate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied . Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tost Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established >< II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification l III.D Equipment Not in the Scope of the Qualification Review

• l IV Documentation Not Made Available TMI Action Plan Item No. II.E.4.2

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NRC Contract No. NRC-03-79-118 00 Fr:nklinR:searchCcnter FRC Project No. C525'l Page , A Dvwon of The FrankhnInstuute FRC Assignment N3.13 5i 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. 5 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. i imzst

                      .                  -3 WAY SOLENOID VALVES
                                                                                                                                     sal.EM
                                    % for' Air,' Inert Gas,' Water and Light Hydra'ulic Oil                .
                                  -    r      . + .%" and %" N.P.T.                                      ,

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• General Description .

This compact design eliminates the ,

            .ess6se connection in the solenoid -all                          i..

aseemstions are in the valve body pro- iT A O -, 6 vidingla-line piping, y ..,_ , . M*f,,ht S i This modern design concept with ori-

            .fice and pipe connections in the body              .

p. * * . ' . " "

T aise pennits coil replacement without j ' Q*5.h e cpenas pipe connecuens - now nec.

          ,1ssary on other 3 way valves.                                      ,T ,                                         - g. ,

b, f ,_ _ Applications M.. . . . O Forautomatic control of air, inert gas, 4 + k.5,.R ($;i'.li . maar, light hydraulic oil, freon and aR other asses and liquids . . . non - Qp df ~

 ,            corrosive to brass and stainless steel.

Valves are commonly used to apply w ses,s \ st'inE a w seass N a h pressere to and vent pressure from b a cylinders and diaphragms or for so-1sesion and diversion of pressure. ,QJ Special valves available for:

• dry air -

gas

• continuous cycling
• exception. (c) Universa! - for normally closed Ambient: Nominal Range, 32*F. -

ally long life

• heavy-duty operation or normally open operation. Selection 77'F. (104*F. occasionally - see n; e clickless and quiet (no A-C hum) or diversion of pressure can be applied 6 in Engineering Information Sectier..

8peration. at I,2 or 3. - Installation: Mountable in -any pco-

          ' Refer to I.ong ufe Construction on Pipe Slass: %* and %* N.P.T.                             tion withouraffecting operation.

pass 63. . Yalve Parts In Contact with Media: Mounting: See dimension drawings.

           ' Some typ'ical applications are:                  Body - Brass or 303 s.s., as listed.       Approvals: UL listed and CSA crr:-

• automation Seals and Discs - Buna "N" or Ure. Iled. Refer to page 6 for details.
• vending thane, as listed. Optional Features:
• air and hydraulic cylinders Core Tube - 305 s.s.
• Junction Box Solenoid Enclosure
• pilot operators Core and Plugnut - 430F s.s.
• Strain-Relief Connector
• 3as sampling Core Spring - 302 s.s.
• Manual Operator o copying and reproduction Shading Coil- Copper-(brass body);
• M* Threaded Conduit Hub or

               . eqmpment                                    Silver (stainless steel body). ,

Adapter a lubricating devices Dise Holder - Acetal.

• Molded Class A or F Coils e airconditioning . Core Guide (10.5 and 16.7 watt only) . with Spade Terminals or Leads
• tation - Acetat
• Dual Voltage Molded Class A or Solenoid

Enclosures:

Two types avail. F Coils

             * *i' d'7'"      .                              able:

• Cass H High-Temperature Coil
• I*""d'7 '9"*P"*"" -(a) General Purpose (NEMA I).
• Open Frame Solenoid for
• 88mPresson (b) Explosion-Proof and Watertight Cabinet Installation SpecH! cations (NEMA 7C 7D and 4).

          'C               Three types available:            Electrical: Standard Voltages:

(ah Diormally Cosed - applies pres- 4.120,240,480 volts, A C,60 Hz (or 50 Hz in 110 voit multiples). {g sue when solenoid is energized; ex. t hausts pressure when solenoid is de., 6,12,24,120,240 volts D-C. l energized. Other voltages avaitable when required. l (b) Norma!!y' Open - applies pressure Coih Continuous Duty Molded Class l when solenoid is de-energized; ex. A or F Coils, as listed. hausta pressure when solenoid is ener. Temperature: Fluid: To 200*F. Maxi-gazed. , mu a, as listed.

NRC Contract flo. NRC-03-79-118 00 FranklinR;searchCenter FRC Project No. C5257 Page A DMsion of The Franidin Institute FRC Assignment No.13 5j 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTaskNo. SU EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. i m as As can be seen from the preceeding pages, the solenoid valves are suitable for a normal maximum ambient temperature of 77"F. The materials of construction vary according to the type of internals specified for the application. The referenced report c'oes not take into account all of the possible materials. The submittal does not contain any information regarding the valve internals or other materials of construction. One of the more significant itema that affect the valve life and suitability for temperatures beyond the 77*F identified on the preceeding pages is the insulation system used for the solenoid coil. If the materials used were identified, it would be possible for the licensee to perform an analysis which would provide a determination of the suitability of the installed valve for the conditions described on the SCEW sheet. However, the licensee has not provided documentation to establish the environmental qualification of the equipment installed in the plant. CONCLUSION The licensee has not provided evidence of qualification of the installed solenoid valves. In addition no radiation capability is provided by the manufacturer for these valves. The licensee has not provided a radiation analysis for the actual mater'ials used in the valves. I

4vu0u Fr:nklin Research Ccnter NRC Contract N3. NRC 03-79-118 FRC Project N2.CS257 Page _

         . A DMe6on of The Frankhn Instituta                                          FRC Assignment        .17                         6a 20th and Race Sweets. Ph61a.. Pa.19103 (215) 448-1000                      FRC Task No.           II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. l i

I INSTALLED TMI LESSONS LEARNED IMPLBJ'2iTATION BOUIPMENT

SUMMARY

NRC requested an evaluation of the environmental qualification of safety- ! ralsted electrical equipment located in harsh environments required for TMI

. Lersons Learned Implementation. The objective is to evaluate qualification

documentation of equipment within the scope of IE Bulletin 79-01B, Supplement 3 (item 2), in accordance with criteria established-by the NRC (see Section 2 i cf this report) in a manner identical to the evaluation of all other safety-rointed electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with specific sections of NUREG-0737 which l hava an instiallation implementation date of January 1,1981 (sections are idsntified below). Where applicable, a review is to be performed on installed equipment with implemencation dates after January 1, 1981 if adequately id:ntified by the licensee.

I This plant is a PWR N , EWR . I The NSSS Vendor is Westinghouse (W)[, Babcox & Wilcox (B&W) ,

Combustion Engineering (CE) , General Electric (GB) .

With respect to this equipment item, it is noted (applicable section checked):

 !         The Licensee does not provide adequate information with respect to

{ identification of TMI Action Plan equipment installed as of 1/1/81. The Licensee has not provided the correlation of this equipment item with the specific sections of NUREG-0737. [The correlation is needed to ensure

;          that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal blocks associated with the device also identified?]

The Licensee has not provided the approximate installation date for the TMI' Action Plan equipment items so that the appropriate qualification criteria (NUREG-0588 or DOR Guidelines) can be used in the EBQ evaluation. The Licensee has provided a standard Owners' Group position with respect to a NUREG-0737 technical area. The Licensee has requested extensions of implementation dates. j The Licensee has stated that this equipment item is associated with the ! following section of NUREG-0737. (This list of applicable NUREG-0737 sections has been identified by NRC as sections within the scope of this review): II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment l II.D.3 (ALL/1-1-81) Direct Indication of Relief and Safety Valve

!                 Position

4 NRC Contract N . NRC-03-79-118 FRC Project No. C5257 Pag] UOOU Fr:nklin R:se1rch Crnter A Divmon of The Fr:nklin Instituti FRC Assignm:nt No.13 6b 20th and Race Streets. Phila.. Pa. 19103 (215) 44810m FRC Task No. M EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. i II.E.1.2 (PWR/1-1-81) Auxiliary Feedwater System Automatic Initiation and' Flow Indication II.E.3.1 (PWR/1-1-81) Emergency Power Supply for Pressurizer Heaters (Safety-Grade Interfaces II.E.4.1 (ALL/7-1-81) Dedicated Hydrogen Penetrations 1 II.E.4.2 -(ALL/1-1-81) Containment Isolation Dependability II.F.2 (PWR/1-1-81) Instrumentation for Detection of Inadequate Core Cooling II.G.1 (PWR/1-1-81) Emergency Power for Pressurizer Equipment (Safety-Grade Interfaces) II.K.2.10 (PWR/B&W/7-1-81) . Safety-Grade Anticipatory Reactor Trip II.K.3.9 (PWR/W/1-1-81) PID Controller Modification (If Hardware Change Involved) - II.K.3.12 (PWR/W/1-1-81) Anticipatory Reactor Trip upon Turbine Trip II.K.3.13 (BWR/GE/7-1-81) Separation of HPCI and RCIC Initiation Signals II.K.3.15 (BWR/GE/7-1-81) Prevention of Spurious Isolation of HPCI and RCIC Systems II.K.3.19 (BWR/GE/7-1-81) Interlock on Recirculation Pump Loop II.K.3.21 (BWR/GE/7-1-81) Restart of Core Spray and LPCI Systems (If Hardware Changed Out) II.K.3.27 (BWR/GE/7-1-81) Provide Common Reference Level for Vessel Level Instrumentation (If Hardware Changed Out)

i i l A NRC Contract ND. NRC-03-79-118 liDDEFrsnklin R:sesrch Cent:r FRC Project ND. C5257 P;g2 - A Dmson of The Franklin Institute FRC Assignment No.13 la 20th and Race Streets. Phila.. Pa 19103(215) 448-1000 FRC Task No. 6// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2. EQUIPMENT ITEM NO. 2 SOLEN 0ID VALVE LOCATED IN THE CONTAINMENT, ELEV. 283'0" ASCO MODEL NP831665E REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. 2 LICENSEE REFERENCE (S): 40, 649 FUNCTION (PLANT ID): NOT STATED (V12-7, -9, -11, -13; CVC-200A, B, C) LICENSEE SUBMITTAL: SCEW(S): 20 OF 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) CdLY (S33 Section 3 of this TER for Legend) T, QY, RT, P, H, CS S, (R) , M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Centents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb i Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 44-System Consideration Review te, 4b, 4c, 4d, 4e, if Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, Sf, 5;, Sh, Si, Sj ! S:, 55-In3talled TMI Lessons Learned Implementation Equipment Sununary Maintenance and Replacement Schedule Summary '7;, 7b, 7c

Ar NRC Contract N2. NRC-05-79-118 PaQ3 000llFrinklin R:se:rch Ccnter FRC Project N;. C5257 A Division of The Franklin Institut2 FRC Assignment No.13 lb 20tt. and itace Streets. Phila.. Pa 19103 (215) 448 1000 FRC Task No. 6/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. A

SUMMARY

OF LICENSEE RESPONSES 'IO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: g Tne Licensee (has,^r -^S provided a response to the SER concerns. g The Licensee (has/h:2 ..et) specifically stated that the equipment is qualified and7tw. sill function when exposed to the applicable DBE environmental ser.vice conditions.

                                                                                 ~

The Licensee hr.s presented information which shows there are no outstanding qualification deficiencies. The Licens9e (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment- item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALINICATION EVALUATION CATEGORY BASED ON REVIEW

  - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

[I.a Qualified] II.c Qualified Life Deficiency 1.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available

                                                                                                            ~

1 NRC Contract NO. NRC-03-79-118 00J Fr:nklin Research Ccnter FRC Project No. C5257 Page - A Dwon of The Frankhn Institute FRC Assignment No.13 2 I 20th and Race Streets. Phda.. Pa. 19103 (215) 44810m FRC Task No. X1l i EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. .m'l EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qutlified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate . o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tact Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.o Equipment Qualified X I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life

  .         or Replacement Schedule Justified III.a       Equipment Exempt From Qualification III.b       Equipment Not in the Scope of the Qualification Review IV          Documentation Not Made Available L$

N NRC Contr:ct NJ. NRC-03 79-118 Pag 3 00 Fr:nklin Rewarch C:.nter FRC Project No. C5257 A Divisen ome Franklin Indtute . . FRC Assignment N;.13 30 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. fI / EQUIPMENT ENVIRONMENTALQUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _4 LICENSEE RESPONSE 'IO NRC SER 4.2 Ecutement Requiring Additional Information and/er Corrective Action (Appendix B) The bulk of master list squipment was placed in this category and our review of deficiencies is based upon the following:

             -     Deletion of deficient listed equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.

f - Re-evaluation of CP&L's updated submittals by NRC Region II, N Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IEB 79-013. Technical Draluation Report

                   - Docket No. 50-261; Plant:                     H. B. Robinson 2, dated November 6, 1980 nd Revised November 11, ?.980.

Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Equipment Description Manufacturer Model No. Location

1. pump motor Westinghouse 506UPZ outside containment

2. motor operator Limitorque SMB-00 containment

3. motor operator Limitorque SMB-00 outside containment

4. motor operator Limitorque SMB-1 outside containment

5. flow transmitter Fisher & Porter 10B2496 outside PBBABBB containment

6. pressure transmitter Fisher & Porter 50EP1041 outside BCIA containment

7. fan motor Westinghouse 685.5-S containment

8. cable Continental Wire CC2115 containment

                                                         & Cable

9. cable Kerite RT FR containment'

70. solenoid valve,1 ASCO NroneO5E containment ]

Notes: 1 As reported in qualification test programs, components and/or materials will require replacement on a designated schedule to maintain qualification. - i

      ^-       Solenoid Valve                     ASCO                   NP831665E            1          R,CS,A i                                          . - .

l - t A Items reported as qualified within NRC Region II revised TER, dated 11/7/80. i l - _ _

 *                                                                                                                          ^
                                                                                         \i =
                                                                                                                                         .l 4                                                         NRC Contract No. NRC-03 79-118 FRC Project No.C5257                               Page UOOU Frankhn Research Center                                                                                                              ,

A Diweson of The Frankan Inseuute FRC Assignment No.13 , 3U 1 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRCTask No. 511 f. . l EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _P _ z s s s 1 3.2.6 Solenoid Valves As reported in CP&L responses to NRC IE Bulletins 79-01 and, g 79-013 (45-day report), the listed solenoid valves in contunment are to be replaced by qualified equipment. The in-place ASCO solenoid valves have not exhibited poor performance or requirai % - ~ excessive maintenance. When manufactured and supplied, ASCO Company was not required to maintain the QC/QA procedures and. - programs necessary to allow traceability and certification needed for qualification. ' The replacement valves are also ASCO Company equipment Model Nos. NP831665E, NP8316E35E and 206-381-2U used' singly or in combination to achieve their valving function. These solenoid valve types were included in a qualification testing program to meet IEEE Standards 323, 344, and 382. Results of

                                                                                                                ~

this testing are published in AUTOMATIC SWITCH COMPANY. l Test' Report No. AQS21678/TR, Revision A, entitled Qualification, Tests of Solenoid Valves by Environmental Exposure io, Elevated 1 Temperature, Radiation, Wear Aging, Seismic Simulation, Vibration Endurance, Accident Radiation and LOCA Simulation. The test parameters subjected the valves to a maximum temperature s of 346 F, a maximum pressure of 125 PSIA, a relative humidity of100%,aboratedspraydugingtheLOCAsimulationanda total radiation of 2.0 x 10 RADS. The test results are v civided into two (2) parts-first the evaluation of the elastomers and coil materials and second the valve mechanisms and housing. - The elastomers and coil materials, as reported, are qualified for a 4.4 year life (includes a 10% margin figure). The valve ~ d,. proper is qualified for a 40-year life. This will require the coils and elastomers to be replaced on a scheduled basis to maintain the serviceability of the entire c valve as well as its qualification. The proposed schedule is replacement of stated components on a four- (4) year cycle. Replacement will be performed during the closest outage or ' refueling to that time period.

                                                                                                                   -M                 .-

v \ V g b

NRC Contract No. NRC-03 79-118 s 4UOOU Fr:nklin Research C;nter FRC Pro}ect No. C5257 Page

      ~*

A Dwon of The Franklin Insth xe FRC Assignment No.13 3c Nth and Race Streets. Phda.. Pa 19103 (215) 44810m FRC Task No. 8/l ,c. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. f.

  ~y
     ~:v 7
 \              \                                                   '

LICENSEE RESPONSE 'IO NRC SER (Continued) . s - N - Solenoid W1ves

                             'g                Replacemeat of in-containmc.nt solenoid valves identified within this report has been pe.rformed during the 1980 refueling
                           .                 " outage (August - October,1980) . The ASCO valves specified as i replacements are considered qualified by similar type testing performed by the manufacturer and reported within available
                                ','            qualification reports (Paragraph 3.1, Reference 47).                                                       81 t, y                     Additional action required - Noted in the manufacturer's J      ,                report is a certified life of 4.4 years for the coil and elastomers within these solenoid valves. These elements will be replaced on a four- (4) year cycle to maintain complete Y                                            cperational capability.

N. s Cn3 e Mm.

     +

1 4 4 5-s 4 1 , 1 't s

t. x "

 .;_\                               -

s Y 7 <- g A

                                        ,,v,         - ~ - .          ,.    . - . .   .    - . - - - - . - , . , - . . - - .-,.          -    --        ,     -

I gh, NRC Contract No. NRC-03 79-118 000h Fr:nk!!n Rewarch C:nter FRC Project No.C5257 Page A Division of The FrankhnInsutute o.13 5 20th and Race Streets. Phda . Pa 19103(215) 448-1000 FRC Assignmeng// FRC Task No. 6 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2 1 Checksheets [ o T:~dw f/ have been removed due to the preprietary nature of information contained therein.- i i I

#%                                                           NRC Contract N2. NRC-03-79-118                                   ~

bbFr:nk!1n Rise 1rch Ccnter FRC Froject N .C5257 Pig 3 A Dim on of The Frankhn Institute FRC Assignment No.13 la 20th and Race Streets. Phda . Pa. 19103 (215) 448-10rA) FRC Task No. S/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d _ EQUIPMENT ITEM NO. 3 SOLENDID VALVE LOCATED IN THE CONTAItEENT, ELEV. 283'0" ASCO MODEL NP8316E35E REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. 3 LICENSEE REFERENCE (S): 40, 649 FUNCTION (PLANT ID): NOT STATED (V12-7, -9, -11, -13 ; CVC-200A, B, C) LICENSEE SUBMITTAL: SCEW(S): 20 0F 25 (20} DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY2 (S:e Section 3 of this TER for Legend) T, r#, RT, P, H, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Centents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a , 3 b , 3 c , Syctem Consideration Review 's, 25, 4c, d', 40, if Equipment Environmental Qualification Review **

                                                                                    "". *c.      Ed. Se, 5f, 50, 55     Si, Sj In3talled TMI Lessons Learned Implementation                                  4 4b.

Equipment Summary Maintenance and Replacement Schedule Summary 't. '" 't-

Ag NRC Contract N2. NRC-03-79-118 du Fr:nklin Research C:nter FRC Project No. C5257 Page A Dwen of The Frankim insutute FRC Assignment No.13 lb 20th and Race Streets. Phda. Pa 19103 (215) 448 1000 FRCTask No. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d StMMARY OF LICENSEE RESPONSES 'IO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: [ Tne Licensee (has,S : ~ti provided a response to the SER concerns. 1 The Licensee (has/h:: ::t) specifically stated that the equipment is qualified and)4 4;, will function when exposed to the applicable DBE environmental service conditions.

                                                                            ~

The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: . Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item l .that can be construed as a basis for justification for interim oparation. The Licensee (has/has not) provided a schedule for the proposed t corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. l DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

  - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend) fi.a Oualified)                                              II.c Qualified Life Deficiency I.b   Modification                                         III.a Exempt II.a Qualification Not Established                          III.b Not in Scope II.b Not Qualified                                          IV    Documentation Not Available

  #g                                                            NRC Contract No. NRC-03-79-118 FRC Project No.C5257                      Page 000U Fr:nklin Research Center A De d The Frankhn Insntute                             FRC Assignment No.13                       2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. X/ /

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Ad:quate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qutlified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding. Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tact Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified X I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review l IV Documentation Not Made Available SEE EQUIPMENT ITEM 2 FOR DETAILED EVALUATION, SHEETS Sa THROUGH Sf. l

NRC Contract NO. NRC-03-79-118 LOhkr:nklin Research Center FRC Project N2. C5257 Pag] A Dwision of The Frankhn Instaure FRC Assignment No.13 30 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 1 LICENSEE RESPONSE TO NRC SER 4.2 Eeutement Recuirine Additional Information and/or Corrective Action (Accendix 3) The bulk of master list equipment was placed in this category and our review of deficiencies is based upe- the following: > Deletion of deficient listed ~ equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environ = ental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                    - Docket No. 50-261; Plant:                   H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.
                                                                                                  ~

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Ecutement Descrietton vanufacturer Model No. Location (

10. solenoid valvel ASCO NP831665E contain=ent

11. solenoid valve l ASCO NPS316E35E containment

12. solenoid valvel ASCO 206-381-2U containment Notes:

1 As reported in qualification test programs, components and/or materials will require replacement en a designated schedule to maintain qualification. - l A. NP8316E35E 1 R,CS,A Soler.aidfalve ASCO Items reported as qualified within NRC Region II revised TER, dated 11/7/90.

NRC Contract N J. NRC-03-79-118 FRC Project Nr.C5257 P g3 00 Fr:nklin Research Center A DMsson of The Frankhn Institute FRC Assignment No.13 3b 20th and Race Streets. Phila.. Pa. 19103 (215) 44810m FRCTask No. 5 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 3 3.2.6 Solenoid valves As reported in CP&L responses to NRC IE Bulletins 79-01 and 79-01B (45-day report), the listed solenoid valves in containment are to be replaced by qualified equipment. The in-place ASCO solenoid valves have not exhibited poor performance or required excessive maintenance. Fnen manufactured and supplied, ASCO Company was not required to maintain the QC/QA procedures and programs necessary to allow traceability and certification needed for qualification. The replacement valves are also ASCO Company equipment Model Nos. NP831665E, NP8316E35E and 206-381-2U used singly or in combination to achieve their valving function. These solenoid valve types were included in a qualification testing program to meet IEEE Standards 323, 344, and 382. Results of this testing are published in AUTOMATIC SWITCH COMPANY. Test Report No. AQS21678/TR, Revision A, entitled Qualification Tests of Solenoid Valves by Environmental Excosure to Elevated Temperature, Radiation, Wear Aging, Seismic Simulation, Vibration Endurance, Accident Radiation and LOCA Simulation. The test parameters subjected the valves to a maximum temperature of 346 F, a maxi =um pressure of 125 PSIA, a relative humidity of100%,aboratedspraydugingtheLOCAsi=ulationanda total radiation of 2.0 x 10 RADS. The test results are divided into two (2) parts-first the evaluation of the elastomers and coil =aterials and second the valve mechanisms and housing. The elastomers and coil materials, as reported, are qualified for a 4.4 year life (includes a 10% margin figure). The valve proper is qualified for a 40-year life. This will require the coils and elastomers to be replaced on a. scheduled basis to maintain the serviceability of the entire valve as well as its qualification. The proposed schedule is replacement of stated components on a four- (4) year cycle. Replacement will be perfor=ed during.the closest outage or refueling to that time period.

    &                                                          NRC Contract N 3. NRC-03-79-118 00br:nklin R: search Center                                FRC Project NO. C5257               Pag]

A Divison of The FranklinInstitut2 FRC Assignment N;.13 3c 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. # // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. .J 4.6 Solenoid valves Replacement of in-containment solenoid valves identified within this report has been performed during the 1980 refueling outage (August - October,1980). The ASCO valves specified as replacements are considered qualified by similar type testing performed by the manufacturer and reported within available qualification reports (Paragraph 3.1, Reference 47). 8 Additional action required - Noted in the manufacturer's report is a certified life of 4.4 years for the coil and elastomers within these solenoid valves. These elements will be replaced on a four- (4) year cycle to maintain complete operational capability.

ZA NRC Contract N . NRC-03-79-118 000 r:nklin Rrse:xch C;rnter FRC Project N3. C5257 Pig 3 A DMsion of The Frankhn Institute FRC AssignmenJto.13 5 20th and Race Streets. Phila. Pa. 19103(215) 448-1000 FRC Task No. O // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1 Checksheets (( have been removed due to the Proprietary nature of infomation contained therein.- l l l i e

        ,                                                   NRC Contract N . NRC-03-79-118 4)UU b         Frinklin Riserrch C:nt:r                         FRC Project N2. C5257                     Paga A Dnnson of The Franklin Instaure                      FRC Assignment No.13                       lc 20th and Race Streets. Phda . Pa 19103 (215) 4481mo    FRC Task No. - 6//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M EQUIPMENT ITEM NO. 4 SOLENOID VALVE LOCATED IN THE CONTAINMENT, ELEV. 283'0" ASCO MODEL 2063812U REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. 4 LICENSEE REFERENCE (S): 40, 649 FUNCTION (PLANT ID): NOT STATED (V12-7, -9, 13; CVC-200A, B, C) LICENSEE SUBMITTAL: SCEW(S): 20 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) T , @', RT, P, H, S, (R) , M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la _ Sumary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 44-A= '5 4c, ?d, !:, If System Consideration Review Equipment Environmental Qualification Review *= C5, Sc, 5d, 5:, 55, O. 5" C 51, 5j-Installed TMI Lessons Learned Implementation 52, 55 Equipment Summary Maintenance anc Replacement Schedule Summary '2, 75, 7:

NRC Contract Nr. NRC43 79-118 LO0hr:nklin R:se:rch Ccnt:r FRC Project ND. C5257 PCg3 A Dwabn of The Franklin Institute FRC Assignmentjo.13 lb 20th and Race Streets. Phda.. Pa. 19103 (215) 448-Imo FRC Tar.k No. c /I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. y

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: [ Tne Licensee (has/h:2 r t) provided a response to the SER concerns. [ The Licensee (has/h:: n:t) specifically stated that the equipment is qualified and7ec will function when exposed to the applicable DBE ~ environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source l Verify qualification by additional (testing / analysis) l Equipment relocation to a mild environment l Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) ' The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

  - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

(I.n Qualified] II.c Qualified Life Deficiency I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available

NRC Contract No. NRC-03-79-118 pUO0hr:n khn Research C nter FRC Project No.C5257 Page A DMsaon of The Frankhn Instituti FRC Assignment NO.13 2 20th and Race Streets. Ph6ta.. Pa 19103 (215) 448-1000 FRC Task No. C // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. & EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation ' Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate __ o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied ~ Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied l Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified X I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review I IV Documentation Not Made Available l FOR DETAILED EVALUATION SEE ITEM 2 , SHEETS Sa. THROUGH Sf. l l

NRC Contract No. NRC-03 79-118

 @O0hr nklinResearchCenter U                                                              FRC Project Nr. C5257                       Pag)

A Division of The Frankhn Institute FRC Assignment No.13 3a 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1000 FRC Task No. S/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. Y LICENSEE RESPONSE TO NRC SER 4.2 Eouipment Recuiring Additional Information and/or Corrective Action ( Accendix B) The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the folleving: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.

            -      Re-evaluation of CF&L's updated submittals by NRC Region II,                           ,

Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                   - Docket No. 50-261; Plant: H. 3. Robinson 2, dated Nove=ber 6, 1980 and Revised November 11, 1980.

. Telecons with NRC, 3ethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Equipment Descriotion Manufacturer Model No. Location

10. solenoid valve' ASCO NP831665E containment

11. solenoid valve l ASCO NP8316E35E containment

12. solenoid valvg 1 ASCO 206-381-2U contain=ent Notes:

1 As reported in qualification test programs, components and/or materials vill require replacement on a designated schedule to maintain qualification. A. Solenoid Valve ASCO 206-381-2U 1 R,CS,A AIta=s reported as qualified within NRC Region II revised TER, dated 11/7/8C

NRC Contract No. NRC-03-79-118 8UD06cnklin Research Center FRC Project No. C5257 PagJ A Dwoon of The Franklin Instuute FRC Assignment No.13 3b 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITE,M NO. 4

                                                                             ~

3.2.6 Solenoid Valves As reported in CP&L responses to 12C IE Bulletins 79-01 and 79-013 (45-day report), the listed solenoid valves in containment are to be replaced by qualified equipment. The in-place ASCO solenoid valves have not exhibited poor performance or required excessive maintenance. When manufactured and supplied, ASCO , Company was not required to maintain the QC/QA procedures and programs necessary to allow traceability and certification needed for qualification. The replace =ent valves are also ASCO Company equipment Model Nos. NP831665E, NP8316E35E and 206-381-2U used singly or in combination to achieve their valving function. These solenoid valve types were included in a qualification testing program to meet IEEE Standards 323, 344, and 382. Results of this testing are published in AUTOMATIC SWITCH COMPAh"f. . Test Report No. AQS21678/TR, Revision A, entitled Qualification Tests of Solenoid Valves by Environmental Excesure to Elevated Temperature, Radiation, Wear Aging, Seismic Simulation, Vibration Endurance, Accident Radiation and LOCA Simulation. The test para =eters subj ected the valves to a maximum temperature of 346*F, a maxi =um pressure of 125 PSIA, a relative humidity of100%,aboratedspraydugingtheLOCAsi=ulationanda total radiation of 2.0 x 10 RADS. The test results are divided into two (.2) parts-first the evaluation of the elastomers and coil materials and second the valve mechanisms and housing. l The elastomers and coil materials, as reported, are qualified for a 4.4 year life (includes a 10% margin figure). The valve proper is qualified for a 40-year life. This will require the coils and elastomers to be replaced on a. i scheduled basis to maintain the serviceability of the entire valve as well as its qualification. The proposed schedule is l replacement of stated components on a four- (4) year cycle. l Replacement will be perfor=ed during the closest outage or refueling to that time period. I l l l l b

AUOOU Fr:nklin R: search C;nter NRC Contract ND. NRC-03-79-118 P g3 FRC Pro}ect No. C5257 A Divisu>n of The Frankhn Institute FRC Assignment No.13 3C 20th and Race Streets, Phda.. Pa. 19103 (215) 44810m FRC Task No. 8/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M 4.6 Solenoid Valves Replace =ent of in-containment solenoid valves identific1 within this report has been performed during the 1980 refueling outage (August - October,1980) . The ASCO valves specified as replacements are considered qualified by similar type testing performed by the manufacturer and reported within available qualification reports (Paragraph 3.1, Reference 47) . Additional action required - Noted in the manufacturer's report is a certified life of 4.4 years for the coil and elastomers within these solenoid valves. These elements will be replaced on a four- (4) year cycle to maintain complete operational capability. I l l l . l

A_ NRC Contract N 2. NRC-03-79-118 b{l hFrrnklin Rese:rch Cent:r FRC Pr: Ject N 3. CS257 P:g2 A Dmsson of The Frinkhn Institute FRC Atsignm:nt No.13 lc

                                                                                                  .Tl/

20th and Race Streets. Phila.. Pa 19103 (215) 448 1000 FRC Task No. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. E EQUIPMENT ITEM NO. 5 MOTORIZED VALVE ACTUATOR LOCATED IN THE CONTAINMENT, ELEV. 241'0" LIMIIORQUE MODEL SMB00 WITH PEEP.LESS MOTOR, CLASS B INSULATION REQUIRED OPERATING TIME: 1 HOUR TER CHECKSHEET NO. 5 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): ACTUATES HOT LEG INJECTION VALVES (V-866A, B) LICENSEE SUBMITTAL: SCEW(S): 6 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) T, (fl', RT, P, H, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, i Not stated, Not applicable l LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb

Equipment Environmental Qualification Summary Forms 2 l

l Licensee Response to NRC SER 3a, 3b, 3c, 3d System consideration Review M. 45, 50, id, i, if Equipment Environmental Qualification Review Sa,, 5b., Sc, 5d, Se, ! M. 5b ,5c.,5d.,5c.. K Sg ch, si. Installed TMI Lessons Learned Implementation 52, 5b j Equipment Summary l Mairstenance and Replacement Schedule Summary "I = * "' c -

NRC Contract N3. NRC-03-79-118 LO0hnnklin R:seirch Ccnter FRC Project N .C5257 P g3 A DMsion of The Franklin Institute FRC Asaignment No.13 lb 20th and Race Streets. Phda.. Pa. 19103 (215) 448-tmo FRC Task No. 8 // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: U Tne Licensee (has,S:: ..; M provided a response to the SER concerns. [ The Licensee (has/he.; ..e:.) specifically stated that the equipment is qualified and*/y will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipm9nt replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) l The Licensee has provided other information for this equipment item j that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

   - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a -Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt g 11.e Qualification Not Establishedj III,b Not in Scupe II.b Not Qualified IV Documentation Not Available

AUO0hr:nklin Research C:nter NRC Contract No. NRC 03-79-118 FRC Project No.C5257 Page A DMsen of The FranklinInstitute FRC Assignment No.13 2 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRCTask No. 81l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate X Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) X Program Established to Identify Aging Degradation X Criteria Regarding Aging Simulation Satisfied (If Required) 1 Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied . Criteria Regarding Radiation Satisfied V Criteria Regarding Test Sequence Satisfied X Criteria Regarding Test Failures or Severe Anomalies ,._ (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established 1 II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available

NRC Contract No, NRC-03 79-118

@O0hr'nklin Research Center U                                                                FRC Project No,C5257                     Page A DMson of The Frankhn Inst ut.                             FRC Assignment No.13                      30 20th end n.c. sir.ets, Phd... Ps. 19103 (215) 448-1000      FRC Task No. 4~l l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. [

LICENSEE RESPONSE TO NRC SER 4.2 Ecuipment Recuirine Additional Information and/or Corrective Action (Apeendix 3) The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following:

           -     Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.
           -      Re-evaluation of CP&L's updared submittals by NRC Region II, Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report
                  - Docket No. 50-261; Plant: H. 3. Robinson 2, dated November 6,1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Ecuipment Description Manufacturer Model No. Location 3 1- pu p roter

                                                        'M e tinghoue -         506UD?           ^""d>=

s.*a44nment

2. motor operator Limitorque SMB-00 . containment A. Motor Operator Limitorque 'SMB-00 1 R,CS,A A

Icess reported as qualified within NRC Region II revised TER, dated 11/7/80.

                                                                                                   $    1

A NRC Contract No. NRC 03 79-118 000Er:nklin Research Center FRC Project No. C5257 Page A DMsion of The FrankhnInstitute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m FRC Task No. ffI EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I LICENSEE RESPONSE 1D NRC SER The items within Appendix 3 not fully covered by eith'er TER classification or SCEWS's are as follows: Eculptsent Descriotion Manufacturer Mod el No . I,ocation Motor Operator Limitorque SMB-3 containment Transmitter Rosemount 1153A . containment Level Switch Madison 5602 containment Silicon Rubber Tape 3M Scotch 70 containment The Limitorque motor operators of type SMB-3 are operators with motor brakes. Two are in the master list - V744A and V7443. These operators were required by Westinghouse to be upgraded to speelal service by Limitorque before installation. Data is in file denoting the requirements and certification that these operators were modified for their intended service. Under review is the currently available 53 Model Lisitorque . Operators t.ich perform similar function without a motor brake. When completed, a recommendation and disposition will be made to the NRC. At the present time , the installed SMB-3 operators are considered adequate for thet: service and qualified for their environment. N r o I t l l

4UOOU Franklin Research Center NRC Contract NO. NRC-03 79-118 FRC Project ND.C5257 Pag] l A Dwon of The Franklin insutute FRC Asalgnment Ro.13 3 c. 20th and Race Streets. Phda.. Pa. 19103 (215) 44810m FRC Task No. 5 II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I 3.2.3 Motor-operated valves CC Within containment at H. B. Robinson four (4) =otor operators are used for valve actuation for the listed equipment in this report. They are: V-744A and V,744B. Auxiliary Cooling System and V-866A and V-866B, Safety Inj ection System. They are Limitorque Models SMB-00 (V-866A,B) and SMB-3, with motor brake (V-744A,B). Torque motors for V-744A&B have been wound with Class H insulation. V-866A&B Torque motors and V 744A&B l SI motor brakes are wound with Class B insulation. Model SMB-00 has a Peerless built torqua motor and Model SMB-3 has a Reliance built torque motor. Qualification testing of Limitorque motor operators was perfor=ed by Franklin Institute Research Laboratories and the test reports included in Westinghouse WCAP 7410-L. Environmental Testing o_f, Engineered Safety Features Related Equipment. Limitorque Model SMB-Os, with and without motor brake, and Class B and Class H insulation were used during the tests. The results are applicable to the Models SMB-00 and SMB-3 used at H. B. Robinson as differences are dimensional and in torque rating only. The qualification testing perfor=ed by FIRL encompasses the temperature, pressure, relative humidity and chemical :: pray para =eters for H. B. Robinson; therefore, the Limitorque motor operations within containment are considered qualified per these parameters for H. B. Robinson operation. Of concern was motor brake operation due to the results of FIRL Final Report F-C2485-01, Tests of a Limitorcue Valve Operator and Motor Brake Assembly, Both with Class B_ Insulation _Under Simulated Reactor Containment Post Accident Steam and Chemical Environments. Failure of the motor brake with sub-sequent valve operator failure was reported as occurring after seven (7) days within the test program. Performance prior to this ti=e was recorded as satisfactory. Since the H. B. Robinson application of the motor brake, valve operator com-bination occurs within five (5) minutes after LOCA initiation, it is concluded that the intended function of this equipment will be met by the installed equipment; no further qualifying or changeout is planned. Radiation exposure and aging tests are described within Westinghouse NCAP 7744, Environmental Testing o_f_ Engineered Safety gFeatures Related Ecuipment. Total irradiation to 2 x 10 RADS and a thermal aging equivalent to forty (40) years is reported. Support data for these tests are on request from from Westinghouse and will be made available for review when received.

A~ NRC Contract NJ. NRC-03-79-118 Page 0000 Fr:nklin R:se:rch Ccnter FRC Pro}ect NO.C5257 A DMsaon of The Franklin Institute FRC Assignment No.13 3d 20th and Race Streets. Phca.. Pa. 19103 (215) 448-10M FRC Task No. 8Il EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I Outside of contain=ent for long-term accident mitigation are additional Limitorque motor valve operators which will be exposed to elevated radiation levels only. These are CVC.381, R1 V-860A, V-8603, V-861A, V-8613, V-863A, V-863B, V-869. The Limitorque c:odels used are S18-00 and SMB-1. No motor brakes are associated with these operators. As stated previously, WestinghouseWCAg7744reportsatestwhichachievedirradiation levels of 2 x 10 RADS with no failures encountered. CP&L has requested copies of the test data from Westinghouse, and it will be made available upon receipt.- No other accident environ =ent parameters are experienced at this location; therefore, CP&L considers these motor valve operations qualified for their intende,d use and location. l i i I

        .                                                       NRC Contract N 2. NRC-03-79-118 d00J Fr nk!In R:se rch C:nter                               FRC Project N3.C5257              PJg3 A Divisk>n of The Franklin Institute                    FRC Assignment No.13               5 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No.f//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1 Checksheets[a 3 2 bEC / 2 have been removed due to the proprietary nature of information contained therein.- l l l l

A NFIC Contract No. NRC-03-79-118 000binklin Rise:rch Ccnter FRC Project N2 C5257 Pag 3 A Division of The Frankhn Institute FRC Assignment No.13 5 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTask No. A~// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. S. Checksheets gf h f4 have been removed due to the proprietary nature of information contained therein.-

As NRC Contract Nr. NRC-03-79-118 b0kFr:nklin R:se:rch Cant:r FRC Project N3. C5257 Pago A Dimson of The Frankhn Insntute FRC Assignment No.13 lc 20th and Race Streets. Phda.. Pa 19103(215)448 1000 FRC Task No. 8/ / EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. b EQUIPMENT ITEM NO. 6 MOTORIZED VALVE ACTUATOR LOCATED IN THE CONTAI!EENT, ELEV. 245' LIMITORQUE MODEL SMB3 WITH RELIANCE MOTOR, CLASS H INSULATION; MOTOR BRAKE, CLASS B INSULATION REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. 6 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLAlfr ID): ACTUATES REACTOR CORE DELUGE VALVES (V-744A, B) LICENSEE SUBMITTAL: SCEW(S): 9 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NHC SER - CIRCLED ITEM (S) ONLY: (Ste Section 3 of this TER for Legend) T, QT, RT, P, H, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Centents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 3d Syctem Consideration Review 't. th. I, if, I;, if Equipment Environmental Qualification Review Saf Sb,, Sq, 5d, Sei, 5%. A. Sc #uS4 SF . 'Sg , Sh , S L , Sj Installed TMI Lessons Learned Implementation 'r. Equipment Sununary Maintenance and Replacement Schedule Summary 's. 'b, ?r

1 NRC Contract Ns. NRC-03-79-118 ~ LODJ Fr:nkhn R:serrch Center FRC Project Ns. C5257 P g3 A Divwon of The Frinkhn Instuuu FRC Assignm:nt Ng.13 lb 20th and Race Streets. Phde.. Pa- 19103 (215) 448 1000 FRC Task No. G // j EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 6

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: d Tne Licensee (has/"- M provided a response to the SMR concerns. [The Licensee (has/hes-.aot) specifically stated that the equipment is qualified and N will function when exposed to the applicable-DBE ~ environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. 1 Justification for interim operation (has/has not) been provided by the i Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment i Equipment modification } Equipment relocation above submergence level ) Relocate or shield equipment from radiation source ! Verify qualification by additional (testing / analysis)

Equipment relocation to a mild environment 1

Qualification testing of equipment in progress Other (

                                                                                                                                              )

1 The Licensee has provided other information for this equipment item that can be construed as a basis for justification for. interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action . ) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification.

                                                                                                                                        ~

DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

                          - CIRCLED ITEM ONLY                     (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification , III.a Exempt III.b Not in Scope lII.aQuaAII1cationNotEstablished) II.b Not Qualified

                                                                                      ~

IV Documentation Not Available

  ,+
     -cryy        y - -        -%      c.   .-    ,.              + - . , - - -   -

wwq-- - p.-

NRC Contract N3. NRC 03 79-118 00 Frrnklin R se:rch Center FRC Project N;. C5257 Pa0e A DMoon of The Frankhn Institute FRC Assignment No 13 2 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. 5Il EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./s_. i i EQUIPMENT ENVIRONMk.N.4L QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY l Documented Evidence of Qualification Adequate X J Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) A Program Established to Identify Aging Degradation i Criteria Regarding Aging Simulation Satisfied (If Required) 1 Criteria Regarding Temperature / Pressure Exposares o Peak Temperature Adequate o Peak Pressure Adequate-o Duration Adequate o Required Profile Enveloped Adequately - o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied X < Criteria Regarding Test Sequence Satisfied X Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied i Criteria Regarding Instrument Accuracy Satisfied Tast Duration Margin (1 hour + Function Time) Satisfied 1 Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: f X = CATEGORY NRC QUALIFICATION CATEGORY I.e Equipinent Qualified . I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established Y II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life , or Replacement Schedule Justified _ III.a Equipment Exempt From Qualification - III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available O

       -~-                  ,-           t                     , , , . - - ,     ,           - - , - . , - . , . .

A NRC Contract No. NRC-03 79-118 s 000Er:nklin Research Center FRC Project ND.C5257 Pag 3 .. A DMsion of The FrankhnInsutute FRC Assignment N .13 3a 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1 2 0 FRC Task No. /I , EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO./g ss-LICENSEE RESPONSE TO NRC SER ' 4.2 Youtoment Recuirine Additional Information and/or Corrective Action g .- (Accendix 3) ( )

                                                                                          ~

The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. '- Re-evaluation of CP&L's updated submittals by NRC Region II, , g Atlanta, GA, and reported in Environmental Qualification of Safety- s Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                 - Docket No. 50-261; Plant:                   H. 3. Robinson 2, dated November 6, s1980 and Revised November 11, 1980.                                                            '

Telecons with NRC, Bethesda, MD reviewing personnel July 29,- l981, et al. . A. Motor Operator Limitorque SMB-3 1 R,CS,# A Items reported as qualified within NRC Region II revised TER, dated 11/7/80.- '- s hO s

                                                                                                                   \
                                                                                                                       \

4 a-+. NRC Contract NT. NRC-03-79-118 00 Frnklin Research C nter FRC Project NT. C5257 P gJ A Dwon of The Frankhn Insutute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. 5II EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .d. LICENSEE RESPONSE TO NRC SER (Continued) The items within Appendix B not fully covered by eith'er TER classification or SCEWS's are as follows: Equipment Descriotion Manufseturer Model No. Location

     '      Motor Op.arator                              -Limitorque            SMB-3          containment Transmitter                                   Rosemount            1153A          containment s'

Level Switch Madison 5602 containment Silicon Rubber Tape 3M Scotch 70 containment x The Limitorque motor operators of type SMB-3 are operators with m.::oe brakes. Two are in the master list - V744A ard V7443. These operators were required by Westinghouse to be upgraded to special service by Limitorque before installation. Data is in ' file denoting the requirements and certification that these operators were modified for their intended service. Under review is the currently available SB Model Limitorque Operators which perform similar function without- a motor brake. When completed, a recommendation and disposition will be made to the NRC. At the present time, the installed SMB-3 operators are considered c.dequate for their serrice and qualified for their environment. 9

N. NRC Contract No. NRC-03-79-118 FRC Project No. C5257 Pag 3 00 Franklin Research Center A Divwon of The Franklin Institute FRC Asalgnment N S.13 3c 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1000 FRC Task No. ElI - EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _[a. 3.2.3 Motor-Cperated valves p Within containment at H. B. Robinson four (4) motor operators are used for valve actuation for the listed equipment in this report. They are: V-744A and V,.7443, Auxillcry Cooling System and V-866A and V-866B, Safety Inj ection System. They are Limitorque Models SMB-00 (V-866A,B) and SMB-3, with motor brake (V-744A,B) . Torque motors for V-744A&B have been wound with Class H insulation. V-866A&B Torque motors and V 744A&B l SI motor brakes are wound with Class B insulation. Model SMB-00 has a Peerless built torque motor and Model SMB-3 has a Reliance built torque motor. Qualification testing of Limitorque motor operators was perfor=ed by Franklin Institute Research Laboratories and the test reports included in Westinghouse WCAD 7410-L, Environmental Testing g Engineered Safety Features Related Equipment. Limitorque Model SMB-Os, with and without motor brake, and Class B and Class H insulation were used during the tests. The results are applicable to the Models SMB-00 and SMB-3 used at H. B. Robinson as differences are dimensional and in torque rating only. The qualification testing perfor=ed by FIRL encompasses the temperature, pressure, relative humidity and chemical spray parameters for H. B. Robinson; therefore, the Limitorque motor operations within containment are considered qualified per these parameters for H. B. Robinson operation. Of concern was motor brake operation due to the results of FIRL Final Report F-C2485-01, Tests g a Limitorque valve Operator and Motor Brake Assembly, Both with Class B, Insulation Under Si=ulated Reactor Containment Post Accident Steam and

    .          Chemical Environments. Failure of the motor brake with sub-sequent valve operator failure was reported as occurring after seven (7) days within the test program. Performance prior to this time was recorded as satisfactory.                        Since the H. B.

Robinson application of the motor brake, valve operator com-bination occurs within five (5) minutes af ter LOCA initiation, it is concluded that the intended function of this equipment will be met by the installed equipment; no further qualifying or changeout is planned. Radiation exposure and aging tests are described within Westinghouse WCAP 7744, Envircr:= ental Testing of_ Engineered Safety Features Related Q u > ent. Total irradiation to g 2 x 10 RADS and a thermal aging equivalent to forty (40) years is reported. Support data for these tests are on request from from Westinghouse and will be made available for review when rece1ved.

NRC Contract N t. NRC-03-79-118 Pag 3 L0branklin Research Ccnter FRC Pro}ect N2. C5257 A Divts.on of The Frankhn Insnture FRC Assignment No.13 3d 20th and Race Streets. Phda.. Pa. 19103 (215) 44810M FRC Task No. Y ll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _/2 Outside of contain=ent for long-ters accident citigation are additional L1=itorque =otor valve operators which vill be exposed to elevated radiation levels only. These are CVC.381, R2 V-860A, V-8603, V-861A, V-8613, V-863A, V-8633, V-869. The Limitorque models used are SM3-00 and SM3-1. No =otor brakes are associated with these operators. As stated previously,

    'Jestinghouse 'JCAj 7744 reports a test which achieved irradiation levels of 2 x 10 RADS with no failures encountered. CP&L has requested copies of the test data from *iestinghouse, and it will be made available upon receipt.- No other accident environment parameters are e:cperienced at this location; therefore, C?&L considers these =otor valve operations qualified for their intended use and location. C i Q                                                               '

4 L

A NRC Contract N3. NRC-03-79-118 ghranklin UO0 Rise rch C ntr.r FRC Project N3.C5257 P;g3 A Divtsson of The Frankhn Institute FRC Assl9nment No.13 5 20th and Race Streets, Phila., Pa. 19103 (215) 448-1000 FRCTask No. #// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _6r. Checksheets [a p 2 C & f,a have been removed due to the proprietary nature of information contained therein..

NRC Contract Ns. NRC-03-79-118 4'ennuiin 000u arse:rch Csnt:r FRC Project No. C5257 P g3 A Division of The Franklin Institute FRC Assignment No.13 5 20th and Race Streets. Phila.. Pa. 19103 (215) 448-10m FRC Task No. S// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _(_. Checksheets . fydb6'/ have been removed due to the proprietary nature of information contained therein.- l

A NRC Contract N2. NRC-03-79-118 UO0EFrznklin R:se:rch Cantir FRC Project No. C5257 P ga A Divisen of The Franklin Institute FRC Asaignment No.13 Ia 20th and Race Streets. Phila . Pa. 19103 (215) 448-1000 FRC Task No. 8/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 7 EQUIPMENT ITEM NO. 7 MOTORIZED VALVE ACTUATOR LOCATED IN THE REACTOR AUXILIARY BLDC. LIMITORQUE MODEL SMB00 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 7 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): ACTUATES HOT LEG IRJECTION BORON INJECTION VALVE (V869) LICENSEE SUBMITTAL: SCEW(S): 7 0F 25 [20] FUNCTION (PLANT ID): ACTUATES RHR DISCHARGE TO SI SPRAY SYSTEM VALVES (V863A, B) LICENSEE SUBMITTAL: SCEW(S): 12 0F 25 [20] FUNCTION (PLANT ID): ACTUATES REACTOR COOLANT PUMP SEAL WATER RETURN VALVE (CvC-381) LICENSEE SUBMITTAL: SCEW(S): 23 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (Sse Section 3 of this TER for Legend) T , Q1', P, H, CS, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la l Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, M Syctem Consideration Review 's, th, tc, If, I;, if Equipment Environmental Qualification Review 52, 55, 5;, 5d, Se, if, Sg, Sh, Si, Sj Installed TMI Lessons Learned Implementation '2 65 Equipment Summary Maintenance and Replacement Schedule Summary 'r. 'b. M

NRC Contract N2. NRC-03-79-118 dhrinklin Rxse rch Cent:r FRC Project N .C5257 Pag 3 A Division of The Frankhn Institute FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa. 19103 (215) 44810m FRC Task No. 8// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 7 SucetARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: M Tne Licensee (has/':: ::t) provided a response to the SER concerns. ( The Licensee (has;'h:: .;t) specifically stated that the equipment is qualified and7ag will function when exposed to the applicable DBE ' environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not.) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) l l The Licensee has provided other information for this equipment item l that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not requira qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

  - CIntCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt III.b Not in Scope 1II.aQualificationNotEstablished} II.b Not Qualified IV Documentation Not Available

41100U Fr nklin R; search Ccnter NRC Contract No. NRC-03 79-118 FRC Project No. C5257 Page A DMoon of The Frankhn Institute FRC Assignment N J3 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ~7 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate X Adequate Similarity Between Equipment and Test Specimen Established X X

                                                                              ^

Aging Degradation Evaluated Adequately Qu211fied Life or Replacement Schedule Established (If Required) Y Program Established to Identify Aging Degradation X Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied TJct Duration Margin (1 hour + Function Time) Satisfied __ Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC CUALIFICATION CATEGORY X = CATEGORY j I.c Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established 1 II.b Equipment Not Qaslified II.c Equipment Satisfies All Requirements Except Qualified Life i or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available I l t

NRC Contract N 2. NRC-03-79-118 0 Fr:nklin R: search C',nter FRC Project No. C5257 Page A DMston of The Frankhn Institute FRC Assignment NO.13 30 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. 5/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. 7 LICENSEE RESPONSE TO NRC SER 4.2 Eouiement Recuiring Additional Information and/or Corrective Action (Accendix 3 The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following:

            -      Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.
            -      Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report
                   - Docket No. 50-261; Plant:                   H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, 3ethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Eeulement Descriotion Manufacturer Model No. Location

1. pu=p c:otor tiestinghouse 506U?Z outside l containment

2. motor operator Limitorque SMB-00 . containment

3. motor operator Limitorque SMB-00 outside containment

  ^*   Motor Operator                    Limitorque               SMB-00              2          R,RT,A Items reported as qualified within TRC Region II revised TER, dated 11/7/80.-

Cab

l NRC Contract No NRC-03-79-118 FRC Project No. C5257 Pag') 00 FranklinResearchCenter A Divmon of The Frankhn Institute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m FRCTask No. S 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITE,M NO. } Motor-Operated valves {Q Within containment at H. B Robinson four (4) motor operators are used for valve actuation for the listed equipment in this report. They are: V-744A and W7443. Auxiliary Coolind System and V-866A and W8663, Safety Inj ection System. They are Limitorque Models SMB-00 (W866A,B) and SMB-3, with motor brake (V-744A,B). Torque motors for W744A&B have been wound with Class H insulation. W866A&B Torque motors and W744A&B l SI motor brakes are wound with Class B insulation. Model SMB-00 has a Peerless built torque motor and Model SMB-3 has a Reliance built torque motor. Qualification testing of Limitorque motor operators was performed by Franklin Institute Research Laboratories and the test reports included in Westinghouse WCAP 7410-L, Environmental Testing of_ Engineered Safety Features Related Equipment. Limitorque Model SMB-Os, with and without motor brake, and Class B and Class H insulation were used during the tests. The results are applicable to the Models SMB-00 and SMB-3 used at H. B. Robinson as differences are dimensional and in torque rating only. The qualification testing perfor=ed by FIRL encompasses the temperature, pressure, relative humidity and chemical spray parameters for H. B. Robinson; therefore, the Limitorque motor operations within containment are considered qualified per - these parameters for H. B. Robinson operation. Of concern was motor brake operation due to the results of FIRL Final Report F-C2485-01, Tests of_ a_ Limitorque Valve Operator and Motor Brake Assembly, Both- with Class B_ Insulation Under Simulated Reactor Containment Post Accident Steam and Chemical Environments. Failure of the motor brake with sub- _. n sequent valve operator failure was reported as occurring after l seven (7) days within the test program. Performance prior to this time was recorded as satisfactory. Since the H. B, Robinson application of the motor brake, valve operator com-bination occurs within five (5) minutes af ter LOCA initiation, it is concluded that the intended function of this equipment will be met by the installed equipment; no further qualifying or changeout is planned. Radiation exposure and aging tests are described within l Westinghouse WCAP 7744, Environ = ental Testing o_f, f Engineered Safety, Features Related Ecuipment. Total irradiation to i 2 x 10* RADS and a thermal aging equivalent to forty (40) l years is reported. Support data for these tests are on request from from Westinghouse and will be =ade available for review when received.

NRC Contract N;. NRC-03-79-118 00 Frrnklin Rxsearch C:nter FRC Project N;. C5257 Page A Diwston of The Frankhn Institute FRC Assignment N t.13 3c 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTask No. 8/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO Outside of containment for long-ters accident mitigation are additional L1=itorque motor valve operators which will be , exposed to elevated radiation levels only. ihese are CVC.381, R 2. V-860A, V-8603, V-861A, V-8613, V-863A, V-8633, V-869. The Limitorque models used are SMB-00 and SMB-1. No motor brakes are associated with these operators. As stated previously, Westinghouse WCAP d 7744 reports a test which achieved irradiation levels of 2 x 10 RADS with no failures encountered. CP&L has requested copies of the test data from Westinghouse, and it will be made available upon receipt.- No other accident environ =ent parameters are e:cperienced at this location; therefore, CP&L considers these motor valve operations qualified for their intende,duseandlocation.(gf}

NRC Contract N3. NRC-03-79-118 pErinklin UDD R:se rch Cint:r FRC Project N3. C5257 P g3 A DMuon of The Franklin Institut2 FRC A:signm:nt N3.13 5g 20th and Race Streets. Phila.. Pa. 19103 (215) 44810m FRC Task No. 5 II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I wrss:

1. % Li k_mo ah4 .

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2. Test Saecimen - The test specimen should be the same model as. the ecuipment being qualified. The type test should only be considered valid I for equipment identical in design and material construction to the test specimen. Any deviations should be evaluated as part of the qualifica -

tion documentation (see also Section 8.0 below)I ...,

z. ec,e +aca L,w M Bddal9 en L ,wA '4 , A t'% , M .

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        ,aws 'aAs                                                           uw % -,u.

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4UOOU Fr:nk!!n R: search Center NRC Contract No. NRC-03-79-118 FRC Project N3. C5257 Page A DMsion of The Frankan Insatute FRC Assignment Nr.13 5h 20th and Race Streets. Phde.. Pa. 19103(215) 448 1 2 0 FRC Task No. 5 Ii EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 7 wrzs: 1si$ .

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   -                       D A>                     1m $    j's   dM1                   b Nh0 M A at'a                /                                               !

Od

As NRC Contract N O. NRC-03-79-118 P;g3 ddU Franklin Reserrch Csnter FRC Project N2. C5257 A Dwrsion of The Franklin insnrure FRC Assignment No.13 lc 20th and Race Streets. Phda.. Pa 19103 (215) 448 1000 FRC Task No. 5*// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I EQUIPMENT ITEM NO. 8 MOTORIZED VALVE ACTUATOR LOCATED IN THE REACTOR AUXILIARY BLDC. LIMITORQUE MODEL SMB1 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 8 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANI ID): ACTUATES CV SUMP TO RHR SUCTION VALVES (V860A, B) LICENSEE SUBMITTAL: SCEW(S): 10 0F 25 [20] FUNCTION (PLANI ID): ACTUATES CV SUMP TO RHR SUCTION VALVES (V861A, B) LICENSEE SUBMITTAL: SCEW(S): 11 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (S;e Section 3 of this TER for Legend) T, QT, P, H,'CS, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 3d-Syctem Consideration Review d2, $5, t:, Id, k, if Equipment Environmental Qualification Review *b, 50, Ed, 50, Sf, Sg,Sh,Si,Sj Installed TMI Lessons Learned Implementation fr. 55 Equipment Summary Maintenance and Replacement Schedule Summary '- '5, 'r-

4du Fr nklin R:serrch Cant;r NRC Contract N r. NRC-03-79-118 FRC Project Nr. C5257 Pag 3 A DNmon of The Fr:nklin Instituti FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa.19103 CIS) 448-1000 FRC Task No. SI / EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 9

SUMMARY

OF LICENSEE RESPONSES TO THE NRC S1R - ONLY CHECKED ITEMS ARE APPLICABg : X Tne Licensee (has/hummmet) provided a response to the SER concerns. N The Licensee (has/h) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipmen* item that can be construed as a basis for justification for intera operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective l action .) The Licensee states that the equipment item does not requiz 3 qualification and/or should be exempted from environmental qualificatioa. DESIGNATION OF RESULTANT NRC OUALIFICATION EVALUATISN CATEGORY BASED ON REVIEW

      - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt LII.a Qualification Not Establishedl III.b Not in Scope II.b Not Qualified IV Documentation Not Available

AUO0hr:nkhn Research Center NRC Contract No. NRC-03-79-118 FRC Project No. C5257 Page A Otvision of The Frankhn Insmuti FRC Assignment No.13 2 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. < // EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate X Adiquate Similarity Between Equipment and Test Specimen Established X Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) X Program Established to Identify Aging Degradation X Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergenc,e Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied TCat Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established 1 II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life l or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available l

6UO0hrinklin Research Center NRC Contract No. NRC 03 79-118 FRC Project No..C5257 PagD A DMs6on of The Frankhn Institute FRC Assignment N .13 30 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. f LICENSEE RESPONSE TO NRC SER 4.2 Ecutement 'Aecuirine Additional Information and/or Corrective Action (Accendix 3) The bulk of = aster list equipment was placed in this category and our review of deficiencies is based upon the following:

           -      Deletica of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.
            -     Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report
                  - Docket No. 50-261; Plant:                      L 3. Robinson 2, dated November 6,1930 and Revised Nove=ber 11, 1980.

Telecons with NRC, Sethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Eautoment Description Manufacturer Model No. Location

1. pump motor Westinghouse 506UPZ outside containment

2. motor operator Limitorque SMB-00 . containment

3. motor operator Limitorque SM3-00 outside containment

4. motor operator Limitorque SMB-1 outside containment A. Motor Coerato:- t.imitorque SMS-1 2 R,RT,A A

Items reported as qualified within NRC Region II revised TER, dated 11/7/80.* c%

NRCContractNo NRC-03-79-118 Page

  @UUUU Franklin Research Center Project No.C5257             FRC A Dwon of The Franklin Institute                         FISC Assignment No.13           3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000   FRCTask No.     <- M EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1 Motor-Operated Valves                        (lb Within contain=ent at H. B. Robinson four (4) motor operators are used for valve actuation for the listed equipment in this report. They are:                   V-744A and V ,7443, Auxiliary Cooling System and V-866A and V-8663, Safety Inj ection System. They are Limitorque Models SMB-00 (V-866A,B) and SMB-3, with motor brake (V-744A,B). Torque motors for V-744A&B have been wound with Class H insulation.                       V-866A&B Torque motors and V.744A&B motor brakes are wound with Class B insulation. Model SMB-00 has a Peerless built torque motor and Model SMB-3 has a Reliance built torque motor.

Qualification testing of Limitorque motor operators was performed by Franklin Institute Research Laboratories and the test reports included in Westinghouse WCAP 7410-L, Environmental Testing of, Engineered Safety Features Related Equipment. Limitorque Model SMB-Os, with and without motor brake, and Class B and Class H insulation were used during the tests. The results are applicable to the Models SMB-00 and SMB-3 used at H. B. Robinson as differences are dimensional and in torque rating only. The qualification testing perfor=ed by FIRL encompasses the te=perature, pressure, relative humidity and chemical spray parameters for H. B. Robinson; therefore, the Limitorque motor operations within containment are considered qualified per these parameters for H. B. Robinson operation. l Of concern was motor brake operation due to the results of FIRL Final Report F-C2485-01, Tests of_ a Limitorcue Valve Operator and Motor Brake Assembly, Both with Class B_ Insulation Under Simulated Reactor Containment Post Accident Steam and Chemical Environ =ents. Failure of the motor brake with sub-sequent valve operator failure was reported as occurring after j seven (7) days within the test program. Performance prior to this time was recorded as satisfactory. Since the H. B. Robinson application of the motor brake, valve operator com-bination occurs within five (5) minutes af ter LOCA initiation, it is concluded that the intended function of this equipment will be met by the installed equipment; no further qualifying or changcout is planned. Radiation exposure and aging tests are described within Westinghouse WCAP 7744, Environmental Testing o_f. Engineered Safety Features Related Eauipment. Total irradiation to g 2 x 10 RADS and a thermal aging equivalent to forty (40) years is reported. Support data for these tests are on request from from Westinghouse and will be made available for review when received.

AUO0hrinklin R: search C:nter NRC Contract No. NRC-03-79-118 FRC Pro}ect N . C5257 Pag 3 A DMsion of The Franklin Institute FRC Assignment No.13 3C 20th and Race Streets. Phila.. Pa. 19103 (215) 448 l @ 0 FRC Task No. 8 /I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1 Outside of containment for long-ters accident mitigation are additional Limitorque motor valve operators which will be exposed to elevated radiation levels only. These are CVC.381, V-860A, V-8603, V-861A, V-861B, V-863A, V-863B, V-869. The Limitorque models used are SMB-00 and SMB-1. No motor brakes are associated with these operators. As stated previously, WestinghouseWCAg7744reportsatestwhichachievedirradiation levels of 2 x 10 RADS with no failures encountered. CP&L has requested copies of the test data from Westinghouse, and it will be made available upon receipt.- No other accident environ =ent parameters are experienced at this location; therefore, CP&L considers these motor valve operations qualified for their intende,d use and location. C/C3 w - --

            ,                                                     NRC Contract N2. NRC-03-79-118 00 Frinkhn Research Ccnter                                   FRC Project No. C5257                  PaQ3 A Divise,n of The Franklin Ir.stitut2                     FRC Assignment No.13                    5g 20th and Race Streets. Phita.. Pa. 19103 (215) 448 1000   FRC Task No.      5Ii EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 6 wrzs:

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#A                                                           NRC Contract NO. NRC-03-79-118 P:ga L0bEFranklin Rese1rch Csnt:r                                FRC Pr: Ject NO. C5257 A Divmon of Ths Frankhn Ins:stute                       FRC Assignm'_nt N .13                      lo 20th and Race Streets. Phila . Pa 19103 (215) 448-Imo   FRC Task No.      5I/

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 9 EQUIPMENT' ITEM NO. 9 FLOW TRANSMITTER LOCATED IN THE REACTOR AUXILIARY BLDG. FISCHER AND PORTER MODEL 10B2496PBBABBB REQUIRED OPERATING TIME: 30 DAYS TER CHECKSHEET NO. 9 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): MONITORS SAFETY INJECTION HEADER HOT LEG FLOW (FT-940) LICENSEE SUBMITTAL: SCEW(S): 1 0F 25 [20] FUNCTION (PLANI ID): MONITORS SAFETY INJECTION HEADER HOT LEG FLOW (FT-943) LICENSEE SUBMITTAL: SCEW(S): 2 0F 25 (20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (S:e Section 3 of this TER for Legend) T, RT, P, H, CS, S, (R) , M, I, QM RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 3d-System Consideration Review S, Ib, I;, 02, 46, 4f Equipment Environmental Qualification Review Sa, 5b, 4+, 5d, Ge, Sf, 5g, Sh, M , 5s-Installed TMI Lessons Learned Implementation ' n Equipment Summary Maintenance and Replacement Schedule Summary  ?:, 7b, 7;

NRC Contract N . NRC-G3-79-118 00 Frsnklin Rrseach Cant:r FRC Project N2. C5257 Pag 3 A Dwon of The Frankhn Instituts FRC Assignment N 13- lb 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m FRC Task No. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 9

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: t ITne Licensee (has/':: .m ) provided a response to the SER concerns. j The Licensee (has/':: =t) npecifically stated that the equipment is qualified andAr will function when exposed to the applicable DBE ' environmental service conditions. d The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment

item whose qualification has not been fully established.

Justification for interim operation (has/has not) been provided by the Licensee for this equipment-item. Corrective action specified by the Licensee Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level i Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item l that can be construed as a basis for justification for interim i operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION E'ALUATION V CATEGORY BASED ON REVIEW j - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend) I I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt j Q Qualification Not Established III.b Not in Scope f II.b Not Qualified l IV Documentation Not Available i

Aw 0000 Fr:nklin R:se rch Ccnter NRC Contract No.. NRC-03-79-118 FRC Project No.CS257 Page A D6 vision of The FranklinInstitute FRC Assignment No.13 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTask No. 5// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 7 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Y Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) X Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied 1 Tast Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established X-II.o Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D ' Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available

NRC Contract No. NRC-03-79-118 lM Fr:nklin Research Center FRC Project No. C5257 Pag 3 A Division of The Frankhn Institute FRC Assignment N *.13 30 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 9 LICENSEE RESPONSE TO NRC SER 4.2 Ecuiement Recuirine Additional Information and/or Corrective Action (Accendix 3) The bulk of master ldst equipment . ras placed in this category and our review of deficiencies i': based upon the following: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evalt.ation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Envircraental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                   - Docket No. 50-261; Plant: H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Eculoment Descriotion Manufacturer Model No. Location

1. pump motor Westinghouse 506UPZ outside containment

2. motor operator Limitorque SM3-00 containment

3. =ocor operator Limitorque SMB-00 outside containment

         , 4. motor operator                              Limitorque            SM3-1          outside containment

5. flow transmitter Fisher & Porter 1032496 outside P3BA33B containment A. Flew Transmitter Fischer & Porter 1032496PE8ABBS 2 R,QT,A,QM

    ^ Items reported as qualified within NRC Region II revised TER, dated 11/7/SO.

Submergence of equipment outside of containment will also be s tttdied . New modification of Auxiliary Building areas due to fire protection requirements need to be evaluated to establish drain paths and/or water acettmulations . Existing reports indicate no detrimental water buildups due to HELB or small pipe breaks, but they do not account for building modification performed in recent months. A report on submergence of safety-related electrical equipment within harsh environ =ent areas in the Auxiliary Building vill be completed and submitted by the date established by the NRC for completion of qualification of safety-related electrical equipment. Qo]

NRC Contract N3. NRC-03-79-118 ' 00 Fr:nklin Research Center FRC Project N;.C5257 R93 i A Dhnston of The Franklininwaute FRC Assignment No.13 3b 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1000 FRC Task No. (// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. P LICENSEE RESPONSE TO NRC SER (Continued) Electronic Transmitters pg] H. B. Robinson's original da_ sign and specification called for ' installation and use of Fisher and Porter electronic trans-mitter for the measurement of Pressure, Level and Flow para - - meters. As stated within CP&L response to NRC IE Bulletin 79-01 and the 45-day response to NRC IE Bulletin 79-01B C?&L preference, to obtain better operation and maintenance per-formance, is to change out the existing transmitters within - containment-to be replaced by Rosemounts' Model No.1153A. Environmental tests performed on Fisher & Porter's trans-mitt,ers (Model No. 10B2496) indicate failure occurs during the high temperature, steam / chemical spray testing stage while attempting to qualify to IEEE 323-1971 parameters. '(Reference WCAP 9157 Environmental Qualification o,f f Saferv-Related Class E Process Instrumentation). I_E c 4

N . NRC Contract No. NRC-03-79-118 00 Fr:nklin R: search C:nter FRC Project No. C5257 PagJ A DWon of The Franun Insutuo 13 3c FRCTask Assignment 0 No;/ l M and Race Streets. PMa.. Pa. 19103 (215) *48 N00 FRC No. EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4 For long-term accident-mitigation, Fisher & Forter trans-mitters, Mcdel Nos. 10B2496 and 50EP1041, located within the Reactor Auxiliary Building are used. Transmitter identification numbers are FT-940, FT-943, PT-934, PT-940 and PT-943. As these transmitters are not exposed to the LOCA accident environment, but will see the' elevated radiation levels associated with reactor coolant recirculation, qualification is limited to their radiation withstand capability. As previously stated, Fisher & Porter 10B2496 transmitters had failed environ = ental testing per IEEE 323-1971 require =ents and reported in WCAP 9157. Failure occurred withing six (6) minutes of operation when in the high temperature /high pressure / spray testing environment (Table A-7, WCAP 9157). It is noted, though, an. d stated, that the " trip" function time of operation for the transmitters was accomplished. This portion of the test program is not relevant to H. B. Robinson use of the listed Fisher & Porter transmitters as they are not within g containment and, therefore, not required to function under the harsh environmental conditions which caused test failure. Within the sc=c report, it is stated that Fisher & Porter transmitters had successfully operated during and after irradiation testing (Table A-6, WCAP 9157) . As only a total radiation level of 4x10*' RADS were achieved, additional qualification was required to meet the radiation requirements established in Table 1.3.3. Westinghouse WCAP.7744, Envircnmental Testing of Engineered Safety Features Related Zauipment states that transmitters, identifiedbyWestinghouseasFisher& Porter,Mcgel10B2496, had been successfully' tested to a level of 2.0x10 RADS. As theligtedFisher&Portertransmittersareexposedtoa 1.1x10 RAD level, they are considered qualified for the application and functions stated within this report. To further identify the transmitters in use at H. B. Robinson with those tested, Westinghouse has stated that instru=ents used were ordered as NS (nonstandard) from Fisher & Porter. Check of purchase order and manufacturer's fabrication instructions show that the listed E. B. Robinson Fisher & Porter transmitters were supplied as NS (nonstandard). Westinghouse has been requested to supply the specific data and/or reports associated with the testing program, and it will be available for review af:er receipt.gg

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     ~                                                        NRC Contract No. NRC-03-79-118                                         *                 %

(O0hr:nklin R:se:rch Ccnter U FRC Project No.C5257 Pag 3 A DMsk>n of The Franklin Institute FRC Assignment No.13 5 ( 20th and Race Streets. Phila., Pa. 19103(215) 448 1000 FRC Task No.8// E2UIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 9 p 4 w. i

                                                                                                                                                   -4 Checksheets ,6~            f"/._ fdff/%4.d., have been removed due to the                                                            !'

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I Z% NRC Contract N3. NRC-03-79-118 g MU Frznklin Reserrch Cent:r FRC Project N2. C5257 l Pag] A Dwison of The Frankhn Institute FRC Assignment No.13 lc FRC Task No. R)th and Race Streets Phila.. Pa 19103 (215) 448-1000 61/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /0 EQUIPMENT ITEM NO.10 t

      ,' PRESSURE TRANSMITTER LOCATED IN THE REACTOR AUXILIARY BLDG.

FISCHER AND PORTER MODEL 50EP1041BCXA REQUIRED OPERATING TIME: 30 DAYS TER CHECKSHEET NO.10 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANI ID): BORON INJECTION TANK HEADER PRESSURE (PT-934) LICENSEE SUBMITTAL: SCEW(S): 3 0F 25 (20] FUNCTION (PLANT ID): SAFETY INJECTION TANK HEADER PRESSURE (PT-943) LICENSEE SUBMITTAL: SCEW(S): 5 0F 25 [20] 5 s

    ', w l,,                                \-

s 8 s !)- 0ESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEN(S) ONLY: (S:e Section 3 of this TER for Legend)

                -T          RT, P, H, CS,              S, (R), M,   I QM RPN, EXN, SEN, QI, RPS, None, Not stated, Not appNicable                       ,

LETING OF APPLICABLE CHECKSHEETS: Crntents '. Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER , lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 3d-System Consideration Review 'r, 55, i, id, h, 4f JEquipment Env! -'nental Qualification Review 6er-55, 5;, 5d, Se, 5f, 5;, 55, Si, Sj In3talled TMI Lessons Learned Implementation 5;, 55 Equipment Summary Ma intenar.ce\ 3nd Replacement Schedule Summary g - ., 72, 75, 7; _i 1

                                         -                             - -rA

As NRC Contract No. NRC-03-79-118 000Er:nkhn Research C:nter FRC Project No.C5257 Page A DM- of The rrankha lascun FRC Assignment No.13 lb 20th and Race Streets. Phita . Pa 19103 (215) 448 10 o FRC Task No. 6// p EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. #

SUMMARY

OF LICENSEE RESPONSES 'IO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: I Tne Licensee (has/L. ..et) provided a response to the SER concerns. 4 The Licensee (has/.'.e; =t) specifically stated that the equipment is qualified and/qp will function when exposed to the applicable DBE environmental service conditions. [ The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation.

The Licensee (has/has not) provided a schedule for the proposed i

corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification j and/or should be exempted from environmental qualification. I DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

 - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt Q Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available

As NRC Contract No. NRC-03 79118 FRC Project No. C5257 Page 00hr:nklin Rese:rch Ccnter A Dwmon of The Frankiminstitute FRC Assignment No.13 2 20th and Race Streets. Phde.. Pa- 19103(215) 448 1000 FRC Task No. F/1 EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. / d EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate , Adequate Similarity Between Equipment and Test Specimen Established Y Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) 4 Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Pequired) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied X_ Tact Duration Margin (1 hour + Function Time) Satisfied _ Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.c Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established Y II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipmbnt Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available ff% A ,$

A NRC Contract No. NRC-03-79-118 UO0hr~nklin Rewarch Center FRC Froject NT. C5257 Page A Dnimon of The Frankhn Instuute FRC Assignment No.13 3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. E /l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./Q. LICENSEE RESPONSE TO NRC SER 4.2 Ecutement Recuirine Additional Information and/or Corrective Action (Accendix B) The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                - Docket No. 50-261; Plant:                     R. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, M3 reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Eeutement Descriotion Manufacturer Model No. Location

1. pu=p motor Westinghouse 506UPZ outside containment

2. motor operator Limitorque SMB-00 . containment

3. motor operator Limitorque SMB-00 outside containment

4. motor operator Limitorque SMB-1 outside containment

5. flev transmitter Fisher & Porter 1032496 outside F33A333 containment

6. pressure transmitter Fisher & Porter 50E?1041 outside 3 CIA containment A. Pressure Transmitter Fischer & Porter 50E?l041aCXA 2 R,QT,A,qM A

Ice =s reported as qualified within NRC Region C revised TIR, dated 11/7/30.

                               +

4UOOU Franklin Rewarch Center NRC Contract No. NRC43 79-118 FRC Project No.C5257 Page A Division of The Frankhn Institute FRC Assignment No.13 3h 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1000 FRCTask No. & EZUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. l9_ LICENSEE RESPONSE '10 NRC SER (Continued) Submergence of equipment outside of containment vill also be studied. "New modification of Auxiliary Building areas due .to fire protection raquirements need to be evaluated to establish drain pathe and/or water accumulations. Existing reports indicate no detrimental water buildups due to HELB or small pipe breaks, but they do not account for building modification performed in recent months. A report on submergence of safety-related , electrical equipment within harsh environmeat areas in the Auxiliary Building vill be completed and submitted by the date established by the NRC for completion of qualification of safety-related electrical equipment. Qo] Electronic Transmitters ~ p H. B. Robinson's original design and specification called for installation and use of Fisher and Porter electronic trans-mitter-for the measurement of Pressure, Level and Flow para-meters. As stated within CP&L response to NRC IE Bulletin 79-01 and the 45-day response to NRC IE Bulletin 79-013 CP&L

             , preference, to obtain better operation and maintenance per-formance, is to change out the existing transmitters within containment--to be replaced by Rose =ounts' Model No. 1153A.

Environmental tests performed on Fisher & Porter's trans-mitters (Model No. 1032496) indicate failure occurs during the high te=perature, steam / chemical spray testing stage while attempting to qualify to IEEE 323-1971 para =eters. (Reference WCAP 9157 Environ = ental cualification g Safetv-Related Class E Process Instru=entation). l

NRC Contract No. NRC 03-79-118 FRC Project No. C5257 Page 00 FranklinResearchCenter A Otv6s6on of The Frank!!n instnute FRC Assignment No.13 3c 20th and Race Streets. Phita.. Pa. 19103 (215) 448N FRC Task No. J7/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /o LICENSEE RESPONSE 'IO NRC SER (Continued) For long-term accident mitigation, Fisher & Porter trans-mitters, Model Nos. 1032496 and 50EP1041, located within the Reactor Auxiliary Building are used. Transmitter identification numbers are FT-940, FT-943, PT-934, PT-940 and PT-943. As these trans=1tters are not exposed to the LOCA accident environment, but will see the elevated radiation levels associated with reactor coolant recirculation, qualification is limited to their radiation withstand capability. As previously stated, Fisher & Porter 10B2496 transmitters had failed envirorrental testing per IEEE 323-1971 requirements and reported in WCAP 9157. Failure occurred withing six (6) minutes' of operation when in the high te=perature/high pressure / spray testing environ =ent (Table A-7, WCAP 9157) . It is noted, though, and stated, that the " trip" function time of operation for the transmitters was accomplished. This portion of the test program is not relevant to H. B. Robinson use of the - listed Fisher & Porter transmitters as they are not within g contain=ent and, therefore. not required to function under the. harsh environmental conditions which caused test failure. - " Within the same report, it is stated that Fisher & Porter- - transmitters had successfully operated during and after irradiation testing (Tablg A-6, WCAP 9157) . As only a total radiation , level of 4x10 RADS were achieved, additional qualification was required to meet the radiation requirements established in Table 1.3.3. ,

                                                                              ~

Westinghouse WCAP 7744, Enviror E ntal Testing of Engineered Safety Features Related Ecuipment states that transmitters, identifiedbyWestinghouseasFisher& Porter,Mcgel 1032496, had been successfully tested to a level of 2.0x10 RADS. As the listed Fisher & Porter transmitters are exposed to a 1.1x10D RAD level, they are considered qualified for the application and functions stated within this report. To further identify the transmitters in use at H. 3. Robinson with those tested, Westinghouse has stated that instruments' used were ordered as NS (nonstandard) from Fisher & Porter. Check of purchase order and =anufacturer's fabrication instructions show that the listed H. 3. Robinson Fisher & Porter transmitters were supplied as NS (ncnstandard), . Westinghouse has been requested to supply the specific data and/or reports associated with the testing program, and it will be available for review af ter receipt.gg

&                                                           NRC Contract Nr. NRC-03-79-118 l.05U Fr:nklin Resesrch Canter                             FRC Pr joct N3.C5257                     P go A Dwmon of The Frankhn Institute                      FRC Assignment No.13                      Ia 21)th and Race Streets. Phda.. Pa 19103 (215) 44810m  FRC Task No. 6//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. // EQUIPMENT ITEM NO.11 PRESSURE TRANSMITTER LOCATED IN THE REACTOR AUXILIARY BLDG. FISCHER AND PORTER MODEL 50EP1041 REQUIRED OPERATING TIME: 30 DAYS TER CHECKSHEET NO.11 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): SAFETY INJECTION HOT LEG HEADER PRESSURE (PT-940) LICENSEE SUBMITTAL: SCEW(S): 4 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (Sta Section 3 of this TER for Legend) T, RT, P, H, CS, S, (R), M, I, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 4d-System Consideration Review II, ti, tc, if, I;, If Equipment Environmental Qualification Review "3 55, 52, 53, 50, 5f, 50, 55, Si, Sj Installed TMI Lessons Learned Implementation 52, Eh Equipment Summary Maintenance and Replacement Schedule Summary '7 ' *

• NRC Contract N3. NRC-03-79-118 00 Frinklin RIseirch Ccnter FRC Project N2. C5257 P g2 A DMsion of The Frankhn Institute FRC Assignment No.13 lb i 20th and Race Streets. Phda.. Pa 19103 (215) 448 1000 FRC Task No. S// l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. #

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: 1 Tne Licensee (has/h;; .4) provided a response to the SER concerns. [ The Licensee (has/hae-not) specifically stated that the equipment is ' qualified and/hp will function when exposed to the applicable DBE environmental service conditions. ' d The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for.this equipment-item. Corrective action specified by the Licensee Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC OUALIFICATION EVALUATION CAT %ORY BASED ON REVIEW

 - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legeno; I.a   Qualified                                             II.c Qualified Life Deficiency I.b   Modification                                          III.a Exempt Q ualification Not Established                               III.b Not in Scope II.b Not Qualified                                           IV    Documentation Not Available

NRC Contract No. NRC-03-79-118 phranklin UO0 R:se:rch Center FRC Project No. C5257 Pag 3 A DMseon of The Frankhn Instaute - FRC Assignment No.13 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTask No. S //

;   EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW CF EQUIPMENT ITEM NO. ./L EQUIPMENT ENVIRONMENTAL QUALIFICATION 

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Mequate Similarity Between Equipment and Test Specimen Established X Aging Degradation Evaluated Mequately X Qualified Life or Replacement Schedule Established (If Required) 1 Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Mequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied X Tcat Duration Margin (1 hour + Function Time) Satisfied __ Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified l I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established Y j II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available Fn 5 ^ 70 ~ ' _y..

A NRC Contract No. NRC-03-79-118 UO0hr:nklin Research Center FRC Project Nr. C5257 Page A Divmon of The Frankhn Institute FRC Assignment No). ,3, 3a 20th and Race Streets. Phila.. Pa. 19103(215) 448 1000 FRC Task No. W EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _#_ LICENSEE RESPONSE 'IO NRC SER 42 Ecutement Recuirine Additional Information and/or t.'orrective ' Act' ion (Accendix B) ,. The bulk of master list equipment was placed in ' this entegory and ' ' our review of deficiencies is based upon the following:

• Deletion of deficient listeh'equipt:ent due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. ,

3

                                                                                            .                .L    -

Re-evaluation of CP&L's updated submittals by NRC Region II, ' Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment II3 79-013. Technical' Dialuation Report

             - Docket No. 50-261; Plant:                     R. 3. Robinson 2, dated November 6,                     1930 and Revised November 11, 1980.

Telecons with NRC, 3cchesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Ecutement Descrietion Manufacturer Model No. Location

1. pump motor Westinghouse 506U?Z outs'ide containment

2. motor operator Limitorque SM3-00 . containment

3. motor operator Limitorque SMB-00 outside contairment

4. motor operator Limitorque SMB-1

                                                                                  ~

outside containment

5. flew transmitter Fisher & Porter 1032496 outside

                                                                           ?33A333                . contain=ent

6. pressure transmitter Fisher & Porter 50E?1041 outside 3 CIA containment A. Pressure Transmitter Fischer & Porter 50E?l041oCXA 2 R,QT,A,QM A

Items reported as qualified within NRC Region II revised TIR, dated 11/7/SO.

NRC Contract No. NRC-03 79-118 FRC Project No. C5257 Pag] 00 Frank!!n Research Center A DMsion of The Frankhninretute FRC Assignment No.13 3b 20th and Race Streets. Phas. Pa. 19103 (215) 448 1000 FRC Task No. (8 EEUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. N LICENSEE RESPONSE 'IO NRC SER (Continued) Submergence of equipnent outside of containment vill 'also 'be studied. 'New modification of Auxiliary Building areas due ,to fire protection - requirements need to be evaluated to establish drain paths and/or water accumulations. Existing reports indicate no detrimental water buildpps due to HEL3 or small pipe breaks, but they do not account for building modification performed in recent months. A report on sub=ergence of. safety-related electrical equipment within harsh environ =ent areas in the Auxiliary Building vill be completed and submitted by the. date established by the NRC for completion of qualification of safety-related electrical equipment. Qo]

                                      ._.     .: _._                ~

Electronic Transmitters {g]

             'H. B. Robinson's original design and specification called for installation and use of Fisher and Porter electronic trans-                     ;

mitter for the measurement of Pressure, Level and Flow para-meters. As stated within CPSL response to NRC IE Bulletin 79 , 01 and the 45-day response to NRC IE Bulletin 79-013 CP&L

            , preference, to obtain better operation and maintenance per-formance, is to change out the existing transmitters within contain=ent--to be replaced by Rosecounts' Model No. Il53A,                    -

Environmental tests performed on Fisher & Porter's trans-mitters (Model No. 1032496) indicate failure occurs during the high temperature, steam / chemical spray testing stage while ( attempting to qualify to IEEE 323-1971 parameters. (Reference l UCAP 9157 Environmental Oualification g Saferv-Related class I_E E Process Instrumentation).

NRC Contract No, NRC-03-79-118 4000u Fr:nklin Research Center FRC Pro}ect N2. C5257 Page A DMsaon of The Frankhn Institute FRC Assignment No.13 3C 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. d~// EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. // LICENSEE RESPONSE 'IO NRC SER (Continued) For long-term accident mitigation, Fisher & Porter trans-

      =1tters, Model Nos. 1032496 and 50EP1041, located within the Reactor Auxiliary Building are used.                         Transmitter identification numbers are FT-940, FT-943, PT-934, PT-940 and PT-943.                               As these transmitters are not exposed to the LOCA accident environ =ent, but will see the elevated radiation levels associated with reactor coolant recirculation, qualification is limited to their radiation withstand capability.

As previously stated, Fisher & Porter 10B2496 transmitters had failed environ = ental testing per IEEE 323-1971 require =ents and reported in WCAP 9157. Failure occurred withing six (6) minutes'of operation when in the high te=perature/high pressure / spray testing environ =ent (Table A-7, WCAP 9157). It is noted, though, and stated, that the " trip" function time of operation for the transmitters was accomplished. This portion of the test program is not relevant to H. 3. Robinson use of the listed Fisher & Porter transmitters as they are not within g containment and, therefore, not required to function under the . harsh environmental conditions which caused test failure. - " Within the same report, it is stated that Fisher & Porter-transmitters had successfully operated during and after irradiation testing (Tablg A-6, WCAP 9157). As only a total radiation , level of 4x10 RADS were achieved, additional qualification was required to meet the radiation requirements established in Table 1.3.3. < . Westinghouse WCAP 7744, Environm ntal Testing f Eneineered Safety Features Related Ecuipment states that transmitters, identified by Westinghouse as Fisher & Porter, Medel 1032496, had been successfully tested to a level of 2.0x10* RADS. As the ligted Fisher & Porter transmitters are exposed to a ' 1.1x10 RAD level, they are considered qualified for the application and functions stated within this report. To further identify the transmitters in use at H. 3. Robinson with those tested, Westinghouse has stated that instru=ents' used were ordered as NS (nonstandard) frc= Fisher & Porter. Check of purchase order and manufacturer's fabrication instructions show that the listed H. 3. Robinson Fisher & Porter transmitters were supplied as NS (nonstandard). Westinghouse has been requested to supply the specific data and/or reports associated with the testing progra=, and it will be available for review after receipt. g g

  #,_%                                                         NRC Contract N 2. NRC-03-79-118 l000 Franklin Research Cantir                               FRC Pr: Ject No. C5257 P:g3 A Dimion of The Frankhn institute                       FRC Assignment No.13                            Ia 20th and Race Streets. Phila., Pa 19103(215) 448-1000   FRC Task No. 8//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /1 EQUIPMENT ITEM NO.12 PRESSURE TRANSMITTER LOCATED IN THE CONTAIt@fENT ROSEMOUNT HODEL 1153A REQUIRED OPERATING TIME: 30 MIN (TABLE 1.3.3) TER CHECKSHEET NO.12 LICENSEE REFERENCE (S): 1764, 4423 FUNCTION (PLANT ID): PRESSURIZER PRESSURE CONTROL SIGNAL (PT-444) FUNCTION (PLANI ID): PRESSURIZER PRESSUSE SIGNAL FOR SIS INITIATION (PT-455) FUNCTION (PLANT ID): FUNCTION NOT STATED (PT-445, -456, -457) LICENSEE SUBMITTAL: SCEW(S): 19 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (Ste Section 3 of this TER for Legend) R, T, QT, RT, P, H, (R) , M, I, RPN, EXN, SEN, QI, None, Not stated, Not applicable ! LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 3d System Consideration Review ^= *" '" #d. 't. 'f Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, 5f, 5g, Sh, ci. *j, Se, , gf,, E* > Sb > S Jo > 0he ,bi ,5o,2 Installed TMI Lessons Learned Implementation Equipment Summary 52, fi gg2 , g 2' 2 Maintenance ana Replacement Schedule Summary 7a, ?b, 7:

__._.m 4000U Frinklin Rrserrch Ccnter NRC Contract N2. NRC-03-79-118 FRC Project Ns.C5257 Paga A Divisen of The Frankhn Insntus2 13 lb 20th and Race Streets. Phila.. Pa. 19103(215) 448-1000 FRC FRC AssignmInt Task No. 8/No.I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _ll.

4 SIMMARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: g Tne Licensee (has/;... ..v4 provided a response to the SER concerns. The Licensee (has/"- -^'-) specifically stated that the equipment is qualified and7qr will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. [ The Licensee (has/hu .4 proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment' item. d Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in rogress _g_ Other ( M n 0- A M '

                                                                                         - M ,r1a b )

N AC /o - 1 The Licensee has provided [other M information f!D #// 3 for thisMequipment M

• it4 ["# m .

that can be construed as a basis for justification for interim operation. E The Licensee (has/ hee-rret) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective

action VM_ .)

l f l The Licensee states that the equipment item does not require qualification ( and/or should be excepted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW i - CIRCLED ITEM ONLY (See Section 3 of this TER for Legend) l I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope Not Qualified IV Documentation Not Available i f

NRC Contract ND. NRC-03-79-118 FRC Project No.C5257 Pag 3 00 Fr:nklin R:se:rch C nter A Divesion of The Frankhn Institute FRC Assignment No.13 2 20th and Race Streets. Phila.. Pa. 19103 (215) 44810m FRC Task No. f1! EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adrquate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately Y Qualified Life or Replacement Schedule Established (If Required) 1 Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied 1 Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied 1 Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tast Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) Y DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified Y II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available g M b v1 A (2 2 j 1) C 2. cd Sh .

NRC Contract N;. NRC-03-79-118 00 Fr .nklin Research Center FRC Project NO. C5257 Page A Divwon olThe Frankhn Insettute FRC Assignment Nr.13 30 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. f/I EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /.a-LICENSEE RESPONSE TO NRC SER 4.2 Ecutoment Recuirine Additional Information and/or Corrective Act' ion (Aeoendix B) {p] The bulk of master list equipment was placed h this category and our review of deficiencies is based upon the following: Deletion of deficient listed" equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region I.I, Atlanca, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IZ3 79-013. Technical Evaluation Report

                   - Docket No. 50-261; Plant:                           H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment deleted due to replacement programs completed at the ~ plant. (Deficiency listings vill not be addressed as these equipments are no longer in place or use at the plant) . Ecutoment Descriotion Manufacturer Model No. Location

                                                                                              ~

1. level transmitter Fisher & Porter 1032496 Containment

2. pressure transmitter Fisher & Porter 50EP10413 CIA-NS Containment

3. flow transmitter Rosemount 1151 '

Containment

4. level transmitter Fisher & Porter 13D2495 Containment

5. solenoid valve ASCO L38211C32 Containment

6. solenoid valve ASCO L38316B25 Containment

7. solenoid valve ASCO L38316B15 Containment

8. solenoid valve ASCO L38316314 Containment

9. level tra'nsmitter ?isher & Porter 1332496 Containment The Rosemount il53A Transmitters are currently qualified to IEEE 323-1971. As reported in our 90-day responses these transmitters require a changeout cycle of ten (10) years with an 0-Ring replacement after each calibration check to =aintain their qualification level. C?&L is part of a utilities group which is underwriting transmitter qualification to IZZE-2 323-1974 standards. As these tests are ongoing, no recommendations or changeout program is being formulated at this time. Upon test completion, C?SL will determine any added transmitter changeout or modification program and report to the NRC its actions.

T

NRC Contract N]. NRC-03-79-118 00 Franklin Research Center FRC Project No. C5257 P g3 A Divmon of The Frankan Institute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa. 19103(215) 448-1000 FRC Task No. Sh EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. l.el. Electronic Transnitters g{ H. 3. Robinson's original design and specification called for installation and use of Fisher and Porter electronic trans-citter for the measurement of Pressure, Level and Flow para-meters. As stated within CPSL response to NRC IE Bulletin 79-01 and the 45-day response to NRC IE Sulletin 79-013 CP&L preference, to obtain better operation and maintenance per-for=ance, is to change out the existing transmitters within

            , containment--to be replaced by Rose =ounts' Model No.1153A.

Environ = ental tests performed on Fisher & Porter's trans-

              =1tters (Model No. 1032496) indicate failure occurs during the high temperature, steas/ chemical spray testing stage while attempting to qualify to IEEE 323-1971 parameters. (Reference WCAP 9157 Enviren= ental cualification of,Safetv-Related    f                 Class E Process Instru=entation).

Qualification testing of Rosemount Model 1153, Series A, per Rose =ount Report No. 3788 states that the transmitter is qualified per the requirements of IFEE 323-1971. Missing from this report is the aging parameter not required for IEEE 323-1971 but necessary for complete 10CA qualification. Recent - Rose =ount testing to qualify a transmitter to meet IEEE 323-1974 requirements has resulted in failure. A co=bination of ther=al aging, irradiation and chemical spray test speci-fication parameters has resulted in failed components. The initial f ailed ele =ent was an 0-ring co= prised of sulphur cured polyethylene rubber. This allowed steam / chemical spray to affect electronic co=ponents. The 0-ring mode of failure is attributed to high te=perature vs. time necessary for the Arrhenius curve ti=e compression to satisfy aging test re-l quirements. This testing failure does not preclude the use of the Rese-mount 1153A within H. 3. Robinson containment as it has successfully perfor=ed within the H. 3. Robinson accident parameters of temperature, pressure and radiation levels., Transmitters located in containment will be required to , perform within a maximum time period of twenty-four (24) hours following accident. 0-ring failure due to high temperature should not occur during this time period. Reviewing Table C-1 of Appendix C, NRC IE Bulletin 79-013, Thermal and Radiation Aging Degradation o_f, Selected Materials, shows that poly-ethylene rubber has a potential for significant aging at t9n (10) years and an allowable radiation susceptibility of 10 RADS before serious degradation occurs. Evaluating the above establishes the need to perform periodic changeout of trans-mitter 0-rings.

4000U Fr:nklin Research Center NRC Contract No. NRC-03-79-118 FRC Project No. C5257 Page A Division of The Frankhn Institute FRC Assignment No.13 3c 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m FRC Task No. T // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _/.t. Additionally, the time span to which Rosemount will qualify its IEEE 373-1974 transmitters is ten (10) years. To assure that listed transmitters within H. B. Robinson contairment re=ain ified a ten- (10) year replacement cycle will be adopted Replacement of in-containment transmitters identified within this report has been performed within the 1980 refueling outage (August - October, 1980). At this time, no fully qualified transmitter is available for nuclear plant in-containment operation. Rose =ount 1153A transmitters, qualified to IEEE 323-1971 version, were used as replacements. Additional action required - A program of periodic transmitter housing 0-ring replacement (performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2.) ,To assure operational capability, a ten- (10) year transmitter replacement schedule has been adopted, to be modified when Rosemount can certify, by test, longer life equipment is available. {j

                                                                 ,-4                        . , , ,

4 NRC Contract No. NRC-03-79-118 FRC Project N2. C5257 Pag 3 UOOU Fr:nklin Research Center A Divisen of The Frankhn Instnute FRC Assignment No.13 3 ,(, 20th and Raca Streets. Phila.. Pa. 19103 (215) 448.imo FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /.1 LICENSEE RESPONSE TO NRC SER (Continued) ! SECTION III - Proposed Corrective Actions for Outstanding Items Electronic transmitters qualified to IEEE-323-1974 are noc currently

  'tvailable.          CP&L is a participating member of the Wisconsin Electric Transmitter Evaluation Program to test and qualify electronic transmitters for nuclear plant use.               Presently, CP&L has upgraded its mastei list transmitters within containment to Rosemount 1153A models which are qualified to IEEE-323-1972. After the current test program is complete - which extends into the fourth quarter of 1982 - CP&L will evaluate the results and decide -on action (s) to be taken to provide fully qualified equipments. In the interim, CP&L has established a program which requires changeout of 0-rings when yearly -

calibration checks are performed and a complete instrument changeout on tan-year cycles after installation dates, to maintain qualification level. D6 l l I l l 1

A NRC Contract No. NRC-03-79-118 000Er:nklin Rese:rch Center FRC Project No. C5257 Page A Dtvmon of The Frankhn Instnute FRC Assignment No.13 50 20th and Race Struts. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /1 EQUIPMENT ENVIROleENTAL QUALIFICATION REVIEW Criteria: DOR Guidelines  ; NUREG-0588, Cat. I /; NUREG-0588, Cat. II . NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.)

                                                    !               ! O fff E A ENT/Al--             1 EQUIPMENT DESCRIPTION                            !       g g7        gA Ef J V/ 6                  !

Equipment Type 1 7gfA/S/fIIII/E  ! Manufacturer's Name  ! (5.2.2/-/-)  !! kOM/fo##I~I! /k056MOuN7~ g Model Number ( 5. 2. 2/-/-)  ! J/f'3A  ! jj f , g/ Serial Number g/g

                                                   !               !  lo G/S(, ThRU       l0G/PS ;

Features / Mounting !NOT* ST/J78D !  ! (5.2.6/-/-)  !  ! //J"3 SEA /ES A  ! i /

  $ 23 r       e
                                                   . N'T3#         .

o J///0"[gfgeggy 7,, , Location / Elevation  ! g gg fjv /4. ! 2 o w siof PL v/14 to -

                                                   !               ! To 67/ sos Ph BRic.           .

Equipment ID No. ' 3fg [ /e' { ,, e QUALIFICATION REPORT  !  !  ; (8.0/5.0/5.0)  !  ! l Report ID Number j 373 j RMT 37B3 .

                                                                                                         )7 f f/]

Report Date . .

                                                   !       N/A     !    ??lcutek 23, I 778         i Issued by                                        !               !

• 1f05ll051 gg '

Prepared for  ! ifosfM0"pf!! gy l Referenced Reports  ! -

                                                   !     WA        1 RMT       2122l           l[W23]

Qualification Method  ! -  ! . (5.1, 5. 3/2.1, 2. 4/2.1, 2. 4) ! 780I  !  !

                                                   !               ! 7yfE TES7~                   !

QUALIFICATION TEST PROGRAM  !  ! I Functional Test Description !  !  ! (5.2.5/2.2.9/2.2.9)  ! 8[A  ! yp T fo b.7 6 8 0 0  !

                                                   !               ! gao p/wuxi2 to               !

Operating Conditions  !  !  ! (-/ 2. 2.10/ 2. 2.10 )  ! )l/M  ! o  ! Ioad/ Cycles / Voltage /  !  ! c -- O89 Current /Freq.  !  !  ! V- 20 /7% -  ! l

NRC Contract N3. NRC 03 79-118

     @DDE,:nkiin U

a: s,ca cente, FRC proi.ct No. Csasy Page A DMs on of The Frinkhn Institute FRC Assignment No.13 5b 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10M FRC Task No. E// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 22 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Acc ptance Criteria  ! f

                                                                                      *+SYo$0.SAfrAg1yo
                                                                                      !-                                MM}1 g/'j       ! f- #% c'"#/#6 JT I#J 7~ '

(5.2.5/2.2.1/2.2.1)  ! T Accuracy (5.2.5/-/-) y .

                                                                                                 #f
                                                                                                  ,         ,7           puh p,yE A Number of Specimens                                              '               '  sann u biw*           .a +g, . rs g 1 y                         ]               37EM

( Txt Instruments Calibrated p/f .; YES /N 6J j Srfoty Function (Active /  !  ! Psccive) (-/2.1. 3/2.1. 3)  ! N CI/I#N ! j(/h { Tect Duration (5.2.1/-/-) g/g p,yfy i Accident Duration (Envir.  ! 2YNk .'! g/4 Above Normal) (5.2.1/-/-)  !  ! Required Function Time  ! py /;g *

                                                                                                                                ,?

Tact Sequence (General)  !  !  ! (5. 2. 3/2. 3.1/ 2. 3.1)  ! )l/p  !

                                                                                      ! g/f 0//J[/oA/[8//JM/C !                 !
                                                                                         $ffdff-PRf55UAf/SfM7 :

• Tect Sequence (NUREG-0588, -* ~

Cat. I) (-/2. 3.1/-)  ! ///  ! /1/ *

1. Representative Sample  !  ! l

2. Baseline Data  !  ! l

3. Performance Extremes  !  ! *

4. Thermal Aging  !  !  ;

l 5. Radiation Aging  !  ! g// ! l l

6. Wear Aging  !  !  ;

l 7. Vibration / Seismic  !  ! * ! 8. DBE Exposure  !  !

• i 9. Post-DBE Exposure  !  ! I

10. Inspection  !  !  !

                                                                      !               !                                        I Aging                                                            !               !                                       !

I (5.2.4, 7.0/4.0/4.0) Th0rmal Aging / Basis

                                                                      ! A/ON6-p o A/6 y

Matorial Aging Evaluation (7.0/-/-)  ! N086 fg Matorials Susceptible  !  ! ' (Thsemal) ( 5'. 2. 4, 7. 0/-/-) g Radiation Aging, Type  !  ! go  ! cA Ntle Co .

 '-w   -     - - - - -       -- - - - - - - - - - - - - - . - - - - -

Alj00hnnkhnR:se rchCantir NRC Contract N2. NRC-03 79-118 FRC Project NO. C5257 Page A DM9on of The Frankhn Institute FRC Assignment No.13 5c 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /2 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Radiation Aging, Dose (rd) ' p/j ggj gg fg g7 payg ' .

                                                  '                                                I Radiation Aging, Dose Rate                               jy       !
                                                  .               !   Sff JCC/dfNT 005f I!

Radiation Aging, Method  !  !

                                                  !               !          TEST'                !

Materials Susceptible  !  ! (Radiation) (5.2.4, 7.0/-/-) { g ,7 grg7ED!{ go { Operational Aging  ! pM  !  ! (-/4.2/-) ' Other Age Conditioning M! k (-/4.2/-)  !  !  !

                                                                  !          p/g -               1 Qualified Life Claimed /                                NONb                                     !

Established (5.2.4/4.10/-)  ! . gay g,737pf' y Normal Ambient Temperature  !  !  ! Normal Ambient Radiation

                                                   !AM.p $ 1!               g                   ;

Normal Ambient Humidity  ! On-Going Surveillance and  !  !  ! Preventive Maintenance  !  ! (7.0/-/-)  ! ' por STif 7/b *g

                                                    .              .                            e On-Going Analysis of                               !               !                           .

Failures and Degradation  !  ! . (7.0/-/-)  !  ! pot STAKO - 1 1 Margin (General)  !  ! (6.0/3.0/3.0)  ! N((  ! Margin (NUREG-0588,  ! *

                                                                   !   l0/o oN RAD /A Ila/) $; 9Y Cat. I) (-/3. 2/-)                                  !              !

1. Temperature (+15'F)  !  ! jy/g

2. Pressure (+10%,  !  !  ;

10 psig max)  !  !

3. Radiation  !  !

(not required)  !  !

4. Time (+10%, +1 hour  !  !

     + function time minimum)                       !              !

4000d Fr:nklin R:serrch Ccnter NRC Contract No NRC-03-79-118 FRC Project N2. C5257 Page A Dim of The Franklin Institute FRC Assignment No.13 5d 20th and Race Streets. Ph61a.. Pa.19103 (215) 4481000 FRC Task No. d~// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./l I NRC REQUIREMENTS DEFICIENCY l WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS 1 1  ! IDCA/MSLB/HELB/ Uncontrolled ! (4.1, 4.2, 4.3.1,'4.3.3/  ! [ o C// pp 1 1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) !  !  ! Radiation Type  ! g ' gg so ' Radiation Dose (rd) g gb gg3 (4.1.2/1.4/1.4)  ! 7Id/0  ! N  ! Radiation Dose Rate (rd/hr')  !  ! O .8 X MS g  ! Radiation Qual. Method  ! #0 T S TAI #0! A g (5.3.1/-/-)  ;

                                                                     ,        7gg7 Proximity to Concentrated                        !                 !                           !

Radiation  ! NO  ! g//[  ! ( 4.1. 2/1. 4. 6/1. 4. 6)  !  !  ! Equipment Susceptible to  !  ! e Beta Radiation (4.1.2/-/-)  ! NO .N/g { Radiation Dose (Normal + 1 g!  ! Accident) (4.1.2/-/-) '

                                                       /, o )( 10    '

l . .

                                                                                  / /0 8AO      f.

l Picteout Dose Considered  !  !  ! (-/1. 48/1. 4 8) ' pp ' Gamma + Beta Dose (rd)  ! ph  !

                                                                                  /V[j[

(4.1.2/1.4.7/1.4.7)  !  !  !

4 A NRC Contract NO. NRC-03 79-118 1 00bhrinklin R:se:rch Ccnter FRC Project N2.C5257 Pag 3 ! A Division ol The Frinkhn instituti FRC A:signment N2.13 5e 20th and Race Streets. Phila.. Pa. 19103 (215) 448-10m FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /1 1 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE , LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.)

                                                     !                !                                    s ENVIRONMENTAL PROFILE                               !                 !

l OF ACCIDENT CONDITIONS  !  !  ; l > Rate of Temp./ Press.  !  ! /, f 7f /o.f 7 /*J' { Increase

                                                     !                !                                   ep
                                                                      !    3C*lino//o e/ o - to/1 ! .2 cyeL ES Peaks      'F/psig/RH/ Time                                                                              .ggg 1.769.f// foo[J#

Decrease To:

                       'F/psig/RH/ Time ')/?/2 a[/oo[fff !

3es/ a b c/ r k !Iwra m psofir//so/cc Ag i

                                                    -                 2 Decrease Tot *F/psig/RH/ Time                                 j, jg '                                   .-

R o o ft TEM P.  ! Decrease To: 'F/psig/RH/ Time !  ! . Equipment Surface Tempera-  !  ! N oNf ture (MSLB) (-/1.2.5.C, 2.2.6/1.2.5.C, 2.2.6)

                                                         ///[        !

l* e e Spray Qualification Method TfSI f (5.3.2/1.3, 2.2.8/1.3,  ! Ib/  !

• 2.2.8)  !  !
• e e Spray Composition hg ygas fangh Mg 807 /f0 00 W f-n M :n i e s yi "/; 6 r" 'or j

                                                                                             /[L Spray Density (gpm/f t 2)                                      y               o ,ff                  .

Spray Duration gg } O - p. y }loup g 3 Submergence Durati'on  !  ! gogg ( 4.1. 3/2. 2. 5/2. 2. 5)  !  ! f I In-Leakage Considered  ! e  !  ! l ( 5. 2. 6, 5. 3. 2/-/-)  ! N/M  ! No / EA K4(rf 1

                                                   !                 !     O G TEcTE b               !

Tir.e to Submerg,ence  ! y/))  ! 8/4  ! l Dust Environment  !  ! 4  ! l (-/2. 2.11/2. 2.11)  !  !  ! l l l l l

A NRC Contract No. NRC-03-79-118 000pU Fcnk!!n R: search C:nter FRC Project No,C5257 Page A Dwon of The Franklin Institute 20th and Race Streets. Phda.. Pa. 19103 (21W 4481000 FRC Asalgnment No.13 FRC Task No. f// 5p EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./.2.

                 /.        Th W These test units are representative of the whole 1153 Series A model line. The remainder of the model line differ by the spring constant (thickness)ofthesensingdiaphragmandbytheprocesspressure level. The stiffness of the metal sensing diaphragm, whose movement is minute             .004 inches, does not constitute a significant design difference. Radiation, vibration, and steam temperatures would not effect diaphragm stiffness to the extent that performance would exceed the specified acceptance criteria limits.                          Also, all transmitters within the model line have a design capability of withstanding a
        , process pressure proof load of 10,000 psi. This is more than twice the maximum operating pressure range of. any transmitter. Hence, process pressure is a static load which is well below the design proof load and the effects of this static loading would not be                             ,.
                                                                                                         ~

l significantly enhanced by exposure to the qualification testing. l Thus, the entire 1153 Series A model line is qualified to the acceptance levels specified in this document by virtue of similarity to the test units. Span Maximum Working . j , Model No. Type Min. Max. or Maximum Static ll53DA3 Differential 0-5" H 2O 0-30" H 2O 2000 psig ll53DA4 " 0-25" H2O 0-150" H 2O " 11530A5 0-125"H2 O 0-750"H20 " 1153DA6 0-17 psid 0-100 psid "

           .ll53DA7                       "

0-50 psid 0-300 psid " 1153DA8 0-170 psid 0-1000 psid " o

NRC Contract No NRC-03 79-118 00 Fr:nklinResearchCcnter FRC Project No,C5257 Page A Divism of The Franklin Insedute FRC Assignment No.13 5 20th and Race Streets. Phila.. Pa 19103 (215) 448-1000 FRC Task No. d~// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /2. ll53HA4 Differential 0-25" H2O 0-150" H 2O 4500 psig Il53HA5 0-125" H 2O 0-750" H 2O 1153HA6 0-17 psid 0-100 psid " 1153HA7 0-50 psid 0-300 psid "

~

0 W " HgA 0-55" HgA 1153 5 Absolute 2000 psig ll53AA6 " 0-17 psia 0-100 psia . ll53AA7 " 0-50 psia 0-300 psia " 1153AA8 " 0-170 psia'0-1000 psia "

  ,1153AA9   ,

0-500 psia 0-3000 psia 4500 psig ll536A3 Gauge ' 0-5" H 2O 0-30" H 2O 2000 psig ll53GA4 0-25" H2O 0-150" H 2O " 1153GA5 0-125" H2O 0-750" H20 , ll53GA6 " 0-17 psiG 0-100 psiG " 1153GA7 0-50 psiG 0-300 psiG " 1 53GA8 0-170 psiG'0-1000 psiG A9 0-500 psiG 0-3000 psiG . 4500 psig gna # _ Summary of Radiation Results . During the exposure period, the following worst case output signal deviations were noted: .6%, h%, and +1.5% of span for serial numbers 106186,106187, and 106188; respectively. These resul,ts are well within the expected error band of 5% upper range limit. The post-test calibration check indicates that all transmitters returned to near normal performance; all transmitters were within 0.5% of the pre-test data. No changes worthy of noting were seen in liftoff voltage or time constant parameters in the before to after compari-son. The temperature coefficient data do indicate that radiation does have an effect on this parameter; howeve*, the magnitude of

                                                                              ~                       '

this effect is small. The largest difference between the pre-to-post test data at the hot temperature (200 F) was only 1.3% of span.

NRC Contract No. NRC-03 79118

  @DDEr.nklin Research Center U                                                             FRC Project No, C5257               Page A DMeion of The Frankhn Insntute                          FRC Assignment No.13                 Sh 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1 2 0   FRC Task No.      87/

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. Jd. wrzs: . pA;.3- Zh- @ M ' The deviation from procedure esulted from a problem with the filtra-tion system for the chemical spray. The plurbing for the spray became clogged such that units 106186, 106187, ar.d 106188 were sprayed for 10, 21, and 24 hours; respectively. The procedure originally specified 24' hours of chemical spray. This deviation does not impact the results_ , of the test for three reasons. First, the transiaitter design is one in wh.ich all exposed surfaces are of ferrous material and are chemically compactable with the spray. Second, the strip chart data for signal. . outout and past development testing indicate that the output signal is uneffected by the spray introduced into the chamber. Third, unit 106188 did experience the required amount of spray and, therefore, l demonstrates the design compactability with the 24 hours of spray. It is concluded from the results present that all three units met the requirements of the steam / chemical test. 7/r b f - N [ I' CONCLUSIONS It is concluded from the data obtained from this type-test program, a summary of which is document in this report, that all three test ! units have successfully demonstrated the Rosemount Model 1153 Series A pressure. transmitter to be qualit'ied for C1' ass 1E service in those applications requiring compliance with the 1971 IEEE standards. l

s 4UOOU Ftnk!!n R:sersch Cent:r NRC Contract Ns. NRC-03-79-118 Page-FRC Project ND. C5257 .} p , A Divmon of The Frankhn Instituts FRC Assignment N2.13 ' - -

• 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. _ M/ ' 5s#

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENTiiEM NO. /2 ,.

                                                                                                 ~,                                -

1 ,_

                                                                                                      -. , , ,                                              ?.

y , - EQUIPMENT ENVIROleElNTAL QUALIFICATION REVIEW .. Criteria: DOR Guidelines  ; NUREG-0588, Cat. Id;NUREG-0588, Cat. II' .' NHC REQUIREMENTS DEifCIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION '(I Oh' (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.)_ EQUIPMENT DESCRIPTION  !  ! h AU$d I88 N 45 '*! Equipment Type !7gggfM/TTTl' 784NJM/TTfR i Manufacturer's Name

                                                     ! kCJfgouvrj ROSE //00Ni -                                          !

(5.2.2/-/-)  ! . g

                                                     !                !    //(3 GA 7                  -

Model Number ( 5. 2. 2/-/-)  ! //88A l- g

                                                                                                                                                    }f' 1  Serial Number                                           MM                                    '

( Features / Mounting  ! gg7 g737fD ! gof g7jf7'[D * { gM / (5.2.6/-/-)  !  ! .s u Connectiona/ Interfaces  ! NoT STAT!D! NOT S74ffD , (5.2.6/-/-)  !  ! . Location / Elevation gff 8 /t f Equipment ID No. . S/E ff /* . NM ,f ~ 1 QUALIFICATION REPORT  !  ! N l (**0l5*0l5*0) I  ! Report ID Number ' [/p / ' RMT NO. 3 7f2] REf8;[yy2 } , Report Date . . a 4' /fvG -78 '!

                                                                                                                                                                ~

Issued by . gcSfMoupT. A osE/fo uN'[~ - { Prepared for goff/foukl R os EM ovpT

                                                    !                !                                                *4 Referenced Re,,..rta                              !

p/jf  ! g M 7' N O . J 7 8 8 ((.j7fy} Qualification Method  !  !  ! (5.1, 5.3/2.1, 2. 4/2.1, 2. 4) ! g  ! p , s  !  !  ! QUALIFICATION TEST PROGRAM  !  ! I Functional Test Description ! g !ypir 8 0ts # # 5 0 AND g (5.2.5/2.2.9/2.2.9) '

                                                                     ' /KFSSu A / 2 60                              .'

Operating Conditions k h !MM7 (-/2.2.10/2.2.10)  ! /  ! O - 3000 M7  : Ioad/ Cycles / Voltage /  !  !  ! l Current /Freq.  !  ! 8 8IA  !

             - - ,                                 --               - - ,                   --                     ..mr-,       -.               .      w -, -

s NRC Cantr ct No. NRC-03-79-118

                         '00'%J Franklin Research Center                                     FRC Project No. C5257                        P gs FRC Assignment No.13 A Divisor. of The janun Inmute                    -
                                                                                   -s 20th and itace Stre ts. Phda.. Pa. {0103 (215) 448-1000     FRC Task No.           8 //                  5b'
                  =
                                       ~

EQUIPMENT E!O/lRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /2. NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) IS$$)/2$2I2I2f N/A YY

                    ' Accuracy (5.2.5/-/-)                                             gh       !   _.3 25%            d JMNbbggj
                                                                                                                   / gjpgg             I MM NNber of Specimens                                                                                      '

g ' ON6 . Test Instruments Calibrated g  ! Safety Function (Active / .! g7jpg  !  ! g/g Passive) (-/2.1. 3/2.1. 3) ' 1 [ Test Duration (5.2.1/-/-) 8/A

                                                                               !                !        N$           S O NIN. !

Accident Durat.icn (Envir.  ! ,  !  ! i- Aoove Ncrmal) (5.2.1/-/-) '

• E ' '

jj/p

     .-                Required Function Time                                  ! J y /)g        .
       ~

Test Sequence (Gener al)  !  ! 1 M li (5. 2. 3/2. 3.1/ 2. 3.1) } i s TE4M/C4EM/d/- l i *

• sfRoy Test Sequence (NUREG-0588,  ! p  !  ! [

Cat. I) (-/ 2. 3.1/-)  ! '

l. Eepresentative Sunple  !  !  !

2. Baseline Cata  !  !  !

4 7 3. Performance Extremes  !  !  ! [ 4. Thermal Aging  !  !  ! 11 5. Radiation Agi:tg  !  !  ! in 6. Wear Aging  !  !  !

7. Vibration / Seismic  !  !  !

ru 8. DBE Exposure  !  !  ! m 9. Post-DBE Exposure  !  !  !

10. Inspection  !  !  !

         ;            -Aging                                                     !                !                              !

(5.2.4, 7.0/4.0/4.0)  !  !  ! Thermal Aging / Basis  ! gDN /\/ONE X Material Aging  !  !  ! Evaluation (7.0/-/-)  ! NOFE  ! jgfoys  ! X

   ...~

1  !  ! Materials Susceptible  !  !  ! (Thermal) (5.2.4, 7.0/-/-)  !  ! NOT 8I/f7Bb e Radiation Aging, Type N gl/ jf e,

A NRC Contract Nr. NRC-03-79-118 000b:nklinR:se rchCenter FRC Project Nr.C5257 Pag 3 A Dwon of The Fr:ntlin Instruta FRC Assignment Nr.13 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. (// Se' EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. / A NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIRONMENTAL PROFILE  !  !  ! OF ACCIDENT CONDITIONS  !  !  ! Rate of Temp./ Press.  !  !  ! h h j.( */S fC G 7l# ?l5 A" "'A*5 Peak: 'F/psig/RH/ Time gj,, 350l)pol/c olo -/oM - Decrease To: 'F/psig/RH/ Time 'gj o/j h/l!! I ff Decrease To: *F/psig/RH/ Time If;/S*//u/// ! 3 o 3lcC//a./ Q 4 A 2

                                                                                                   !   Q
                                                    !                 ! pro /is//co/ /.c4x !

Decrease To: 'F/psig/RH/ Time '

                                                                      ' /Too M TE//PE/A7u/r4j Equipment Surface Tempera-                         1                 !                            !

ture (MSLB) (-/1. 2. 5. C ,  ! gh  ! /YOI 8IWO  ! 2.2.6/1.2.5.C, 2.2.6)  !  !  ! Spray Qualification Method  !  ! e (5.3.2/1.3, 2.2.8/1.3,  ! 7bI  ! 78J 7 { 2.2.8)  !  ! g Spray Composition  ! g 1 808/C AC/D /(coa prg 1 (4.1.4/1.3, 2.2.8/

1. 3, 2. 2. 8) i jy y .j,, ! e e

i j Nad# o@7'/.* I O ./6~ GPM /FT - Spray Density (gpm/f t 2) g f.3 ps 3 w//) Spray Duration p/g h 88I 87dI O { Submergence Durati~on  !  ! y n (4.1.3/2.2.5/2.2.5)  !  ! g In-Leakage Considered (5.2.6, 5.3.2/-/-) g  ! fff  ! M g (, Time to Submergence k. gM k k Dust Environment p //[/f (-/2. 2.11/2. 2.11)  !  !  ! l

i A NRC Contract N3. NRC 03 79-118 Pag 3

                                                                                                               )

000hrinklin R:serrch Cent:r FRC Project No. C5257 A owis.on of Th. Frankhn Institute FRC Assignment No.13 5f, 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. T// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1&. , l Norss:

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NRC Contract N2. NRC-03-79-118 phnnklin UO0 R: search Center FRC Project No.C5257 P g3 A D6vmon of The Frankhn Insntut2 FRC Assignment N;.13 5 20th and Race Streets. Phda.. Pa. 19103 (215) 448 Imo FRC Task No. f// 7# EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _ZA NOTES:

r. A q J 21 A v} M-II - . - - .

TEST RESULTS Accuracy deviations at the input pressures of 50 and 20% full

              ' scale-(F.S.) are plotted versus time in Figures 2 and 3. These data indicate the maximum output signal deviation occurs during the 10 minute hold peried at 350*F. The worst errors from the 50% and 20% full scale pressure tests during this period were
               -3.25 and -2.60 percent of span, respectively. At the 303'F temperature, the accuracy deviations were less than +1.5 and
               -0.8% of span for the 50% and 20% F.S. tests. At the 250 F temperature, the deviations were less than +1.8 and -0.6% of span. y G
              % %, rx qM :                                                                  ~
         //

Two anomalies developed during the testing. The first was a minor leak developed at the threads between the process fluid bleed valve body and the process flange. This joint is sealed using a Loctite thread sealant. The leak was minimial, only a few drops of fluid per minute. The' bleed valve assembly was l removed and re-installed using a tape thread sealant in order to , expeditiously finish the performance testing. Subsequent to the steam testing, an evaluation was made to reaffirm the design adequacy of the Loctite thread sealant at 350*F and 30'00 psig l

l NRC Contract No. NRC-03-79-118 phcnklin UO0 - R search Conter FRC Project No.C5257 Page A DMsen of The FrankhnInstitute FRC Assignment No.13 5},, 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./2 l NOTES: fluid pressure. A set of four flanges were assembled with bleed valves by the Production Department per procedures for the Model 1153. These were then heated in an oven to 350'F for four hours. They w' e re removed from the oven and immediately pressurized to 3000 psig for a period of 20 minutes. During the twenty minutes, they were visually checked for leakage; none was detected. It was concluded that Loctite is an adeouate thread sealant for these conditions. /' 7. T.n2 f Y$ aA K ' M ch.s. . 4; T'he second anomaly involved the output signal at the 100% full scale pressure, i.e. 3000 psig. After the first test had been completed and the unit had cooled to room temperature, a calibra-tion check was made at 20% F.S. intervals. The 100% F.S. signal exhibited anomalous behavior characterized by an erratic output to a level 1.25% of span below the expected reading. Immediate cycling between zero and full scale, 3 cycles, indicated the 100% F.S. output signal to be a normal steady value each time. The transmitter was then reworked for the 'second phase of testing; new electronics and new 0-rings were installed. A calibration check prior to subjecting the transmitter to the second steam test showed normal operation. Also, during the

           - steam test the unit exhibited expected performance characteristics.

However, after cooling at room temoerature, the 100% F.S. reading again showed abnormal behavior after pressure cycling.

                                                                                                                      \

_ _ _ _ _0

NRC Contract No. NRC-03-79-118 4000U Fr:nklin Research Ccnter FRC Project No.C5257 Page A DMsen of The Frankhn Insnture FRC Assignment N;.13 Si' 20th and Race Streets. Phita.. Pa. 19103 (215) 448 1 2 0 FRC Task No. W/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _f.:2, NOTES:

                                                    ~~~

ADDENDUM 1 INVESTIGATION INTO THE CAUSE OF THE PERFORMANCE ABNORMALITIES Due to the abnormalities of the 100% output after the original steam test, an attempt was made to determine if the abnormalities were caused by the'trans-mitter or by some other part of the test. ~ - ~~~ In an effort to determine what part of the transmitter wasn't working properly, the capacitance module was disconnected fromthe transmitter and its. capacitance checked. While at room temperature, it was cycled at 80% F.S. pressure,100% F.S. pressure,110% F.S. pressure and 120% F.S. pressure; the cell acted erratically, changing its capacitance readings by up to , 7.5% of the nominal readings. At the same time, a new capacitance module was subjected to the same test. and performed perfectly. Thus , the abnormality can be traced to some problem with the original capacitance module used in the steam test. -. . ~ . - . . After the electronics were replaced, the unit gave very smooth readings. The largest error seen was -3.13% of F.S. during the 350 temperature spike. The errors were

                                .95% of span during the 303*F phase of the test and .44%

of span during the 250*F portion. CONCLUSION The abnormalities that appeared in the original steam test were apparently , caused by a defective capacitance module. An investigation was made to try to pinpoint the exact cause of the problem, but no conclusive results were ever obtained. However, due to the good performance of the new capacitance module when subjected to a steam test, it can be concluded that the problems with the original cell were of a random nature and that the transmitter will operate within the !8% of upper range limit specification. //

NRC Contract N 3. NRC-03 79-118 pkranklin UO0 R:sench Cent:r FRC Project N3.C5257 P:g3 A Division of The Frankhn Institute FRC Assignment No.13 5 a.a 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTask No. (// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1.2, wrzs: O d C M O n & d Nor Jiny A ad L t: X,. 2 L i a - ~ ' m 's v

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                -iThree differential range ll53DAS transmitters were sequentially tested. These units are representative of the entire 1153 Series A mod'el line. The remainder of the model line differs by the sensing diaphragm, spring thickness, and the process pressure rating. These differences are not significant with respect to qualification testing. Thus, the following model line'is qualified by virtue of similarity:                                                          ,

ll53DA3 through 8 ll53HA4 through 7 1153AA5 through 9 l ll54GA3 through 9

                *The transmitters were exposed to a radiation exposure rate of 0.5 Mrd j                    per hour for a total integrated dose of 44 Mrd. The ma'ximum output l                     signal deviation noted was +3.7% of span.

I .

                 - The three transmitters were LCCA tested in a steam temperature /

4 pressure / chemical-spray environment for fy hours. The maximum error, exhibited was +6.95% of span. O AW W d '3 h Y //f3 CA 9

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A NRC Contract N2. NRC-03-79-118 P g3 000Ersnklin RrseIrch Cent:r FRC Pro}ect No.C5257 A Dwisson of Thi Frtnkhn Inshtut2 FRC Assignm:nt N2.13 20th and Race Streets. Phila.. Pa. 19103 (215) 448-Imo FRC Task No. f// 544 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. l3 wrzs: o $ h MA N / PJo . 0-e- d. A M&4 AtuRE C 0 CEf Cd 7(I) x! 2 2 2 J A A-o M - i i

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kosecounttesting"toqualifyatransmittertomeet.IEEE323- - 1974 require =ents has resulted in failure. A combination.of thermal aging, irradiation and chemical spray test speci- - fication parameters has resulted in failed cc=ponents. The initial failed ele =ent was an 0-ring cc= prised of'sulphu. cured polyethylene rubber. This allowed steam / chemical spray

                                                                                                     -~

to affect electronic cceponents. The 0-ring =cde of failure is attributed to high temperature.vs. time necessary for the Arrhenius curve t'=e cc=pression to satisfy aging test re-quirements. l l {

4600U FrInklin Rese:1ch C;nter NRC Contract No. NRC-03 79-118 FRC Project No.C5257 Pag] A DMsen of The Frankhn Institute FRC Assignment No.13 5e g 20th and Race Streets. Phila . Pa. 19103 (215) 448-1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. /2-i NOTES: This testing failure does not preclude the use of the Rese- l mount 1153A within H. B. Robinson containment as it has successfully performed within the H, 3. Robinson accident parameters of temperature, pressure and radiation levels. Transmitters located in containment will be required to perform within a maximum time period of twenty-four (24) hours following accident. 0-ring failure due to high temperature should not occur during this time period. Reviewing Table C-1 of Appendix C, NRC IE Bulletin 79-013, Thermal and Radiation Aging Degradation o_f Selected Materials, shows that poly-ethylene rubber has a potential for significant aging at t9n (10) years and an allowable radiation susceptibility of 10 RADS before serious degradation occurs. Evaluating the above establishes the need to perform periodic changeout of trans-mitter 0-rings. Electronic transmitters qualified to IEEE-323-1974 are not currently

  'available. CP&L is a participating member of the Wisconsin Electric' Transmitter nuclear plant Evaluation use. Presently,      Program to test and qualify electronic transmitters for CP&L has upgraded its . master list transmitters within containment to Rosemount 1133A models which are qualified to IEEE-323-1972.

into the fourth quarter After the of current 1982 test progra= is complete - which extends-

                                                              'CP&L will evaluate the rtsults, and decide.on-action (s). to be taken to provide fully qualified equipments. In the . interim, CP&L has established a program which requires changeout of 0-rings when yearly -

calibration checks are performed and a complete instrument changeout on ten-year cycles after installation dates, to maintain qualification level. ,, l l l l l -

A NRC Contract N;. NRC-03-79-118 00flfFranklin Rzse:rch Center FRC Project N;. C5257 P g] A Division of The Frsnkhn Instituts FRC AssignmInt No.13 5Jg 20th and Race Streets. Phita.. Pa. 19103 (215) 448-10m F'RC Task No. (// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. / L NOTES: h & . A M a su & bA chfl 1s L 1A kf.."A J h s ~ n a wi/22L d & D W (EEEE -Ll3 / y& lJ;/) . TA ',2'J n L M ZAf

       ! N N.B. L L A d 4 -

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A w 'A~ H.B. R K & . rk EA ~ AcLdA h M L dx x & % . u i V2 1 .  !% w"AmM a z a m x an a$A~- M M . A nk 1n'a=us'h.M aI ' M Ed A LM & usn A, am w AA wr sakaw su bMA M . -

A NRC Contract N 2. NRC-03-79-118 000hranklin RIseirch Cs.nter FRC Project N2. C5257 P g3 A Division of The Frtnklin Institut2 FRC AT;Ignment No.13 7q 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. # // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /1 MAINTENANCE AND REPLACDENT SCHEDULE SIMMARY The following information regarding the maintenance and replacement sch:dule(s) for components, sub-components, and materials has been provided by the Licensee. Is Additional action required - A program of periodic transmitter housing 0-ring replacement (performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2.) To assure ___. . . ~ operational capability, a ten- (10) year transmitter replacement schedule has been adopted, to be modified when Rosemount can certify, by test, longer life equipment is available. { f //

  &                                                           NRC C;ntract N 2. NRC-03-79-118 Pcg2 LOOU Franklin Reserrch Centa                                FRC Pr:Jax:t N3.C5257 A Dmsion of The Franklin Institute                      FRC Assignm:nt Ns.13                               lc 20th and Race Streets. Phila.. Pa 19103 (215) 448 1000  FRC Task No. 6/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. O EQUIPMENT ITEM NO.13 LEVEL TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT MODEL 1153A REQUIRED OPERATING TIME: 30 MIN TER CHECKSHEET NO.13 LICENSEE REFe.RENCE(S): 1764, 4423 FUNCTION (PLANI ID):                 NOT STATED (LT-475, -476, -485, -486, -495, -496, -497)

FUNCTION (PLANT ID): MONITORS STEAM GENERATOR A NARROW RANGE LEVEL (LT-474) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR A WIDE RANGE LEVEL (LT-477) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR B NARROW RANGE LEVEL (LT-484) FUNCTION (PLANI ID): MONITORS STEAM GENERATOR B WIDE RANGE LEVEL (LT-487) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR C NARROW RANGE LEVEL (LT-494) FUNCTION (PLANI ID): MONITORS STEAM GENERATOR C WIDE RANGE LEVEL (LT-491) FUNCTION (PLANT ID): MONITORS PRESSURIZER LEVEL AND ACTUATES SIS (LT-459,

                                        -460, -461)

LICENSEE SUBMITTAL: SCEW(S): 19 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) R, T, RT, P, H, (R), M, I, QM RPN, EXN, SEN, QI, RPS None, l Not stated, Not applicable l LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 l Licensee Response to NRC SER 3a, 3b, 3c, 3d System Consideration Review h, ti, tc, 02, L , b^~ ( l Equipment Environmental Qualification Review '"?. "", 52, 50, b , 36

                                                                                 -33 , Ch, Si, Si Installed TMI Lessons Learned Implementation                                    L, Cb i

Equipment Summary

Maintenance and Replacement Schedule Summary 7a, 7b, 7e I

f

NRC Contract N3. NRC-03-79-118 00 Frinklin R: search Canter FRC Project N . C5257 Pag 3 l A DMen of The Frankhn institute FRC Assignment No.13 lb 20th and Race Streets. Phde.. Pa. 19103 (215) 448.I000 FRC Task No. ElI EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .L3

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: I Tne Licensee (has,^-- --t! provided a response to the SER concerns. g The Licensee (has, :: ;;t! specifically stated that the equipment is qualified and$r will function when exposed to the applicable DBE ' environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. [ The Licensee (has/.. _ rrt) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment-ites. 1 Corrective action specified by the L consee: Y u .M We - a w Equipment replacemenI with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress _f_ Other ( b 0 - d a-2 dl~ M . e=_k% ) J The LicenseeEhas & provided le &MN=l_+ & {9. other infordafion = equipmen( for this .- E & te that can be construed as a basis for justification for interim operation. f The Licensee (has/h:2 -^t) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action #, M _ .) 0 0 The Licensee states that the equipment item does not require qualification cnd/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

   - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope Not Qualified IV Documentation Not Available

I NRC Contract N 3. NRC-03-79-118 Page AUCCErrnuiin at .rch c:nter FRC Froi.ct No. Osasy l 4 A Dhnsen of The Franidin Instituu FRC Assignment N ?.13 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. C/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2::3 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) Y Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied X Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied X Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied M Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) X DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established f II.b Equipment Not Qualified X

II.c Equipment Satisfies All Requirements Except Qualified Life l

or Replacement Schedule Justified i III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available ht. Z P _a_A.L . 7% /& k ia - -

                                                                                          , W D.

1 I

A NRC Contract Nr. NRC-03-79-118 00bnklin Research Center FRC Project No. C5257 Pag 3 A DMsion of The Frankhn Institute FRC As signment No.13 3a 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Taak No. A~l/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 43 LICENSEE RESPONSE 'IO NRC SER 4.2 Ecu1pment Recuirine Additional Information and/or Corrective Action (Accendix 3) { The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following: Deletion of deficient listed" equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical F 4uipment IE3 79-013. Technical Evaluation Report

                   - Docket No. 50-261; Plant: R.                     3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment deleted due to replacement programs completed at the ' plant . (Deficiency listings will not be addressed as these equipments are no longer in place or use at the plant). Ecutement Descriotion u.anufacturer Model No. Location l 1. level transmitter Fisher & Porter 10B2496 Containment

2. pressure transmitter Fisher & Porter 50EP10413 CIA-NS Containment

3. flow transmitter Rosemount 1151 '

Containment

4. level transmitter Fisher & Porter 13D2495 Containment

5. solenoid valve ASCO L38211C32 Containment

6. solenoid valve ASCO L38316325 Containment l 7. solenoid valve ASCO L38316B15 Containment

8. solenoid valve ASCO L38316B14 Containnent

9. level transmitter ?isher & Porter 1332496 Containment The Rose =ount ll53A Transmitters are currently qualified to IEEE 323-1971. As reported in our 90-day responses these transmitters require a changeout cycle of ten (10) years with an 0-Ring replacement after each calibration check to maintain their qualification level. CP&L is part of a utilities group which is underwriting transmitter qualification to IEEE-323-1974 standards. As these tests are ongoing, no recommendations or changeout program is being formulated at this time. Upon test completion, CPSL will determine any added transmitter changeout or modification program and report to the NRC its actions.

1

N NRC Contract No, NRC-03-79-118 FRC Project No,C5257 Page 00d Fr:nklin Research Center A DWon of The Franklin Institute FRC Assignment No.13 3b 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. SII EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1.3. 3.2.2 Electronic Transmitters {/ H. 3. Robinson's original design and specification called for installation and use of Fisher and Porter electronic trans-

              - mitter for the ceasurement of Pressure, Level and Flow para-meters.          As stated within CP&L response to NRC IE Bulletin 79-01 and the 45-day response to NRC IE Bulletin 79-01B CP&L preference, to obtain better operation and maintenance per-formance, is to change out the existing transmitters within containment--to be replaced by Rosemounts' Model No.1153A.

Environmental tests performed on Fisher & Porter's trans-mitters (Model No. 1032496) indicate failure occurs during the high temperature, steam / chemical spray testing stage while attempting to qualify to IEEE 323-1971 parameters. (Reference WCAP 9157 Environ = ental Oualification of Safety-Related Class

                 ,I_E, Process Instrumentation).

Qualification testing of Rosemount Model 1153, Series A, per Rosemount Report No. 3788 states that the transmitter is qualified per the requirements of IEEE 323-1971. Missing from this report is the aging parameter not required for IEEE 323-1971 but necessary for co=plete LOCA qualification. Recent Rosemount testing to qualify a transmitter to meet IEEE 323-1974 requirements has resulted in failure. A combination of thermal aging, irradiation and chemical spray test speci-fication parameters has resulted in failed components. The initial failed ele =ent was an 0-ring comprised of sulphur cured polyethylene rubber. This allowed steam / chemical spray to affect electronic co=ponents. The 0-ring mode of failure l is attributed to high te=perature vs. ti=e necessary for the Arrhenius curve time compression to satisfy aging test re-quirements.

• This testing failure does not preclude the use of the Rese-

                 =ount 1153A within H. B. Robinson contain=ent as it has successfully perfor ed within the H. B. Robinson accident parameters of tecperature, pressure and radiation levels.

Transmitters located in contain=ent will be required to j perform within a =axi=um time period of twenty-four (24) hours l following accident. 0-ring failure due to high te=perature should not occur during this time period. Reviewing Table C-1 l of Appendix C, NRC E 3ulletin 79-013, Ther=al and Radiation

Aging Degradation of Selected Materials, shows that poly-j ethylene rubber has a potential for significant aging at t9n (10) years and an allowable radiation susceptibility of 10 RADS before serious degradation occurs. Evaluating the above establishes the need to perform periodic changeout of trans-

                 =itter 0-rings.

l l

NRC Contract No. NRC-03-79-118 4000U Fr:nklin Research C:nter FRC Pro}ect No.C5257 Page A Dwon of The Frankhninstitute FRC Assignment No.13 3c 20th and Rece Streeu. PNia.. Pa. 19103 (215) 448-1000 FRC Task No. (// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. G LICENSEE RESPONSE 'IO NRC SER (Continued) Additionally, the time span to which Rosemo.unt will qualify its IEEE 373-1974 transmitters is ten (10) years. To assure that listed transmitters-within H. 3. Robinson containment remain qgified a ten- (10) year replacement cycle will be adopted Replacement of in-contain=ent transmitters identified within

                                 ~

this report has been performed within the 1980 refueling

           ' outage (August - October, 1980).                     At this time, no fully qualified transmitter is available for nuclear plant in-containment operation.                     Rosemount 1153A transmitters, qualified to IEEE 323-1971 version, were used as replacements.

Additional action required - A program of periodic transmitter , housing 0-ring replacement (' performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2. ) - To assure operationalcapability,aten-(10) yea [transmitterreplacement schedule has been adopted, to be modified when Rosemount can certify, by test, longer life equipment is available. { SECTION III - PropoIed Corrective Actions for Outstanding Items . [ . . . _ . Electronic transmitters qualified to IEEE-323-1974 -are not currently ' l *available. CP&L is a participating member of the Visconsin Electric' Transmitter Evaluation Program to test and qualify electronic transmitters for j nuclear plant use. Presently, CP&L has upgraded its _ master list transmitters i within containment to Rosemount 1153A =odels which are qualified to IEEE-323-1972. Af ter the current test program is complete - which' extends into the fourth quarter of 1982 'CP&L will evaluate the results and decide on-action (s) to be taken to provide fully qualified equipments. In the interim, j CP&L has established a program which requires changeout. of 0-rings when yearly - ! calibration checks are performed and a complete instrument . changeout on l ten-year cycles af ter installation dates, to maintain qualification 'level.

NRC Contract No. NRC-03 79-118 00 Fr:nklin R: search Ccnter FRC Project N2. C5257 Pago A Divmon of The Franklin Institute FRC Assignment Nr.13 3d 20th and Race Streets. Ph11a.. Pa.19103 (215) 448-1000 FRC Task No. . (# EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 42. LICENSEE RESPONSE 'IO NRC SER (Continued) The safety-related level transmitters (LT 459, LT 460, and LT 461) referred to in this paragraph provide pressurizer water level indication and are mounted in an instrument rack on the shield vall at elevation 230 ft within containment. These transmitters have been replaced with Rosemount Model 1153A transmitters during the August, 1980 outage at. R.3. Robinson Unit

2. Instruction was given to remount as high as possible and practical in the instrument rack. A new measurement is required for re-evaluation of submergence level for these instruments. Additional study indicates their need time within the LOCA to be the first 30 minutes.

A study will be performed to evaluate the effect of new mounting, the rate of flood to determine useful time, and the effects of new emergency procedures on these instrumentation reading requirements. At this time, the statement that their assumed failure under submergence vill not affect accident mitigation is still a valid one. This study vill be completed by the date established by the NRC for completion of qualification of safety-related electrical equipment. l l l

As NRC Contract Nr. NRC-03-79-118 000U Fr:nklin Rrse:rch Cent:r FRC Project Nt. C5257 P g3 A DMsion of The Franklin Institute FRC Assignment No.13 7g 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. d~// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. E_ MAINTENANCE AND REPLACDENT SCHEDULE SIMMARY The following information regarding the maintenance and replacement cch dule(s) for components, sub-components, and materials has been provided by the Licensee. It Additional action required - A program of periodic transmitter housing 0-ring replacement (performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2.) To assure operational capability, a ten- (10) year transmitter replacement schedule has been adopted, to be modified when Rosemount can certify, by test, longerlifeequipmentisavailable.{f // f

     %                                                      NRC Contract N2. NRC-03-79-118 P ga 4[I b!!0Franklin Rese:rch Centir                               FRC Project ND. C5257 A Division of The Frankhn Inst.rute                    FRC Assignment No.13                        lc 20th and Race Streets. Phila.. Pa 19103(215) 448-1000  FRC Task No. 6//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM N EQUIPMENT ITEM No.14 FLOW TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT MODEL 1153A REQUIRED OPERATING TIME: 1 HOUR TO 1 DAY TER CHECKSHEET NO.14 LICENSEE REFERENCE (S): 1764, 4423 FUNCTION (PLANT ID): MONITORS MAIN STEAM FLOW LOOP A (FT-474, -475) FUNCTION (PLANT ID): MONITORS MAIN STEAM FLOW LOOP B (FT-484, -485) FUNCTION (PLANT ID): MONITORS MAIN STEAM FLOW LOOP C (FT-494, -495) LICENSEE SUBMITTAL: SCEW(S): 19 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) R, T, RT, H, (R), M, I, QM RPN, EXN, SEN, QI, RPS None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 3c, 9& System Consideration Review h. Ih, II, IS, " =, C Equipment Environmental Qualification Review - { } , } , 5=, Of, y, .., --, ., . Installed TMI Lessons Learned Implementation _-

                                                                               '  95 Equipment Sutumary Maintenance and Replacement Schedule Summary                                   7a, iu, 7w

A NRC Contract No. NRC-03-79-118 000hr nkhnR:searchCcnter FRC Project N2. C5257 Pag 3 A Divisen of The Frankhn Institute FRC Assignment,No.13 lb 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m FPC Task No. 6 II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. N

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: d Tne Licensee (has/h. ..u;- provided a response to the SER concerns. 1 The Licensee (has/hre -^t) specifically stated that the equipment is qualified and7eg will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. [ The Licensee (has/'rr -') proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment-item. X Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in pr ress ~ J Other I( m k O - M M + ' ! . Ah M aL /O-Aw% M i R=hXWW The Licensee has pfovided other inf raation for this equipme it a that can be construed as a basis for justification for interim operation. J The Licensee (has/hrr ret) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action ad .) V I The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

- CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope Not Qualified IV Documentation Not Available

NRC Contract NO. NRC-03-79118 00 FrinklinR:searchCrnter FRC Project NO. CS257 Pag 9 A Division of The FrankhnInstnute FRC Assignment No.13 2 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTaskNo. EII EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIMENT ITEM NO. 4 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately M Qualified Life or Replacement Schedule Established (If Required) 1 Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied X Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied X Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) 1 DESIGNATION: I NRC QUALIFICATION CATEGORY X = CATEGORY l I.a Equipment Qualified I.b Equipment Qualification Pending Modification _ II.a Equipment Qualification Not Established II.b Equipment Not Qualified X II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified l III.a Equipment Exempt From Qualification l III.o Equipment Not in the Scope of the Qualification Review* l IV Documentation Not Made Available l M N~L

4 NRC Contract No. NRC-03-79-118 Page ll001.IFrnklin Research Ccnter FRC Project No. C5257 A Division of The Frankhn Institute FRC Assignmentyg.13 3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTask No. u Il EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. W LICENSEE RESPONSE TO NRC SER 4.2 Ecutement Recuirine Additional Information and/or Corrective Action ( Apoendix 3) Q,o] ' The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following:

          -            Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.
          -            Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report
                       - Docket No. 50-261; Plant: F.             3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment deleted due to replacement programs completed at the plant. (Deficiency listings will not be addressed as these equipments are no longer in place or use at the plant) . Ecutocent Descriotion Manufacturer Model No. Location

1. level transmitter Fisher & Porter 10B2496 Containment

2. pressure transmitter Fisher & Porter 50E?l0413 CIA-NS Containment

3. flow transmitter Rosemount 1151 Containment

4. level transmitter Fisher & Forter 13D2495 Containment

5. solenoid valve ASCO L38211C32 Containment

6. solenoid valve ASCO L38316B25 Containment

7. solenoid valve ASCO L38316B15 Contain=ent S. solenoid valve ASCO L38316B14 Containment

9. level transmitter Fisher & Porter 1332496 Containment The Rosemount ll53A Transmitters are currently qualified to IEEE 323-1971. As reported in our 90-day responses these transmitters require a changeout cycle of ten (10) years with an 0-Ring replacement after each calibration check to maintain their qualification level. C7&L is part of a utilities group which is underwriting transmitter qualification to IEEE-323-1974 standards. As these tests are ongoing, no recommendations or changeout program is heir.g formulated at this time. Upon test completion, C?$L will determine any added transmitter changeout or modification program and report to the NRC its actions.

NRC Contract N . NRC-03-79-118 00 Frnklin Research C;nter FRC Project No. C5257 Page A Divis6en of The Frankhn institute FRC Asalgnment No.13 3b 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. XH EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. lM 3.2.2 Electronic Transmitters {g H. 3. Robinson's original design and specification called for installation and use of Fisher and Porter electronic trans-mitter for the measurement of Pressure, Level and Flow para- , . =eters. As stated within CP&L lesponse to NRC IE Bulletin 79-01 and the 45-day response to NRC IE Bulletin 79-013 CP&L preference, to obtain better operation and maintenance per-formance, is to change out the existing transmitters within contain=ent--to be replaced by Rosemounts' Model No. 1153A. Environmental tests performed on Fisher & Porter's trans-mitters (Model No. 1032496) indicate failure occurs during the high temperature, steam / chemical spray testing stage while attempting to qualify to IEEE 323-1971 parameters. (Reference WCAP 9157 Environmental Oualification o_f, Safety-Related Class y Process Instrumentation). Qualification testing of Rosemount Model 1153, Series A, per Rosemount Report No. 3788 states that the transmitter is qualified per the requirements of IEEE 323-1971. Missing from this report is the aging parameter not required for IEEE 323-1971 but necessary for complete LOCA qualification. Recent Rosemount testing to qualify a transmitter to meet IEEE 323-1974 requirements has resulted in failure. A combination of thermal aging, irradiation and chemical spray test speci-fication para =eters has resulted in failed components. The initial failed element was an 0-ring comprised of sulphur cured polyethylene rubber. This allowed steam / chemical spray to affect electronic co=ponents. The 0-ring mode of failurc is attributed to high temperature vs. time necessary for the Arrhenius curve ti=e compression to satisfy aging test re-quirements. This testing failure does not preclude the use of the Rese- ' l mount 1153A within H. B. Robinson containment as it has succe tsfully perfor=ed within the H. 3. Robinson accident ' para =eters of te=perature, pressure and radiation levels. Transmitters located in containment will be required to perform within a =aximum time period of twenty-four (24) hours following accident. 0-ring failure due to high te=perature should not occur during this ti=e period. Reviewing Table C-1 of Appendix C, NRC IE Bulletin 79-013, Thermal and Radiation Aging Degradation of Selected Materials, shows that poly-ethylene rubber has a potential for significant aging at ten (10) years and an allowable radiation susceptibility of 10' RADS before serious degradation occurs. Evaluating the above establishes the need to perform periodic changeout of trans-mitter 0-rings.

NRC Contract No. NRC-03 79-118 Pag 3 00 Fr:nklinR:searchCcnter FRC Pro}ect No.C5257 A Dwon of The Franklin Institute FRC Assignment No.13 3C 20th and Race Streets. Phila,. Pa. 19103 (215) 448-10 @ FRC Task No. I 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO Additionally, the ti=e span to which Rosemount will qualify its IEEE 373-1974 transmitters is ten (10) years. To assure that listed transmitters within H. 3. Robinson containment remain qgified a ten- (10) year replacement cycle will be adopted Replacement of in-containment transmitters identified within this report has been performed within the 1980 refueling

             ' outage (August - October, 1980).                       At this time, no fully qualified transmitter is available for nuclear plant in-containment operation.                       Rosemount ll53A transmitters, qualified to IEEE 323-1971 version, were used as replacements.

Additional action required - A program of periodic transmitter housing 0-ring replacement (' performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2.) -- To assure Operational capability, a ten- (10) year transmitter replacement schedule has been adopted, to be modified when Rosemount can certif y, by test, longerlifeequipmentisavailable.{j SECTION III - Proposed Corrective Actions for Outstanding Items Electronic transmitters qualified to IEEE-323-1974 are not available. CP&L is a participating member of the Wisconsin Electric ~ curre Transmitter Evaluation Program to test and qualify electronic transmitters for nuclear plant use. Presently, CP&L has upgraded its . master list transmitters within containment to Rosemount 1153A codels which are qualified to IEEE-323-1972. Af ter the current test program is complete - which extends into the fourth quarter of 1982 'CP&L will evaluate the' results, and decide on; action (s) to be taken to provide fully qualified equipments. In the interim, CP&L has established a program which requires changeout of 0-rings when yearly - calibration checks are performed cnd a complete instrument.changeout on ten-year cycles af ter installation dates, to n.11ntain qualification level. O

eu00U Frrnklin a:se:rch C nter NRC C;ntract N;. NRC-03-79-118 FRC Project No. C5257 Pag 3 A Dison of The Frrnkhn Institutz FRC Assignm;nt Nr.13 ' 7a. 20th and Race Streets. Phila.. Pa. 19103 (215) 448-10m FRC Task No. f// . EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. N MAINTENANCE AND REPIACEMENT SCHEDULE SIDi2iARY The following information regarding the maintenance and replacement schedule (s) for components, sub-components, and materials has been provided by the Licensee, is - - Additional action required - A program of periodic transmitter housing 0-ring replacement (performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2. ) To assure operational capability, a ten- (10) year transmitter replace = eat schedule has been adopted, to be modified when Rosemount can . certify, by test, longerlifeequipmentisavailable.{j // l l l -

AS ' NRC Contract No. NRC-03-79-118 P g) LC09 Fr:nklin Rrsetrch Csntir FRC Pr:Joct N3. C5257 A Dwisw>n of The Frankhn Institute FRC Assignment No.13 la 20th and Race Streets. Phda . Pa 19103 (215) 448 1000 FRC Task No. 81/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I EQUIPMENT ITEM NO.15 (TMI ACTION PLAN ITEM II.F.2) PRESSURE TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT MODEL 1153GA9 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO.15 LICENSEE REFERENCE (S): 1764, 4423 FUNCTION (PLANT ID): DETECTION OF INADEQUATE CORE COOLING (PT-500, -501) LICENSEE SUBMITTAL: SCEW(S): 6 OF 15 [15}. DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY (S20 Section 3 of this TER for Legend) R, T, (tr, RT, P, H, CS, A, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated Not applicable i LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Lic3nsee Response to NRC SER 3a, 3b, 3c, Str Syctem Consideration Review ea, u, ,w, ,J, 0-, Of Equipment Environmental Qualification Review 3a, 3v, 1, 50, b , 5 f, 5;, 55 ti, Ej Installed TMI Lessons Learned Implementation 6a, 6b Equipment Summary Maintenance anc Replacement Schedule Summary 7a, 75, 7c

A NRC Contrcct Ns. NRC-03 79-118 000 anklin Rzsezrch Cantsr FRC Pr:: Ject No. C5257 Paga A Dimon of The Frankim institute FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa 19103(215) 448 1000 FRC Task No. (// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /8~ SUMARY OF LICENSEE RESPONSES M THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. The Licensee (bas /has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. 1 The Licensee (has/h . .ut) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. 1 Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equiment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress J Other ( nu1As.s Omf 3<u.A M a d ,A

                                                                                                       )

The Licensee has providbd other informa& t ion $&p k t, aZ for this Jo w & equipme t ,it that can be construed as a basis for justification for interim operation. g The Licensee (has/haa m ) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action m m_1 .) ( / The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

- CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope Not Qualified IV Documentation Not Available

A NRC Contract No. NRC-03 79-118 00 rankhn R search Cent:r FRC Project No.C5257 P:g3 A Dwison of The Frenkhn Instdure FRC Assignment No.13 2 20th and Race Streets. Phaa.. Pa. 19103 (215) 448-1000 FRCTask No. C/ I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 6 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS Xa DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) 1 Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied , Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied X Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied 1 Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test. Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) X DESIGNATION: NRC Qi%LIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qual.ification Not Established II.b Equipmeit Uct Qualified Y' i II.c Equipment Satisfies All Requirements Except Qualified Life I or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available pn Anyphn - i

h NRC Contract No, NRC-03 79-118

.l!00htnkhn Research Center                                                                   FRC Project No,C5257                    Page A DMsk>n of The Frankhn InstWute                                                         FRC Assignment No.13                     3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m FRCTaskNo. 6H EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I sw . Abs.Z To be utilized during THI-2 accident scenario per procedure See accident profile - Temperature - Figure 3.1.1 See accident profile - Pressure - Figure 3.1.2 In containment radiation level established for purchase of component Te,st performed prior to LOCA simulated environmental exposure Rosemount test to IEEE 323-1971 format, currently transmitters under test to meet IEEE 323-1974 requirements '

h5b The Rosemount 1153A Transmitters are currently qualified to IEEE 323-1971. As reported in our 90-day responses these transmitters require a changecut cycle of ten (3.0) years with an 0-Ring replacement after each calibration check to maintain their qualification level. C7&L is part of a utilities group which is underwriting transmitter qualification to IEEE-323-1974 standard.1. As these tests are ongoing, no recommendations or changeout program is being formulated at this time. Upon test completion, C?&L will determine any added transmitter changeout or modification program and report to the NRC its actions. Cpq3

NRC Contract No, NRC 03 79-118 FRC Project No.C5257 Page 00 FrenklinResearchCenter A Dhneson of The Frankhn inetsute FRC Assignment No.13 3b 20th and Race Serests. Phde.. Pa. 19103 (215) 448-1 2 FRC Task No. IIl EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4[ 3.2.2 Electronic Transmitters [I 6) H. B. Robinson's original design and specification called for installation and use of Fisher and Porter electronic trans-mitter for the measurement of Pressure, Level and Flow para-meters. As stated within CP&L response to NRC IE Sulletin 79- , 01 and the 45-day response to NRC IE Bulletin 79-013 CP&L preference, to obtain better operation and maintenance per-formance, is to change out the existing transmitters within containment-to be replaced by Rosemounts' Model No. ll53A. Environmental tests performed on Fisher & Porter's trans-

                     =1tters (Model No. 1032496) indicate failure occurs during the high temperature, steam / chemical spray testing stage while attempting to qualify to IEEE 323-1971 parameters. (Reference WCAP 9157 Environmental Qualification o_f.                    f Safety-Related Class y Process Instrumentation).

Qualification testing of Rosemount Model 1153, Series A, per Rose =ount Report No. 3788 states that the transmitter is qualified per the requirements of IEEE 323-1971. Missing from this report is the aging pcrameter not required for IEEE 323-1971 but necessary for complete LOCA qualification. Recent Rosemount testing to qualify a transmitter to meet IEEE 323-1974 requirements has resulted in failure. A combination of thermal aging, irradiation and chemical spray test speci-fication parameters has resulted in failed components. The initial failed element was an 0-ring comprised of sulphur cured polyethylene rubber. This allowed steam / chemical spray to affect electronic co=ponents. The 0-ring mode of failure is attributed to high temperature vs. time necessary for the Arrhenius curve time compression to satisfy aging test re-quirements. This testing failure does not preclude the use of the Rese-

                    =ount 1153A within H. 3. Robinson containment as it has successfully performed within the H. 3. Robinson accident parameters of temperature, pressure and radiation levels.

Transmitters located in containment will be required to perfor= within a maximum time period of twenty-f our (24) hours following accident. 0-ring failure due to high temperature should not occur during this time period. Reviewing Table C-1 "of Appendix C, NRC II 3ulletin 79-013, Thernal and Radiation Acing Degradation ej. Selected Materials, shows that poly-ethylenerubberhasapotentialforsignificantagingat09n ' (10) years and an allowabic radiation susceptibility of 10 RADS before serious degradation occurs. Evaluating the abore establishes'the need to perform periodic changeout of trans-

                     =itter 0-rings.

A NRC Contract No, NRC-03 79-118 FRC Project No.C5257 Page 000bnklin Research Center A Divis6on of The Frankhn Institute FRC Assignment No.13 3C 20th and Race Streets. Phila.. Pa. 19103 (215) 4481c00 FRC Task No. S il EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .LC Additionally, the time span to which Rosemo.unt will qualify its IEEE 373-1974 transmitters is ten (10) years. To assure that listed transuitters within H. B. Robinson containment remain ified a ten- (10) year replacement cycle will be adopted Replacement'of in-containment transmitters identified within this report has been performed within the 1980 refueling

                 ' outage (August - October, 1980).                      At this time, no fully qualified transmitter is available for nuclear plant in-containment operation. Rosemount 1153A transmitters, qualified to IEEE 323-1971 version, were used as replacements.

Additional action required - A program of periodic transmitter housing 0-ring replacement (' performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2. ) To assure operational capability, a ten- (10) year transmitter ep cement schedule has been adopted, to be modified when Rosemount can certif y, by test, longerlifeequipmentisavailable.{f , SECTION III - Proposed Corrective Action $ for Outstanding Items . Electronic tra sitters qualified to IEEE-323-1974 are not currently

    *available.           CP&L is a participating member of the Wisconsin Electric'                                +

Transmitter Evaluation Program to test and qualify electronic transmitters for

 . nuclear plant use. Presently, CP&L has upgraded its . master list transmitters l     within containment to Rosemount 1153A codels which are qualified to l      IEEE-323-1972. After the current test progra= is complete                                which' extends

• into the fourth quarter of 1982 'CP&L will evaluatie the results, and decide ouy action (s), to be taken to provide fully qualified equipments. In the interim, CP&L has established a program which requires changeout. of 0-rings when yearly' calibration checks are performed and a co=plete instrument changeout on ten-year cycles af ter installation dates, to maintain qualification 'evel. l DC

4 NRC Contract No. NRC 0S 79118 FRC Project N3.CS267 Page UU0U Fr:nklin R: search Ccnter A DMeson of The Frankhn inmuute FRC Assignment No.13 60 20th and Race Sweees. Phde.. Pa.19103 (215) 4481000 FRCTask No. P# EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J.f INSTALLED TMI LESSONS LEARNED IMPLEMENTATION EQUIPMENT

SUMMARY

NRC requested an evaluation of the environmental qualification of safety-rolsted electrical equipment located in harsh environments required for TMI Le:: sons Imarned Implementatie,a. The objective is to evaluate qualification documentation of equipment within the scope of IE Bulletin 79-018, Supplement 3 (item 2), in accordance with criteria established-by the NRC (see Section 2 cf this report) in a manner identical to the evaluation of all other safety-roleted electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with specific sections of NUREG-0737 which h ve an instiallation implementation date of January 1,1981 (sections are idsntified below) . Where applicable, a review is to be performed on installed equipment with implementation dates after January 1, 1981 if adequately id:ntified by the licensee. Thic plant is a PWR [ , BWR . The NSSS Vendor is Westinghouse (W)1, Babcox & Wilcox (B&W) , Combustion Engineering (CE) , General Electric (GE) . With respect to this equipment item, it is noted (applicable section checked): The Licensee does not provide adequate information with respect to identification of TMI Action Plan equipment installed as of 1/1/81. The Licensee has not provided the correlation of this equipment item with the specific sections of NUREG-0737. (The correlation is needed to ensure that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal blocks associated with the device also identified?} The Licensee has not provided the approximate installation date for the TMI' Action Plan equipment items so that the appropriate qualification criteria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. The Licensee has provided a standard Owners' Group position with respect to a NUREG-0737 technical area. The Licensee has requested extensions of implementation dates. 1 The Licensee has stated that this equipment item is associated with the following cection of NUREG-0737. (This list of applicable NUREG-0737 sections has been identified by NRC as sections within the scope of this review): II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment II.D.3 (ALL/1-1-81) Direct Indication of Relief and Safety Valve Position

NRC Contract Nr. NRC-03-79-118 ph~ UOb r:nklin Research Ccnt:r FRC Project NO. C5257 Page A Dhnsion of The Franklin Institute FRC Assignment No.13 6b 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. 8// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./.,C II.E.1.2 (PWR/1-1-81) Auxiliary Feedwater System Automatic Initiation and Flow Indication II.E.3.1 (PWR/1-1-81) Emergency Power Supply for Pressurizer Heaters (Safety-Grade Interfaces . II.E.4.1 (ALL/7-1-81) Ded!.cated Hydrogen Penetrations II.E.4.2 -(ALL/1-1-81) Containment Isolation Dependability [ II.F.2 (PWR/1-1-81) Instrumentation for Detection of Inadequate Core Cooling II.G.1 (PWR/1-1-81) Emergency Power for Pressurizer Equipment (Safety-Grade Interfaces) II.K.2.10 (PWR/B&W/7-1-81) . Safety-Grade Anticipatory Reactor Trip II.K.3.9 (PWR/W/1-1-81) PID Controller Modification (If Hardware Change Involved) II.K.3.12 (PWR/W/1-1-81) Anticipatory Reactor Trip upon Turbine Trip II.K.3.13 (BWR/GE/7-1-81) Separation of HPCI and RCIC Initiatica Signals II.K.3.15 (BWR/GE/7-1-81) Prevention of Spurious Isolation of HPCI and RCIC Systems II.K.3.19 (BWR/GE/7-1-81) Interlock on Recirculation Pump Loop I i II.K.3.21 (BWR/GE/7-1-81) Restart of Core Spray and LPCI Systems'(If l Hardware Char.ged Out) II.K.3.27 (BWR/GE/7-1-81) Provide Common Reference Level for Vessel Level Instrumentation (If Hardware Changed Out) l l l l l l l

h NRC Contract No. NRC-03-79-118 000 r::nklin R: search Ccnter FRC Project No. C5257 Page A Divmon of The Frankhn Institute FRC Aasignment No.13 7q 20th and Race Streets. Phda.. Pa 19103 (215) 448-1000 FRC Task No. J// l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./l~ l MAINTENANCE AND REPLACDENT SCHEDULE SIMMARY The following information regarding the maintenance and replacement sch:dule(s) for components, sub-components, and materials has been provided by the Licensee. te Additional action required - A program of periodic transmitter housing 0-ring replace =ent (performed during yearly instrument calibration check) will provide boron spray protection capability if an accident ever occurs. (See Pargaraph 3.2.2. ) To assure - operational capability, a ten- (10) year transmitter replacement schedule has been adopted, to be modified when Rosemount can certify, by test, longer life equipment is available. { //

  /A                                                             NRC Contract NO. NRC-03-79-118 Pag 3 LOIju Fr:nklin R:se:rch Cent:r                                FRC Project Nr. C5257 A Divmon of The Fr:ntan Instituti                         FRC Assignment Nr.13                                                                     la 20th and Race Streets. Phila.. Pa 19103(215)448-1000      FRC Task No.             5//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. Oa. EQUIPMENT ITEM NO.16 (TMI ACTION PLAN ITEM II.F.1.5) LEVEL TRANSMITTER LOCATED IN THE CONTAINMENT CEMS MODEL XM52495 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO.16 LICENSEE REFERENCE (S): 1887 FUNCTION (PLANT ID): CONTAlltiENT SUMP WATER LEVEL (LT-801A, B, C, D) LICENSEE SUBMITTAL: SCEW(S): 12 of 15 [15]

  -DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLYI (See Section 3 of this TER for Legend)

R, T, QT, RF, P, H, CS, A, S, (R) , M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not state applic LISTING 0F APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, OL, L, M-A= Ah '- if System Consideration Review 4d. '0, Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, 5f, 5g, Sh, Ci, 4 Installed TMI Lessons Learned Implementation 6a, 4tr Equipment Summary Maintenance and Replacement Schedule Summary 7a, 7L, 7e

l NRC Contract N 2. NRC-03-79-118 phr UO0nklinResearchC:nter FRC Prelect N2. C5257 Page A Dwmon of The Frankhn Institute FRC Assignment No.13 lb 20 h and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. f// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _/k

SUMMARY

OF LICENSEE RESPONSES 'IO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: g Tne Licensee (has/M- -^t) provided a response to the SER concerns. l i The Licensee (has/has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE cnvironmental service conditions. ' [ The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. h etion specified by the Licensees has I,are,, peplaced 1 Equipment : ;12: z t with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radi& tion source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification cnd/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

  - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope Q Not Qualified IV Documentation Not Available

NRC Contract No, NRC-03-79-118 OL Fr:nklin R: search Center FRC Project No.C5257 Pace A Dwwon of The Frankhn Instuute FRC Assignment No.13 2 20th and Race Sereets. Phde.. Pa. 19103(215) 448 1000 FRCTaskNo. S// EQUIPMENT ENV!RONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. ./4. EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation. Evaluated Adequately g Qualified Life or Replacement Schedule Established (If Required) A Program Established to Identify Aging Degradation X Criteria Regarding Aging Simulation Satisfied (If Required) X Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied gA Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satiafied 1 Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied g Criteria Regarding Instrement Accuracy Satisfied 1 Test Duration Margin (1 hour + Function Time) Satisfied _ Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) 1 DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified 1 II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment D empt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available i

NRC Contract N3. NRC-03-79-118 Pago

       @O0hr:nklin Research Ccnter U                                                                                                                                                                             FRC Project N2. C5257 A DMsion of The Frankhn Insettute                                                                                                                                        FRC Asalgnment No.13                        3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000                                                                                                                   FRCTask No. SII l      EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ./I LICENSEE RESPONSE TO NRC SER I

The level switch reported is for containment sump level indication cnd has been superceded in place by two GEMS level transmitters Model No. XM36495 as part of the M lessons learned action items. This system is currently reported in our response to the TMI Equipment requirement submitted in February, 1981.

         ,                                                                                                                                                                                         IM)

Madison 5602 1 R,T,QT,RT,P,H, J (i.evalSwitch - CS,A,QM g C#U See, accident profile ' Temperature - Figure 3.1'.1 See accident profile - Pressure - Figure 3.1.2 To be utilized during.THI-2 accident scenario per procedure Eguipment tested to IEEE-323-1971 System designed to measure sequential flood levels

 -                           - __                                                  _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                              -__ - ____          ~

A NRC Contract N2. NRC43 79-118 ll00hr:nklin Rese:rch Ccnter FRC Project NO. C5257 Page A Division of The Franklin Instauti FRC Atsignment N3.13 5a 20th and Race Streets. Phila.. Pa. 19103 (215) 448 lom FRC Task No. 5 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _%t EQUIPMENT ENVIROletENTAL QUALIFICATION REVIEW Criteria: DOR Guidelines ' ; NUREG-0588, Cat. I X ; NUREG-0588, Cat. II . NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) EQUIPMENT DESCRIPTION ll.EVEL.  !  ! Equipment Type  !"I~RANsmtTTT.R!  ! Manu ctu r's Name

                                                           .Dutt,Ayng/Gmsi Dr lavas./G res
                                                                             ,                              l Model Number (5.2.2/-/-)                                                   '

XM36495 ' Serial Number  ;  ;  ; Features / Mounting  ; 3 (5.2.6/-/-)  : g Connections / Interfaces { ND CONDUgy , GE R.ry- c.o i (5.2.6/-/-) . Location / Elevation e CoNTAINME.NTj *!

                                                          ! 231.Z'           !                             !

Equipment ID No. g (7 ggg g  !- LT 802  ! I QUALIFICATION REPORT g i (8.0/5.0/5.0)  ;  ; Report ID Number

                                                                             ! F-C'5BM , S-C3834           ' NOTE i ?-   i Report Date                                                                                             '

i 3 g Issued by , i e

                                                                             ; FIRL Prepared for

• i

' , .OcLAvAt./ Gems  ; Referenced Reports * * . Qualification Method I I I (5.1, 5. 3/2.1, 2. 4/2.1, 2. 4) ' TYPE. TEST I QUALIFICATION TEST PROGRAM I Functional Test Description '. I (5.2.5/2.2.9/2.2.9)  !  !  ! Operating Conditions  !  !  ! (-/2.2.10/2.2.10)  !  !  ! Ioad/ Cycles / Voltage /  !  ! 10 VAC cia.cusT votT. AGE !

       ' current /Freq.                                   !                  I                           I
                                                                                                                  =.=

4000U Franklin Research Ccnter NRC Contract No. NRC-03 79-118 FRC Project No. C5257 Pag 3

                                                                                                               )

A DMwn of The Ftrnklin Institus2 FRC Assignment No.13 5b 20th and Race Streets. Phila.. Pa. 19103 (215) 44810m FRCTaskNo. 511 EQU!PMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _.lio NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.)

• Not Acc:ptance Criteria  !  ! 1mEAsunto

( 5. 2. 5/2. 2.1/2. 2.1)  !  ! E.x c.E.ssivr. OuvruT  ! As A

    ,                                             .                . E" R.R.O R             ,   'J.e A6E Accuracy (5.2.5/-/-)                              .

1 ND *

                                                                   !     N OT STATE.o          !

Number of Specimens  !  !  !

                                                  !                !         i                 !

T00t Instruments Calibrated !  !  ! Safcty Function (Active /  ! CONT.bu C Pcccive) (-/2.1. 3/ 2.1. 3) g Q,g Test Duration (5.2.1/-/-) 1

                                                  !                !   14 oAxs                 !

Accident Duration (Envir. 1,  !  ! Abova Normal) (5.2.1/-/-)  !  !  ! Required Function Time LO N G "T' EW* Tact Sequence (General)  !  !  ! (5.2.3/2.3.1/2.3.1)  !  !  !

                                                  !                !   S 1 MutTAN Ecu S        !

Tect Sequence (NUREG-0588,  !  !  ! C:t. I) (-/ 2. 3.1/-)  !  !  !

1. Representative Sample  !  !  !

2. Baseline Data  !  !  !

3. Performance Extremes  !  !  !

4. Thermal Aging 1 1 1

5. Radiation Aging  !  !  !

6. Wear Aging  !  !  !

7. Vibration / Seismic  !  !  !

8. DBE Exposure  !  !  !

9. Post-DBE Exposure  !  !  !

10. Inspection  !  !  !

Aging  !  !  ! (5.2.4, 7.0/4.0/4.0)  !  ! ND  ! norg, 3 Th;rmal Aging / Basis  !  ! Matsrial Aging  !  !  ! Evcluation (7.0/-/-)  !  !  ! Matorials Susceptible  !  !  ! (Thstmal) (5. 2. 4, 7. 0/-/-)  !  !  ! Radiation Aging, Type  !  ! '

NRC Contract No. NRC-03-79-118

  @bODEr:nklin R:se:rch Cent:r                                                     FRC Project N3. C5257                      Pag 3 A Dusbn of The Frankhn Institute                                       FRC Assignment No.13                        5c 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000                 FRCTask No. 5\1 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.14.

NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.1

                                                        !                             1                           1 Radiation Aging, Dose (rd)                                     No                        25, x lO 6               i Radiation Aging, Dose Rate                                                                                        i i.50-200dhiI'O W b-           ,                              ,

Radiation Aging, Method  !  ! Materials Susceptible  ! (Radiation) (5.2.4, 7.0/-/-) ! ;SlWCONE1:LUlO Operational Aging  !  ;  ; (-/4.2/-)  ! t , Other Age Conditioning  ! * - (-/4.2/-)  ! Qualified Life Claimed /  ! 1 NOM 4 Established (5.2.4/4.10/-)  ! ND ND Normal Ambient Temperature  ! I I Il5'F  ! . - Normal Ambient Radiation  ! Normal Ambient Humidity :50-200 dd.1  ! lNoT STATE.D I  ! On-Going Surveillance and  !  !  !, Preventive Maintenance  !  !  ! PER, (7.0/-/-)

• yES '

PRcGRAM. On-Going Analysis of  !  !  ! Failures and Degradation !ygg  !  ! (7.0/-/-)  !  !'  ! Margin (General)  !  !  ! (6.0/3.0/3.0)  !  !  ! Margin (NUREG-0588,  !  !  ! Cat. I) (-/3.2/-)  !  !  !

1. Temperature (+15'F)  !  !  !

2. Pressure (+10%,  !  !  !

10 psig max)  !  !  !

3. Radiation  !  !  !

(not required)  !  !  !

4. Time (+10%, +1 hour  !  !  !

            + function time minimum)                        !                            !                             !

NRC Contract No. NRC43-79-118 00 Fr:nklin Rese:rch Center FRC Project No.C5257 Page A DMmon of The Frankhn inanute FRC Assignment No.13 5d 20th and Race Sweets. Phila.. Pa. 19103 (215) 448-1000 FRCTaskNo. 91 __ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .lfo NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS  !  ! . 1 IDCA/MSLB/HELB/ Uncontrolled ! ', I (4.1, 4.2, 4.3.1, 4.3.3/  ! L0C A  ; LO C, A 3 1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) !  ! Radiation Type  ! 1

                  ~
                                                 ! gpg            ; b AMMA                   !

Radiation Dose (rd)  !

• G  !

(4.1. 2/1. 4/1. 4)  ! ' 175.O x to  : I

• I Radiation Dose Rate (rd/hr)  !
• Radiation Qual. Method  !
• O a x to C'  !

(5.3.1/-/-)  !  !  ! Proximity to Concentrated  ! I  ! Radiation !C '"T""""T I  ! ( 4.1. 2/1. 4. 6/1. 4. 6)  ! "  !  ! Equipment Susceptible to  !  !  ! Beta Radiation (4.1.2/-/-)  !  !  ! Radiation Dose (Normal + 1 I  ! Accident) (4.1.2/-/-) ' ' Z.O x 1O 8 Plateout Dose Considered  !  !  ! 8 ' (-/1. 48/1. 4 8)  ! ?..Ox 10 d. ' Gamma + Beta Dose (rd)  !  !  ! (4.1.2/1.4.7/1.4.7)  !  !  : J

A HRC Contract No. NRC-03-79-118 000Errnkiin ar 1res center FRC r roject N2.Cs2sy Pag 3 A DMan of The Franklin Instut2 FRC A:signment Ns.13 5e 20th and Race Streets. Phila.. Pa. 19103(215) 448-1000 FRCTaskNo. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .l_G2 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIRONMENTAL PROFILE  !  !  ! OF ACCIDENT CONDITIONS  !  ! Rate of Temp./ Press. l  ; ~ 9 e*% ,15 P553 /s  ;

                                                  .&.58 F[s ,    *    ~"

Increase

                                                     ~ 4.2 PS'i3/s f                              f Peaks     *F/psig/RH/ Time                          2C 5/42/ico/3H          /GO /.100 /l br.     [

Decrease To: 'F/psig/RH/ Time gq/20/too/21H !*150 G 5 100 14 o^YS  ! Decrease To: 'F/psig/RH/ Time !!T2[5[ loo [-p- ! ' Decrease To: *F/psig/RH/ Time :

                                                                  ~

Equipment Surface Tempera-  !  ! ture (MSLB) (-/1.2.5.C, J-  ! 2.2.6/1.2.5.C, 2.2.6) g  ! Spray Qualification Method  !  ! NO SPRAY W TY_GT I (5.3.2/1.3, 2.2.8/1.3,  ;  ; PROGRAM. I NOTE. 3 2.2.8) .  ! i Spray Composition ji, Twt.% k I l (4.1.4/1.3, 2.2.8/ . Bogic Acio :  !

1. 3, 2. 2. 8)

                                                  } Ph*9.3
                                                                     .                            .f l Spray Density (gpm/f t 2)                        g Spray Duration                                   !                  !                            !

Submergence Duration  !  !  ! ( 4.1. 3/2. 2. 5/2. 2. 5)  !  !  ! In-Leakage Considered  !  !  ! (5.2.6, 5.3.2/-/-)  !  !  ! Time to Submergence  !  !  ! Dust Environment  !  !  ! (-/2.2.11/2 2.11)  !  !  ! I

NRC Contract N3. NRC 03-79-118 00 Fr:nklin Research Center FRC Project NO. C5257 Pcg3 A DMsaon of The FrankDn Insneut FRC Assignment No.13 55 20th and Race Sereets. Phda.. Pa. 19103 (215) 44810m FRC Task No. 5 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. ife i NOTES:

1. FI.RL .ha m m,+ v-c.3834 3m c - t n., e ,o -

m ereftCDtbO(uJ2. , 0 c-v, M_o <0Jom e em

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c 6!!00hr:nkhn R:seirch Ccnter NRC Contract No. NRC-03 79-118 FRC Project Nr. C5257 Pag 3 A DMuon of The Frankhn Insntuta TRC Assignment N2.13 53 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTask No. Sil EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.17 l l NOTES:

• T1o_ %+ ,n4 n cwy~ cduD rrwi < hat c c , ,

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3. T ._ L , A } . w% O%4 s - n of The Franidin Insutute FRC A'signment N3.13 5b 20th and Race Streets. Phila.. Pa. 19103 (215) 448-10M FRCTask No. 5ti EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. i'l NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.)

nox wAwnto - Acceptance Criteria i E.xc.r. wive Ouvrut  ! % g %, ( 5. 2. 5/2. 2. J/2. 2.1)  !  ! U R*"  ! NoTEi Accuracy (5.2.5/-/-)  ! go  ! Nov Srkts.D  ! K Number of Specimens  !  ! j  ! T3ct Instruments Calibrated !  ! - Sifety Function (Active / 2 Cour. Sump !  ! Pacsive) (-/2.1. 3/2.1. 3) 1 War gg, b.vt.L!  ! Test Duration (5.2.1/-/-) - WS Accident Duration (Envir.  !-  !  ! Above Normal) (5.2.1/-/-)  !  !  ! Required Function Time  ! L.O NG T E.W!  ! Tact Sequence (General)  !  ! S 1 mut. TAN E.ou S I ( 5. 2. 3/2. 3.1/2. 3.1)  !  !  ! Test Sequence (NUKEG-0588,  !  !  ! Cat. I) (-/2.3.1/-)  !  !  ! X

1. Representative Sample  !  !  !

2. Baseline Data  !  !  !

3. Performance Extremes  !  !  !

4. Thermal Aging  !  !  !

5. Radiation Aging  !  !  !

6. Wear Aging  !  ! 1

7. Vibration / Seismic  !  !  !

8. DBE Exposure  !  !  !

9. Post-DBE Exposure  !  !  !

10. Inspection  !  !  !

Aging 1  ! , 1 (5.2.4, 7.0/4.0/4.0)  ! b4 D Thirmal Aging / Basis  !  !

                                                                                                      !! worr. 5 Matsrial Aging                                          !                !                             !

Evcluation (7.0/-/-)  !  !  ! Materials Susceptible  !  !  ! (Tharmal) (5.2.4, 7.0/-/-)  !  !  ! Radiation Aging, Type  !  ! '.

NRC Contract No. NRC-03 79-118 LOO Fr:nklin R:sench Center FRC Project N3. CS257 Page A,Divis6on of The Frankhn In::: uts FRC Assignment N2.13 $C 20th and Race Streets. Phde. Pa. 19103 (215) 448-1000 FRCTask No. 5M EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. O NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) 8 6 Radiation Aging, Dose (rd) 3

                                                  !        ND       !    25. x 40               !

Radiation Aging, Dose Rate  ! 50 200"'M !* 1. O Med /hc*  ! Radiation Aging, Method  !  !  ! Materials Susceptible  !  ! S ILICONE 1:LUlO I (Radiation) (5.2.4, 7.0/-/-) 1  !  ! Operational Aging  !  !  ! (-/4.2/-)  !  !  ! Other Age Conditioning  !  ! 3 (-/4.2/-)  !  ! g Qualified Life Claimed / k ND k NO i NOTE.4 Established (5.2.4/4.10/-)  !  !  ! Normal Ambient Temperature  ! Il5'F  !  ! Normal Ambient Radiation 150-200 "Yh. !  ! Normal Ambient Humidity !no r STATED !  ! On-Going Surveillance and  !  !  ! PER Preventive Maintenance  ! yES  !  ! pjt

                                                                                                    !(pgaggag (7.0/-/-)                                       !                 !

On-Going Analysis of  !  !  ! Failures and Degradation  ! ygg  !  ! (7.0 /-/-)  !  !  ! Margin (General)  !  !  ! l 1 (6. 0/3. 0/3. 0) 1 1 i

                                                    !                 !                              !               l l

Margin (NUREG-0588,  !  !  ! l Cat. I) (-/3. 2/-)  !  !  ! [ ]

1. Temperature (+15'F)  !  !

2. Pressure (+10%,  !  !  !  !

10 psig max)  !  !  ! l i 3. Radiation  !  !  ! f (not required)  !  !  !

4. Time (+10%, +1 hour  !  !  !

       + function time minimum)                      !                 !                              !

NRC Contract No. NRC 03-79-118

  @OUhr:nklin Research C:nter U                                                               FRC Project N2.C5257                                                                            Page A DMiam of The Frankhn Institute                           FRC Assignment No.13                                                                                           5d 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000     FRC Task No. 51)

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.1"}_ NRC REQUIREMENTS DEFICIENCY WITH SECTION PEFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUME!1TATION NOTE NO.) ACCIDENT CONDITIONS 1 1  !

 'IDCA/MSLB/HELB/ Uncontrolled !                                        !   LO C,A (4.1, 4.2, 4.3.1, 4.3.3/                          ! LOC A            !                                       !

1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) !  !  ! Radiation Type  ! G ame*A  !

                                                     !-                 ! ggm           g 1

Radiation Dose (rd)  !  ! 175.0 x to 1 (4.1.2/1.4/1.4)  !  !  ! Radiation Dose Rate (rd/hr) 1  ! O.7 x to g 1 Radiation Qual. Method  !  !  ! (5.3.1/-/-)  !  !  ! Proximity to Concentrated  ! C onmmt.NT !  ! Radiation  ! b"'  !  ! ( 4.1. 2/1. 4. 6/1. 4. 6) .!  !  ! Equipment Susceptible to  !  !  ! Beta Radiation (4.1.2/-/-)  !  !  ! Radiation Dose (Normal +  !  ! 2.0xtog 1 Accident) (4.1.2/-/-)  !  !  ! Plcteout Dose Considered  ! 2,.0x 10 8

d. '  !

(-/1. 4 8/1. 48)  !  !  ! Gamma + Beta Dose (rd) 1  !  ! (4.1.2/1.4.7/1.4.7)  !  !  !

A NRC Contract Nr. NRC-03-79-118 000hrinklin R:se:rch Center FRC Project N2. C5257 Pag 3 A Divison of The Frinkiin insntut FRC Assignment N3.13 5e FRCTaskNo. 511

                                                                                                               ~

20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. O NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR . (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE Nod ENVIRONMENTAL PROFILE 1  !  ! OF ACCIDENT CONDITIONS  !  !  ! Rate of Temp./ Press. N 's erfs. ' ' Increase g py,3f3 Peaks *F/psig/RH/ Time O /_100 /1 hr. ,i 2C.5/42/soo/3H . .

                                                                                                                                                            ~

Decrease To: *F/psig/RH/ Time 1211/20/too/21H I150 e.5/ico/14 oAvs 1

                                                       !                           !                         s                   !

Decrease To: *F/psig/RH/ Time !!52/5[too/-P !  ! Decrease To: *F/psig/RH/ Time !  !

                                                      !                            !                                             1-   ,

Equipment Surface Tempera-  !  !  ! ture (MSLB) (-/1.2.5.C,  !  !  ! 2.2.6/1.2.5.C, 2.2.6)  !  !  ! Spray Qualification Method  !  ! No SPRAY IN Tt$T  ! NOTE 3

                                                                                                                                                                         ~

(5.3.2/1.3, 2.2.8/1.3,  !  ! PROGRApA.  ! , 2.2.8)  !  !  ! ' Spray Composition l l .ht. *Ze . I 1 (4.1.4/1.3, 2.2.8/  ! Benic Acto !  ! l

1. 3, 2. 2. 8)  ! Phs9.3  !  ! 1

                                                                                                                                                ' '                            ^

I Spray Density (gpm/f t 2) g  !  ; Spray Duration  !  !  ! ) Submergence Durati'on h C"N *E* k ' J

 , (4.1.3/2.2.5/2.2.5)                                !                            !                                             !                                  p            )
                                                       !                           !                                             !                                     i ,

In-Leakage Considered  !  ! z! \ (5. 2. 6, 5. 3. 2/-/-)  !  ! ' ik l Time to Submergence  !  ! , -! Dust Environment  !  !  ! )* (-/2.2.11/2 2.11)  !  !  ! ' s

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NRC Contract N3. NRC-03 79118 Pag]

       @O0hrInklin R:se:rch Canter U                                                                         FRC Project No. C5257 A Dwison of The Frankitn Insutut)                                    FRC Asaignment NO.13                                       5g 20th and Race Streets. Phita.. Pa. 19103 (215) 448-10m               FRC Task No. Sil                                               '

EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. l'1 NOTES:

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4 NRC Contract No. NRC 03-79-118 FRC Project N2.C5257 Page U000 Fr:nklin R:serreh canter A DMs6on of The FrankhnInsmute FRC Assignment No.13 60 20th and Race Streets. Phde.. Pa. 19103(215) 448 1000 FRC Task No. 8 /f EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _C. INSTALLED TMI LESSONS LEARNED IMPLEMENTATION EQUIPMENT

SUMMARY

NRC requested an evaluation of the environmental qualification of safety-rolsted electrical equipment located in harsh environments required for TMI Le sons Learned Implementation. The objective is to evaluate qualification documentation of equipment within the scope of IE Bulletin 79-OlB, Supplement 3 (item 2), 'in accordance with criteria established-by the NRC (see Section 2 cf this report) in a manner identical to the evaluation of all other safety-rolated electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with specific sections of NUREG-0737 which have an instiallation implementation date of January 1,1981 (sections are id ;ntified below) . Where applicable, a review is to be performed on installed equipment with implementation dates after January 1, 1981 if adequately id ntified by the licensee. This plant is a PWR 1 , BWR . Th3 NSSS Vendor is Westinghouse (W)[, Babcox & Wilcox (B&W) , Combustion Engineering (CE) , General Electric (GB) . With respect to this equipment ites, it is noted (applicable section checked): The Licensee does not provide adequate information with respect to identification ot TMI Action Plan equipment installed as of 1/1/81. The Licensee has not provided the correlation of this equipment item with the specific rections of NUREG-0737. [The correlation is needed to ensure that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal blocks associated with the device also identified?] The Licensee has not provided the approximate installation date for the THI' Action Plan equipment items so that the appropriate qualification crittria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. The Licensee has provided a standard Owners' Group position with respect to a NUREG-0737 technical area. The Licensee has requested extensions of implementation dates. 4 The Licensee has stated that this equipment item is associated with the following section of NUREG-0737. (This list of applicable NUREG-0737 sections has been identified by NRC as sections within the scope of this review) : II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment II.D.3 ( ALL/1-1-81) Direct Indication of Relief and Safety Valve Position

            -> H. F.1. c 0-LA (4J4 cY & .
           -                                                             --            -                 - - - ~

    #%                                                          NRC Contract N 3. NRC-03-79-118 h00EFrrnklin Reserrch Csntir                               FRC Project N3. C5257                    P:ga A Dmsson of The Frankhn Institute                      FRC Assignment No.13                      lc 20th and Race Streets. Phila.. Pa 19103(215) 448 1000  FRC Task No.         (//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _/2 EQUIPMENT ITEM NO.18 TEMPERATURE ELEMENT LOCATED IN THE CONTAINMENT, ELEV. 243'0" ROSEMOUNT MODEL 176KF REQUIRED OPERATING TIME: 1 HOUR TER CHECKSHEET NO. 18 LICENSEE REFERENCE (S): 687 FUNCTION (PLANT ID): MAIN STEAM LINE BREAK DETECTION, LOOP 1 (TE-412B, D) LICENSEE SUBMITTAL: SCEW(S): 14 0F 25 [20] FUNCTION (PLANT ID): MAIN STEAM LINE BREAK DETECTION, LOOP 2 (TE-422B, D) LICENSEE SUBMITTAL: SCEW(S): 15 0F 25 [20] FUNCTION (PLANT ID): MAIN STEAM LINE BREAK DETECTION, LOOP 3 (TE-432B, D) LICENSEE SUBMITTAL: SCEW(S): 16 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITD((S) ONLY: (See Section 3 of this TER for Legend) hT,QT, IC, P, H, S, (R) , M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, Oh, h, 2d System Consideration Review 4a, 4b, 4c, Od, L, en Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, Sf, 5g, Sh, Si, Sj Installed TMI Lessons Learned Implementation E. Sb Equipment Summary Maintenance and Replacement Schedule Summary h . "' h im I

NRC Contract No. NRC-03-79-118 00 Funklin R se:rch Cent:r FRC Project N .C5257 Pag) A DMsen of The Franklin Institute FRC Assignment No.13 lb 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. 8 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M SUeG4ARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: [ Tne Licensee (has/':r : t) provided a response to the SER concerns. I The Licensee (has/......2) specifically stated that the equipment is qualified and g will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement w"ith qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) X The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EJALUATION CATEGORY BASED ON REVIEW

 - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)                                                                                                                                             l I.c Qualified                                                                                                                                              II.c Qualified Life Deficiency I     Modification                                                                                                                                         III.a Exempt I. Qualification Not Established                                                                                                                       III.b Not in Scope II.b Not Qualified                                                                                                                                         IV     Documentation Not Available

 ~

NRC Contract NT. NRC-03-79-118 FRC Project No. C5257 Page BOO Franklin R: search C:nter A Divisk>n of The Frankhn Institut> FRC Assignment No.13 2 20th and Race Streets. Phda , Pa. 19103 (215) 448-lm) FRCTask No. C// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. /[. EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate 1 Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately 1 Qualified Life or Replacement Schedule Established (If Required) Y Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately X o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied X Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied g Criteria Regarding Instrument Accuracy Satisfied X Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0583, Cat. I) L  : DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY l l I.a Equipment Qualified l I.b Equipment Qualification Pending Modification j II.a Equipment Qualification Not Established Y 1 II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification I III.o Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available l

NRC Contract N D. NRC-03-79-118 Page 4l}00U Fr2nklin Research Center FRC Project NO. C5257 A Divisen of The Frankhn Institute FRC Assignment No.13 3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1 2 0 FRC Task No. # /I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .!_f LICENSEE RESPONSE 'IO NRC SER Equipment Descriotion Manufacturer Model No. Location'1 Ceficiency A. Temperature Element Rosemount 176KF 1 R,CS,A A Ice =s reported as qualified within NRC Region II revised TER, dated 11/7/80.- Not required for DBE - only used for outside containment Main Steant Line Break protection 6

A p NRC Contract N . NRC-03-79-118 UQfid Fr2nklin arse rch Cxnter FRC Project No. C5257 Page A Dmsson of The Frtnkhn Insr uti FRC Assignment Nr.13 4a 20th and Race Streets. Phila.. Pa. 19103 (215) 448-tm0 FRC Task No. 5"/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITE'M NO. .!A_ SYSTEM CONSIDERATION REVIEW The Licensee has stated that this equipment item does not require environmental qualification and/or should be exempted from qualification. The Licensee's rationale has been evaluated and the reasons for cencurr e/ non-concurrence with the technical basis of the Licensee's position are presented below. Reason for Concurrence Reason ~for Non-Concurrence Equipment does not provide a Backup (equipment / system) is not safety function or mitigate the fully capable of performing the consequences of a design basis intended safety function or accident accident. Equipment Environ- mitigating function. mental Qualification is not required by the DOR Guide- Backup (equipment / system) is not lines. (NRC Qualification environmentally qualified and can Evaluation Category IIIa) be exposed to a hostile environment simultaneously with the primary equipment. Equipment is not exposed to a Backup (equipment / system) is harsh environment by the subject to a potentially disabling accident it is intended to single active failure. mitigate. See note (1) on page 4b. (NRC Qualification Failure of the primary equipment can Evaluation Category IIIb) compromise the ability of other safety-related equipment to perform Backup (equipment / system) is its specified safety function. available which completely per-forms the safety function. The X Failure of the primary equipment can backup (equipment / system) is result in erroneous indication which environmentally qualified and could mislead an operator. appears to meet single active failure criterion. See note (1) X Requirement for continued function-on page 4b. (NRC Qualification ing throughout the post-accident Evaluation Category IIIa) period necessitates environmental qualification.

NRC Contract N;. NRC-03-79-118 00 Fr:nklin R: search Ccnter FRC Project N3. C5257 Page A DMsion of The Franklin institute FRC Assignment No.13 4h 10th and Race Streets. Phita.. Pa. 19103 (215) 448 1000 FRC Task No. SU EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .!O_ Reeson for Concurrence Reason for Non-Concurrence Tne equipment's accident miti- Although backup equipment is avail-gating function is completed able, it is not technically sound to prior to the onset of the hostile relinquish defense-in-depth for this environment. No subsequent function. functions are_necessary. See note (1) below. (NRC Qualifi- Backup (equipment / system) is not cation Evaluation Category IIIb) safety-related. Other (see page ) X< This equipment is necessary for the operator to ensure an ESF system is Resultant NRC Qualification performing its intended safety Evaluation Category (IIIa/IIIb) function. Note 1: The Licensee '(has/ The rationale presented by the has not) stated that failure of Licensee is not supported by the primary equipment.will not objective technical evidence. affect other safety-related equipment or cause an operator X Other (see page O ) to be misled. (See page' ) LICENSEE STATEMENT See page 3a of this checksheet. EVALUATION OF LICENSEE STATEMENT The Licensee states that the Tave RTDs are not required for DBE but are used only for outside containment main steam line break protection. Also, a review of the Licensee's submittal indicates that these are the only reactor coolant system RTDs for which SCEW sheets have been submitted. Reactor coolant system RTDs are required during initial phases of a design basis accident, during a cooldown to cold shutdown conditions, and during long-term cooling (under hot or cold conditions). Hot leg detectors aid in detennining reactor system subcooling and in providing indication of natural circulation. Cold leg instruments also provide indication of natural circulation, provide input to heat balance calculations, and provide direct indication of ECCS injection. During plant cooldown, these detectors are necessary to ensure that cooldown rates are not being exceeded. They are also necessary to ensure

NRC Contract N2. NRC-03-79-118 d Fr nklin

           . Research Ccnter                                                                                                             FRC Project N2. C5257          Pag 3 A Divesson of The Franklin Institute                                                                                                FRC Assignment No.13            4C 20th and Race Streets. Phila. Pa.19103 f215) 44810m                                                                                 FRC Task No. SII EQUIPMENT EMVIRONMENTAL QUALIFICATION REVIEW OF ECulPMENT ITEM NO. .ld.

SYSTEM CONSIDERATION REVIEW EVALUATION OF LICENSEE STATEMENT (Continued) that the long-tem cooling method is functioning properly. Reactor coolant system indication, including the Tave instruments, should be environmentally qualified for long-tenn post-accident operation. 1

4li000FrinklinR:se rchCent:r NRC Contract No. NRC-03-79-118 FRC Project No.C5257 Page A Division of The Frankhn Institute FRC Assignment No.13 5 20th and Race Streets. Phda. Pa. 19103 (215) 448-1000 FRC Task No.8# EQUIPMENT ENVIRONMENTAL QUAllFICATION REVIEW OF EQUIPMENT ITEM NO. /_f Checksheets f a_ h 6"/ have been removed due to the proprietary nature of information contained therein.-

l #h NRC Contract N2. NRC-03-79-118 P g2 l.bFrsnklin Rise rch Cant:r FRC Project N2.C5257 A Dwison of Thz Frinkhn Insntute FRC Assignment N2.13 lc 20th and Race Streets. Phda . Pa 19103 (215) 448-tooo FRC Task No. 5// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. / 7 EQUIPMENT ITEM NO. 19 LEVEL SWITCH LOCATED IN THE CONTAINMENI, ELEV. 228'0" MADISON MODE.L 5602 REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO.19 LICENSEE REFERENCE (S): NOT CITED FUNCTION (PLANT ID): CONTAINMENT SUMP WATER LEVEL MEASUREMENT (LS-1925A, B) LICENSEE SUBMITTAL: SCEW(S): 8 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (S:e Section 3 of this TER for Legend) RT, P, H, CS, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, A , Su System Consideration Review h, '.,, =w, G, = , 47 Equipment Environmental Qualification Review 0-, LL, 5-, Od, Se, Of, 53 , ;b, Si, Si Installed TMI Lessons Learned Implementation -, ', b Equipment Summary Maintenance and Replacement Schedule Summary 7a, 7L, 7w

4000u rrsnuiin arsenca cint:r NRC Contract N2. NRC-03-79-118 FRC Project N2. Cs2s7 Page A Divison of Tha Frinklin Instituti FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa 19103 (215) 448-1000 FRC Task No. 8N EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. I f

SUMMARY

OF LICENSEE RESPONSES 'IO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/imo av u) provided a response to the SER concerns. The Licensee (has/has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions.

                                                                                        ~

The Licensee has presented information which shows there are no outstanding qualification deficiencies. 1 The Licensee (has/h:2 n:ti proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment , Qualification testing of e uipment in progress - g Other ( F b o V (j {/ V 'f (/ The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) l The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW l - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend) I.a Qualified II.c Qualified Life Deficiency Q.b Modification] III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available l l

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

NRC Contract N3. NRC-03-79-118 pE,:nuiin a:.e. sea ccnier FRC proi.ct No.Csasy Page UDD A Division of The Franklin Instituti FRC AssignmentN .17 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-15 2 FRC Task No. d~/ I EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4 EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate X Adequate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Quzlified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate .. o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate

' Criteria Regarding Spray Satisfied Criteria Rega(ding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tast Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I)

DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification 1 II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III. as Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available - fd~~ (/c & /,) J Wy ah i

400hu Fr:nklin Research C:nter NRC Contract N3. NRC 03-79-118 FRC Project No. C5257 Page A Division of The Franklin Inuttute 30 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Assignment FRC Task No. N[:: 13# EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. g LICENSEE RESPONSE TO NRC SER Lefel Switch Madison 5602 1 R,T,QT,RT,P,H,

                                                                                                 ,CS,A,QM The items within Appendix B not fully covered by eith'er TER classification or SCEWS's are as follows:

Ecuioment Description Manufacturer Model No. Location Motor Operator Limitorque SMB -3 Transmitter containment Rosemount il53A . containment Level Switch Madison 5602 Silicon Rubber Tape containment 3M Scotch 70 containment The level switch reported is for containment sump level indication and has been superceded in place by two GEMS level transmittiers Model No. XM36495 as part of the DfI lessons learned action items. This system is currently reported in our response to the TMI Equipment requirement submitted in February, 1981. hO l

NRC Contract No, NRC-03-79-118 4UOOU Fr:nklin Research Center FRC Project No.C5257 Page A DMsion of The Frankhn Institute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. 5ll _ E2UIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. If 3.2.7 Level Switches As reported in CP&L's responses to NRC IE Bulletin 79-01 RA containment level switches (LS-1925A, LS-1925B) located within containment sump would be replaced with qualified equipment as the in-place equipment was never qualified. As supplied, the level switches are magnetic in operation and provided incremental one- (1) foot level data as water would rise in the sump. This equipment could operate completely submerged. A market search did not uncover any source of qualified equipment for replacement purposes. However, a parallel investigative effort by CP&L to meet the requirements of NRC NUREG 0578, TMI Short-Term Lessons Learned, ACRS2 Containment Water Level Indication, has concluded that there should be an analog level signal generated for combined sump and containment water level to aid in reporting and mitigating TMI type accident conditions-- if ever experienced. The current increnental level switches, Madison Model 5602 Switch Units with Type 316 Stainless Steel stem, 10 ft. 6 inches long, with eight (8) 316 Stainless Steel Floats and one (1) Dry Contact' Switch at each level, wired with 22AWG conductors with Silicone Rubber insulation, will remain in place. The. function of these switches will be assumed by the analog system. The schedule for completion of installation is January 1, 1981. CP&L will take no further action on these level switches in conjunction with NRC IE Bulletin 79-01B. 4.7 Level Switches Original plans for replace =ent of the nonqualfied containment su=p level switches with qualified equipment is no longer - considered necessary. The function of level determination is being assumed by a dual analog system provided in the TMI Short-Term Lessons Learned Program (Equipment will be GEMS Level Sensor - Transmitter XM36496, :C436495 and Receiver RE36562.) The existing system will be left in place. Check of E.I.-l procedure, Incident Involving Reactor Coolant System Depressuri-zation, does not reference use of this equipment; therefore, no changes are required in this procedure when switchover is accomplished. Additional action required - None. Gr1

es NRC Contract N2. NRC-03-79-118 P g2 LUUU Franklin Reserrch Cantir FRC Pr: Ject N2. C5257 A Dnnsion ollhe Franklin Institute FRC Asaignment No.13 lc 20th and Race Streets. Phila . Pa 19103 (215) 4481(XX) FRC Task No. 6// l 1 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2d EQUIPMENT ITEM NO. 20 (TMI ACTION PLAN ITEM II.D.3) ACCELEROMETER LOCATED IN THE CONTAINMENT ENDEVC0 MODEL 2273AM20 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 20 LICENSEE REFERENCE (S): 1596 FUNCTION (PLANT ID): NOT STATED (A, B, C) LICENSEE SUBMITTAL: SCEW(S): 2 0F 15 [15] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) R, T, QT, RT, P, H, CS, A, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not p i LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, au, L, 3d System Consideration Review ';, '. b , 00, '5,

                                                                                               -   ';, 40 Equipment Environmental Qualification Review                                    So, Tu, 5u, 55, ;=, ;Z, 5;, "., 31, ;j Installed TMI Lessons Learned Implementation                                    6a, tb Equipment Summary Maintenance and Replacement Schedule Summary                                     ea, iu, E

                                                                                                           /

NRC Contract Nr. NRC-03-79-118 00 Franklin R:seirch C nt:r FRC Project NO. C5257 Pag 3 A Divmon of The Frankhn Institute FRC Asalgnment No.13 lb 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. S/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 42 d St.MMARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. The Licensee (has/has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. I The Licensee (has/"- --t) proposed c.; :::::t' r: action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment- item. M C ::::t*"e action specified by the Licensee Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment y Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

 - CIRCLED ITEM ONLY:                   (See Section 3 of this TER for Legend)

I.o Qualified II.c Qualified Life Deficiency TI.b Modification} III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available

NRC Contract Na, NRC-03 79-118  ! 00 Fr:nklin Research Ccnter FRC Project No. C5257 Page A Dwtseon of The FrankhnInstnute FRC Assignment No.13 2 20th and Race Streets. Phila,. Pa. 19103 (215) 448 1000 FRC Task No. A/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. A l EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM l I DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen 3stablished Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Tdentify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification 1 II.a Equipment Qualification Not Established

• II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.b Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available THE LICENSEE HAS STATED THAT QUALIFICATION TESTING IS IN PROGRESS

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4 NRC Contract N3. NRC43-79118 FRC Project Ns.C5257 Pa08 UObU Fr:nklin R: search Centar A DMs6on of The Frankl6n Insmuti FRC Assignment N2.13 60 20th and Race Sweets. Ph61a.. Pa.19103 (215) 4481000 FRC Task No. TM EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J 8 INSTALLED TMI LESSONS LEARNED IMPLEMENTATION EQUIPMENT

SUMMARY

NRC requested an evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments required fo* TMI Lessons Learned Implementation. The objective is to evaluate qualification documentation of. equipment within the scope of IE Bulletin 79-01B, Supplement 3 (item 2), in accordance with criteria established-by the NRC (see Section 2 of this report) in a manner identical to the evaluation of all r.,cher safety-related electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with specific sections of NUREG-0737 which I have an instiallation implementation date of January 1,1981 (sections are identified below) . Where applicable, a review is to be performed on installed equipment with implementation dates after January 1, 1981 if adequately identified by the licensee,. This plant is a PWR j , BWR . The NSSS Vendor is Westinghouse (W) )(* , Babcox & Wilcox (B&W) , Combustion Engineering (CE) , General Electric (GE) . With respect to this equipment item, it is noted (applicable section checked): The Licensee does not provide adequate information with respect to identification of TMI Action Plan equipment installed as of 1/1/81. The Licensea has not provided the correlation of this equipment item with the specific sections of NUREG-0737. [The correlation is needed to ensure

 ,                    that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal blocks associated with the device also identified?]

l. l The Licensee has not provided the approximate installation date for the l TMI' Action Plan equipment items so that the appropriate qualification criteria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. The Licensee has provided a standard Owners' Group position with respect to a NUREG-0737 technical area. The Licensee has requested extensions of implementation dates. g The Licensee has stated that this equipment item is associated with the following section of NUREG-0737. (This list of applicable NUREG-0737 l sections has been identified by NRC as sections within the scope of this review) : II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment 1 II.D.3 ( ALL/1-1-81) Direct Indication of Relief and Safety Valve i Position

A% NRC Contract N 2. NRC-03-79-118 P gs LOOU Franklin Rese:rch Cent:r FRC Project N3. C5257 A Dwmon of The Frankhn Institute FRC Assignment No.13 lc 20th and Race Streets. Phila . Pa 19103 (215) 448-1000 FRC Task No. S/l , EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.M EQUIPMENT ITEM NO. 21 (TMI ACTION PLAN ITEM II.D.3) AMPLIFIER LOCATED IN THE CONTAINMENI UNHOLTZ-DICKIE MODEL 22CA2TR REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 21 LICENSEE REFERENCE (S): 1596 FUNCTION (PLANT ID): NOT STATED (A, B, C) LICENSEE SUBMITTAL: SCEW(S): 3 0F 15 [15] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) UNLY: (Sco Section 3 of this TER for Legend) R, T, QT, RT, P, H, CS, A, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Noy applicable NfhT 1$tM y LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, ?, 2d System Consideration Review - va, e, ,w, If, 4, if Equipment Environmental Qualification Review Go, L, 5;, 5d. 5-, Of,

                                                                                   % ch         ti, 53 Inatalled TMI Lessons Learned Implementation                                     6a, 66 Equipment Summary Maintenance and Replacement Schedule Summary                                     .22 , 7b, 7;

NRC Contract N 2. NRC-03-79-118 phrinklin UO0 Rrse:rch C nter FRC Project N;. C5257 Pag 3 A Division of The Frankhn Institute FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. 8// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4 /

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. The Licensee (has/has not) specifically stated that the equipment la qualified and/or will function when exposed to the applicable DBE ' environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. g The Licensee (has,S:; m) proposed a.h. action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment-item. 1 Cr:x;;i.; action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment X Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) l The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW l - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend) I.a Qualified II.c Qualified Life Deficiency II.b Modification] III.a Exempt II.a Quanfication Not Established III.b Not in Scope ! II.b Not Qualified IV Documentation Not Available l l

NRC Contred N3. NRC-03-79-118 4UQ06nnklin Research Canter FRC Project No.C5257 Pa08 A Divwon of The FranklinInsedute FRC Assignment No.13 2 20th and Race Sareets. Phila.. Pa. 19103 (215) 448 1000 FRCTask No. 8Il 4 EQUIPMENT ENVIRONMENTAL QUALIFICATON REVIEW OF EQUIPMENT ITEM NO. a./ EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adsquate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation _ Critcria Regarding Aging Simulation Satisfied (If Required) CritGria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Critaria Regarding Spray Satisfied Critoria Regarding Submergence Satisfied Critaria Regarding Radiation Satisfied Critaria Regarding Test Sequence Satisfied 4 Critoria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Critoria 3egarding Instrument Accuracy Satisfied T3st Duration Margin (1 hour + Function Time) Satisfied _

'   Critoria Regarding Margins Satisfied (NUREG-0588, Cat. I)

DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.c Equipment Qualified I.b Equipment Qualification Pending Modification Y II.c Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life

or Replacement Schedule Justified

. III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review 1 IV Documentation Not Made Available THE LICENSEE HAS STATED THAT QUALIFICATION TESTING IS IN PROGRESS

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(S) Values proposed by testing laboratory (AETL) within Qual. Test Procedure _548-8955 Rev. A 6 ( i) Qualification testing not yet completed

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NRC Contract N r. NRC-03-79-118 Pag] AUO0hrinklin R:seirch Center FRC Project N;.C5257 A Divmon of The FranklinInst+tuti FRC Assignment N2.13 60 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. 8"'h EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2.] INSTALLED TMI LESSONS LEARNED IMPLEMENTATION EQUIPMENT

SUMMARY

NRC requested an evaluation of the environmental qualification of safety-rolsted electrical equipment located in harsh environments required for TMI Le: sons Learned Implementation. The objective is to evaluate qualification documentation of equipment within the scope of IR Bulletin 79-OlB, Supplement 3 (item 2), 'in accordance with criteria established-by the NRC (see Section 2 of this report) in a manner identical to the evaluation of all other safety-rolsted electrical equipment. The scope of this review is limited to TMI ActiCn Plan equipment associated with specific sections of NUREG-0737 which h .va an instiallation implementation date of January 1,1981 (sections are id;ntifieu below) . Where applicable, a review is to be performed on installed equipment with implementation dates af ter January 1,1981 if adequately id;ntified by the licensee. Thic plant is a PWR N , BWR . . Th3 NSSS Vendor is Westinghouse (W) Y , Babcox & Wilcox (B&W) , Combustion Engineering (CE) , General Electric (GE) With respect to this equipment item, it is noted (applicable section checked): The Licensee does not provide adequate information with respect to identification of TMI Action Plan equipment installed as of 1/1/01. The Licensee has not provided the correlation of this equipment item with the specific sections of NUREG-0737. [The correlation is needed to ensure that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal blocks associated with the device also identified?] The Licensee has not provided the approximate installation date for the TMI' Action Plan equipment items so that the appropriate qualification criteria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. The Licensee has provided a standard Owners' Group position with respect to a NUREG-0737 technical area. The Licensee has requested extensions of implementation dates. The Licensee has stated that th'is equipment item is associated with the following section of NUREG-0737. (This list of applicable NUREG-0737 cections has been idantified by NRC as sections within the scopa of this review): II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment P II.D.3 (ALL/1-1-81) Direct Indication of Relief and Safety Valve Position

As NRC Contract N 2. NRC-03-79-118 P:ga b00ll Frank!;n Research Cent:r FRC Praject N2. C5257 A Dwisien of The Frankhn institute FRC Assignment No.13 lc 20th and Race Streers Phila.. Pa 19103(215) 448-1000 FRC Task No. S // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.M EQUIPMENT ITEM NO. 22 ELECTRIC MOTOR LOCATED IN THE REACTOR AUXILIARY BLDG. WESTINGHOUSE MODEL 506UPZ REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 22 LICENSEE REFERENCE (S): 606, 3184 FUNCTION (PLANT ID): DRIVES RHR PUMP - SIS (RHR-A, B) LICENSEE SUBMITTAL: SCEW(S): 13 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) h CS, S, (R), I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: ) Contents Checksheet Page No.

Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 ,

Licensee Response to NRC SER 3a, 3b, A , 5u System Consideration Review 4e, th, I;, If, 0;, T Equipment Environmental Qualification Review 5;, 55, :., 52, 5:, Sf, Eg, Sh, Si, Sj l l Installed TMI Lessons Learned Implementation Se, f5 Equipment Summary Maintenance and Replacement Schedule Summary 22, 75, 7c

e , i NRC Contract No. NRC-0349-118 , N nklin R:se:rch C nter FRC Project Nr. C5257 / ' / , age l A DMson of The Franklin insuture FRC Assignment No.13 ~ l h. ' ' l 20th and Race Streets. Phila . Pa 19103 (215) 44 & l000 FRC Task No. S // ' *

                                                                                                                                 ,-                  .                 l
                                                                                                              =:-           -          -
                                                                                                                                             -         ~.; ;;

EEUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EOU/PMENT ITEM NO..dd

                                                                                                                                                        ,n; l    

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CUP.CKED' ITEMS ARF APPLICAPLE: ,x [ Tne Licensee (has/':: rt) provided a response to the SFJ4 conceras.- -i / [ The Licensee (has/b-- -^6) specifically stated that the equipcont is: qualified and4pr will function when exposed to the applicable DBE ' environmental service conditions. ' The Licensee has presented information which shows there are no , outstanding qualification deficiencies. , The Licensee (has/has not) proposed a corrective action!for this equipment ~ .,,- item whose qualification has not been fully established.  ;' Justification for interim operation (has/has not) been provided by the': Licensee for this equipment item. , Corrective action specified by the Licensee:

                                                                                                                                                  )

Equipment replacement with qualified equipment Equipment modification l Equipment relocation above submergence level Relocate or shield equipment from radiation source , Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item , that can be construed as a basis for justification for interim . operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action . ) The Licensee states that the equipment item does not require qualification' cnd/or should be exempted from environmental qualification. DESIGNATION OF RE'SULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

   - CIRCLED ITEM ONLY:                  (See Section 3 of this TER for Legend)

I.c Qualified II.c Qualitted Life Deficiency ~ I.b Modification III.a Exempt Q Qualification Not Established III.b Not in Scope , II.b Not Qualified IV Documentation Not Avrilable ,

                                                                                                   . wm e

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 '                                                            '                  '                                                       ~
                                                                              .,           NRC Contract NO. NRC-03 79118
                             , Shr:rilin R: search Center                                                                           Page j              FRC Prolact No. CS257 f                   f     ' A Dwmon of1he Frwkhn lasutute .
                                                                                         , FRC Asaignment No.13                      2 g

L [ 20th and Rue S:rsos Phda.. Pa 19103 GIS) 443-1000 FRCTask No. I 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .s$id 3 f , EJUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: X = DEFICIENCY NRCREhUfREMENTS

   'I Documeat.ed Evidence of , Qualification Adequate                                                   1 Adequate Similatity Batween Equipment and Test Specimen Established                                 X e               i             Aglag Lbgradation Evaluated .Mequately L

i 4i.e1Ji d Lik a Replacement Schedule Established (If Required) X t Program Establisaed to Identify Aging Degradation X Criteria Regarding A: ling . Simulation Satisfied (If Required)

                            . Criteria Regarding Temparature/ Pressure Exposure:

l' o Peak Temperature 1 Adequate

                 /                     o Peak, Pressure Adequate o Duration Adequate o Required Profile. Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding' Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Tesa Failures or Severe Anomalies (If Any) Satisfied iCriteria RegardinW Functwnal Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hout t Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I)

DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a. Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established Y II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qua'. A; _ed Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification

     '                         111.0          Equipment Not in the Scope of the Qualification Review l                               IV             Documentation Not Made Available l

l i

        ,-c
   - -                I                                            .

i

   /                  I,1

A NRC Contract No. NRC-03-79-118 UO0hr:nklin Research Center FRC Project No. C5257 Page A Division of The Frankhn Inanute FRC Asalgnment No.13 3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448-tmo FRC Task No. 6/l EIEUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .s?.32-LICENSEE RESPONSE TO NRC SER 4.2 Youiement Requiring Additional Information and/or Corrective Action (Accendix 3) gg The tak of matter list equipment was placed in this cr.: agory and our review of deficiencies is based upon the follot<ing: Deletion of deficient listed' equipment due to replaenent programs carried out and reported in our 90-day, Revision 3 tesponse dated February 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                     - Docket No. 50-261; Plant: L 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD revievirg personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11,

• 1980:

Equipment Description Manufacturer Model No. I.ocation

1. pump motor Westinghouse 506UPZ outside containment A. Pump Motor- Westinghouse 506UPI 2 R,T,QT,RT,P,H,

        ,,                                                                                      A.H b

Location (1) Containment Building Location (2) Auxiliarj Suilding A Items reported as qualified within NRC Region II revised TER, dated 11/7/80.* O l

NRC Contract No. NRC-03 79-118 4000U Fr:nidin Research Center FRC Project No.C5257 Page A DMs6on of The Frankhn Instuute FRC Assignment No.13 3h 20eh and Rue Streets. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. S/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITE,M NO. eds?- 3.2.8 Motors {( Within containment at H. B. Robinson included in the equipment list for the report is one (1) motor type. This is a Westinghouse Type 685.5-5 used with the containment fans. There are four (4) f ans mounted in containment designated HVH-1 through HTd-4. Qualification testing on a complete motor / fan' assembly and on individual motor elements has been perfor=ed by Westinghouse. Results are published within WCAP-9003, Fan Cooler Motor Unit Test, 1969; WCAP-7829, Fan Cooler Motor Unit Test, 1972. WCAP-9003 testing included: thermal preaging to an equivalent of seven (7) years a3 maximum pressure of 95 psia, a maximum temperature of 315 F, and use of borated spray for thirty-five (35) hours. WCAP-7829 testing8 included: total irradiation of equipment / components to 2 x 10 RADS, preaging to a 40-year life expectancy. Evaluation of the test reports concludes that the H. B, Robinson accident para =eters are covered by the test envelopes and parameters perfor=ed on the similar Westinghouse motor / components subjected to qualification testing. Therefore, the containment fan motors at H. B. Robinson are considered qualified. Outside of contain=ent, the RHR pump motors are in use during long-term mitigation of LOCA conditicas. The only accident para =eters experienced by these pumps /cotors is radiation. The most susceptible elements / components of the motors are covered by the testing reported within WCAP-7829. Since the RHR pump motors are of a similar type and motor windings are Ther=alastic Epoxy insulated, it is concluded that the RHR pump motor is qualified for the service intended and the environment experienced during post LOCA. Data supporting the Westinghouse testing reported within the stated WCAPs has been requested from Westinghouse and will be available for review upon receipt.

Ar NRC Contract No. NRC-03 79-118 Pag 3 6000 Fr:nkhn R:seirch C2nter FRC Project N2.C5257 A Dven of The Frankhn insneuse FRC Assigrmont No.13 5f 20th and Race Streets. Phda . Pa. 19103(215) 448 1000 FRC Task No. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 22' NOTES: o Although WCAP-7829 does encompass radiation testine to 2.0 EORran the report does not specifically identifv rhe mnene en land an14ea materials. The licensee should identifv the mnearin1= naad in che installed motor and verify that these itama are ann 14fied en tha environmental service conditions to which they nya avnnead o The licensee should provide evidence that the eraman naad in cha bearing lubrication system is the same as that uned in the ennead motor or provide cualification information to enenh14=h nimilarity of lubricatine ability afear avnnnnen en the vndintion service environment. o The licensee should establich a replacement schedule for the arense l and bearings in addition to an analysis extending the cualified life l of the Thermolastic Epoxy Stator Insulation bevond the 7 years of j continuous duty to an actual in olant service life. O c-e e -8 5 8 7 c o n cern s +L_me4L 4feau . s o A. 4e d 0T U UQ Vo cton.s ece bM ile a s tu . u i o 1+/. M A 4-v AIdm v r~ i ~ id . i l t l

. A, NRC Contract N . NRC-03-79-118 FRC Project Ns. C5257 P g3 LOOU Frtnklin R: search Centir A Division of The Frankhn Institute FRC Assignment No.13 lc 20th and Race Streets. Phila . Pa 19103 (215) 448 1000 FRC Task No. 5// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.4.3. EQUIPMENT ITEM NO. 23 ELECTRIC MOTOR LOCATED IN THE CONTAINMENI, ELEV. 275'0" WESTINGHOUSE MODEL 685.5S REQUIRED OPERATING TIME: 3 HOURS TER CHECKSHEET No. 23 LICENSEE REFERENCE (S): 639, 640 FUNCTION (PLANT ID): DRIVES CONTAINMENT FAN COOLER (HVH-1, -2, -3, -4) LICENSEE SUBMITTAL: SCEW(S): 17 0F 25 (20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY (See Section 3 of this TER for Legend) T, (/Y, RT, P, H, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: - Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, 20, 2 0-- System Consideration Review 42, th, t;, "J, 4=, ei Equipment Environmental qualification Review Sa, 5b, Sc, 5d, Se, 5f, Sg, Oh, 31, Sj Installed TMI Lessons Learned Implementation -6a,- e Equipment Summary Maintenance and Replacement Schedule Summary -7. , 7 L , 76

NRC Contract No. NRC-03-79-118 00 Fr:nklin R: search Ccnter FRC Project N2. C5257 Page A Dwmon of The Frankhn Instavie FRC Asaignment No.13 lb 20th and Race Streets. Phda.. Pa. 19103(215) 448 1000 FRC Task No. 8 ll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d ) SUMARY OF LICENSEE RESPONSES 'IO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: g Tne Licensee (has/M ..M provided a response to the SER concerns. f The Licensee (has/t... ws) specifica31y stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental cervice conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. _ ,The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment-item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATMN CATEGORY BASED ON REVIEW

     - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.c Qualified II.c Qualified Life Deficiency I,b Modification III.a Exempt Q Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available j

NRC Contract NO. NRC-03-79-118

@O hr:nk!!n R: search Center U                                                        FRC Project No.C5257                      Page A Divmon of The FrankhnInstitute                     FRC Assignment No.13                       2 20th and Race Streets. Phde.. Pa 19103(215) 448-1000 FRC Task No. EII EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. sd3 EQUIPMENT ENVIRONMENTAL QUALIFICATION 

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate X Adequate Similarity Between Equipment and Test Specimen Established X Aging Degradation Evaluated Adequately X Qualified Life or Replacement Schedule Established (If Required) X Program Established to Identify Aging Degradation X Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteris Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I l I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established X II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life l or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available 1

A NRC Contract No. NRC-03-79-118 ll00fFr nklinResearchCenter FRC Project No. C5257 Pag 3 A Division of The Frankhn Instnute FRC Assignmentpo.13 30 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1000 FRC Task No. c II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. E.3 LICENSEE RESPONSE TO NRC SER Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: gy Eculoment Descriotion Manufacturer Model No. Location I ;"-- reter Sn' N ^"--*>-

                                                            "c:~'-f-"re crt *         :nt
              ? reter :;:::trr                               _ irit:r;r             ~" 0 0           ::xt:i_r ;t S     --rer      ; r rer                      '_ini:::qu:
                                                                                     ~" 0 0          __:;id:

cent in :nt-

                . aetor ;gr;ter                             '.isi t:r;;;            ~" - 1           cc r*>:
                                                                                                     - ,s o , , e ,, . .. e
             - 5. f1= tr ce-itter                             cher ! ?crt er      !**?^od         ^ " , .<,...e
                                                                                    =a n y_u n n     ,,,,

5. ; :::r: tr ::ritt:r ?i9 E ' rt:5 50E? i'" I ^"*^

              ..                                                                    ' 0 7_'.         ::xtrir ent

7. fan motor Westinghouse 685.5-S containment 4.2 Youiement Recuiring Additional Information and/or Corrective Action (Accendix B)

The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evaluation of CF&L's updated submittals by NRC Region II, l Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment II3 79-013. Technical Evaluation Report

                        - Docket No. 50-261; Plant:                   H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

l Telecons with N"C, Bethesda, MD reviewing personnel July 29, 1981, et al.

3. Fan Motor Westinghouse 685.5-5 1 R,CS,A 3

Items reported as qualified in part, with additional testing underway to establish overall equipment qualification, within NRC Region II revised TIR, dated 11/7/30.

N NRC Contract No, NRC-03-79-118 FRC Project No. C5257 Page 00J Ftnklin Research Center A D6viWon of The Franklin Institute FRC Asaignment No.13 3b 20th and Race Streets Phda.. Pa. 19103 (215) 448-1 2 0 FRC Task No. 8 /l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2.3 3.2.8 Motors gG Within containment at H. B. Robinson included in the equipment list for the report is one (1) motor type. This is a Westinghouse Type 685.5-S used with the contain=ent fans. There are four (4) f ans mounted in containment designated HVH-1 through HVH-4. Qualification testing on a complete cotor/ fan assembly and on. individual motor elements has been performed by Westinghouse. Results are published within WCAP-9003, Fan Cooler Motor Unit Test, 1969; WCAP-7829, Fan Cooler Motor Unit Test, 1972. WCAP-9003 testing included: thermal preaging to an equivalent of seven (7) years 3 a maximum pressure of 95 psia, a maximum temperature of 315 F, and use of borated spray for thirty-five (35) hours. WCAP-7829 testing neluded. total irradiation of 8 ecuipment/ components to 2 x 10 RADS, preaging to a 40-year life expectancy. Evaluation of the test reports concludes that the H. B, Robinson accident parameters are covered by the test envelopes and parameters performed on the similar Westinghouse motor / components subjected to qualification testing. Therefore, the containment fan motors at H. 3. Robinson are considered qualified. Outside of containment, the RHR pump motors are in use during long-term mitigation of LOCA conditions. The only accident parameters experienced by these pu=ps/ motors is radiation. The most susceptible elements / components of the motors are covered by the testing reported within WCAP-7829. Since the RHR pump motors are of a similar type and motor windings are Ther=alastic Epoxy insulated, it is concluded that the RHR pump motor is qualified for the service intended and the environment experienced during post LOCA. Data supporting the Westinghouse testing reported within the stated WCAPs has been requested from Westinghouse and will be available for review upon receipt.

NRC Contract No. NRC-03-79-118 100 Fr:nklin R:sench C:nt:r FRC Project N2.C5257 P g3 A Divts6on of The Frankhn Institute FRC Asaignment No.13 5 20th and Race Streets. Phda . Pa. 19103(215) 448-1000 FRC Task No. f// EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.R Che cksheets [a, fR have been removed due to the I proprietary nature of information contained therein.- l l l i

A NRC Contract No. NRC-03-79-118 LNNnklin Rssetrch Cent:r FRC Project Ns. C5257 P g) A Dmuon of The Frankl.n institute FRC Assignment No.13 la 20th and Race Streets. Phda . Pa 19103 (215) 448-1000 FRCTask No. S// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.M EQUIPMENT ITEM NO. 24 ELECTRICAL PENETRATION LOCATED IN THE CONTAINHENT, ELEV. 234'-246' CROUSE-HINDS MODELS 1.2.2 (745), 1.2.2 (747), 1.2.4 (749), 1.2.5 (751) REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 24 LICENSEE REFEREtCE(S): 25, 2096 FUtETION (PLANT ID): ELECTRICAL DISTRIBUTION (B-1, -2, -5, -9 ; C-l', -2, -3,

                                       -4, -6, -8, -9; D-1, -2, -3, -5, -8, -9)

LICENSEE SUBMITTAL: SCEW(S): 18 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITD4(S) ONLY: (S o Section 3 of this TER for Legend) T, P, H, S, (R) , M, I, QM, RPN, EXN, SEN, QI, RPS, None, l Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Pace No. Equipment Item la

Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Lic3nsee Response to NRC SER 3a, 3b, 3c, 3d, Je System Consideration Review #= ^ M M, I;, I l Equipment Environmental Qualification Review -k r 55, 0;, Ed, 50, 5f, l 50, 5., ei, n Installed TMI Lessons Learned Implementation -0;, !b Equipment Summary Maintenance and Replacement Schedule Summary 7a, 7',; 70

NRC Contract N2. NRC-03-79-118 4000U Frznkhn R2se:rch Center FRC Project N3.C5257 Pag 3 A DMuon of The Frankhn Institute FRC Assignment No.13 lb 20th and Race Streets. Phda.. Pa 19103 (215) 448 1000 FRC Task No. -6I( EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 4  ; l

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: I Tne Licensee (has/t;; -^M provided a response to the SER concerns. [ The Licensee (has/h;; n;O specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE ~ environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source l Verify qualification by additional (testing / analysis) l Equipment relocation to a mild environment Qualification testing of equipment in progress l Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification l and/or should be exempted from environmental qualification. l DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

 - CIRCLED ITEM ONLY:                   (See Section 3 of this TER for Legend)

I I.c Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt l II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available l

NRC Contract NO. NRC-03 79-118 4{l00d Fr:nklin Rese:rch Ccnter FRC Project N3. C5257 Pace A DMsum of The Frankhn Institute FRC Assignment No.13 2 20th and Race Streets. Phita.. Pa. 19103 (215) 448-1000 FRC Task No. 8H EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.d EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately , Qualified Life or Replacement Schedule Established (If Requitted) Program Established to Identify Ming Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.b Equipment Not in the Scope of the CJalification Review IV Documentation Not Made Available 1

TEST REPORTS ON VARIOUS WESTINGHOUSE AND CROUSE-HINDS ELECTRICAL PENETRATIONS HAVE BEEN PREVIOUSLY REVIEWED. HOWEVER, SINCE DOCUMENTS REFERENCED BY THE LICENSEE AS 1, 2, 3, and 4 WERE NOT PROVIDED, QUALIFICATION STATUS OF THE ROBINSON UNIT 2 PLANT CANNOT BE DETERMINED.

NRC Contract No. NRC 03-79-118

  @O0hr:nklin R: search Center U                                                          FRC Project No.C5257                    Pago A Dwwon of The Frankhn Instaute                        FRC Assignment No.13                     3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. 8/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. M LICENSEE RESPONSE TO NRC SER 4.2 Youtoment Recuiring Additional Information and/or Corrective Action (Accendix 3)

The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following:

               -     Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.
               -     Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment II3 79-013. Technical Evaluation Report
                     - Docket No. 50-261; Plant:                H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. ' B* Eiectrical 1.2.2 (745) 1 R,QT,RT,CS,A Penetration Crouse-Hinds B. Electrical 1.2.2 (747) 1 R,QT,RT,CS,A Penetration Creuse-Hinds 3* Electrical 1.2.4 (749) 1 R,QT,RT,CS,A Penetration Crouse-Hinds B* Electrical 1.2.5 (751) 1 R,QT,RT,CS,A Penetration Crouse-Hinds i 37tems reported as qualified in part, with additional testing underway to establish overall equip =ent qualification, within NRC Region II revised TER, dated 11/7/80.

NRC Contract No. NRC-03 79-118 00 Franklin Research Center FRC Project No.C5257 Page A Dwon o(The Frankun institute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. 5 ll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J V 3.2 Electrical Equipment Qualification Evaluation 3.2.1 Electrical Penetrations and Connectors {j The H. B. Robinson Nuclear Power Plant electrical penetrations are cartridge types with provisions for continuous pressuri-zation. They were manufactured by Crouse-Hinds Company (Syracuse, N. Y.) to a Westinghouse design and specification CPL-R2-E3. Location within containment forms a grid pattern extending from elevation 234 feet to 246 feet. This places the penetrations above the established containment flood level of 231.2 feet. The electrical penetrations utilized by iden-tified safety class electrical equipment are designated: Low Voltage (600V) 500 MCM, Low voltage (600V) 3/C 19/#22, Low Voltage Control and Power (600V) 2/C #16, 3/C #16, and Instrumentation (600V) 2/C #16, 4/C #16 shielded. These types consist of a

+              mixture of one , two- and three-conductor cable interfaces and appropriate shields. Individual conductors are carried through the penetration and end in either a 60-inch or 72-inch pigtail.

2/C #16 and 3/C #16 pigtails are grouped and attached to electrical connectors (Crouse-Hinds model number RPC-317-160-SOIN/S08N) to provide the appropriate cable match. The connectors are located in cable trays and lie in the horizontal plane. The cable tray runs are located essentially on the outside diameter of the polar crane shield wall to route cable to the respective instrumentation or control equipment. The electrical penetration material which is located within containment and exposed to accident environment conditions consists of stainless steel (container) ceramic plate (con-ductor spacer) PVC and Kerite formula (conductor insulation) and aluminum (electrical connectors). By specification each penetration type was designed to perform under the LOCA environmental conditions of pressure and te=perature depicted within the H. B. Robinson FSAR (shown as Figure 3.1.1 and 3.1.2 in this report). Test information is recorded in References 3 and 4.

NRC Contract No NRC 03 79-118 00 Fr:nklin Research Center Page FRC Pro}ect No.C5257 A Divson of The Frankhn Institute FRC Assignment No.13 3c 20th and Race Streets, Phila., Pa. 19103(215 448-tmo FRC Task No. 8lI EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d The CP&L Brunswick Nuclear Power Plant uses Westinghouse dssigned and fabricated electrical penetrations which are similar to those in use at H. B, Robinson. Both are cartridge type with stainless steel sleeves and both have potting compound ccals for the internal connections of the feed-through solid copper conductors. Brunswick penetrations utilize heat-shrink tubing for small conductors internal insulation spliced to Okonite jacketed cables foming pigtails for field cable R2 hookup. H. B. Robinson penetrations use silicone rubber internal insulation spliced with heat-shrink tubing to two (2) types of jacketed insulation cables (PVC and Kerite) foming pigtails for field cable hookup. Both use a ceramic seal to cncapsulate pigtail entry and provide an impervious shield . with the cartridge sleeve. A greater degree of testing was parformed on Brunswick type penetrations with results found in Rsference 43. Briefly su=marized: Themal cycling - 20 C to 135 C (5 cycles) Pre-aging - 524 hrs. g 70 C (40 years) 1 Radiation - 2.13 x 10 RAD Steam Test - Te=perature, Pressure, Humidity and Spray (per report) Due to the dual nature of the electrical penetrations, one side in contain=ent the other outside, mock-up of only the in-containment area was required for testing purposes. The test data recorded and referenced above should validate qualification of the cartridge portion of the H, B. Robinson electrical ptnetrations. Tha electrical connectors (Crouse-Hinds Model Number ((RPC. 317-160-50lN/S08N)) used'with the penetrations consist of an extruded aluminum shell with a hard anodized finish. The connector pins / sockets are silver-plated copper. The insert material is mineral filled diallyl phthalate with a thin wafer (R1 of silicone rubber provided for sealing purposes. Mineralfilleddialgylphthgatecanwithstandradiation lRI exposurebetgn10 degradation. and 10 RADS with little or no pemanent The silicone rubber seal wafer is positioned batween two plugs of diallyl phthalate and will not be significantly affected by irradiation. The connector proper will not be affected by nor=al plant life operation of forty (40) years or tha added accident radiation dosage as presented in Table 1.3.3.

6000IFr:nklin Reseych C:nter NRC Contract No, NRC-03-79-118 Page FRC Project ND.C5257 A Dtw;zn of The Franklin Institute FRC Assignment N ?.13 3d 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. OI EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. g l l The aluminum shell is comprised of 6061 alloy which contains (%): .25 copper, .6 silicon, 1.0 magnesium and .25 chromium. A Martin hard-coat anodized finish is applied to a depth of 1.7-2.0thousangths. The alloy used experiences a weight loss of 932 mg/dm for the first day and an average of 370 mg/dm 2 per day thereafter when completely i=mergedg a NaOH adjusted boric acid solution (pH-9) heated to 200 F. As the shell is anodized its corrosion resistance is improved. Additionally, the connectors will not be completely immersed in boric acid solution under spray conditions, nor will the high temperature be maintained for a thirty- (30) day period. Therefore, the worst case of loss of mass (.8 ounce per square decimeter af ter 30 days) will net be realized. Sufficient shell material vill remain to pr" serve connector integrity. (2)See Appendix C to this report for reference information. (3)WCAP 7153 Investigation of Chemical Additives for Reactor Containment Sprays. (Reference Table 8 and Figure 9.) . As reported by Crouse-Hinds, the anodized finish provides protection sufficient to enable specifying connector to be corrosion resistant to salt spray for 300 days (in tests per l MIL C-3015D and MIL-E-4970A). Per manufacturer's installation instructions, connector will provide watertight seal and will i ' exclude water by hose spray or stream. During refueling (August-October, 1980), all connectors in containment were checked and tightened to provide watertight fit. RZ A periodic check of connector clamp and shell cover screw l ' tightness will be established and performed to assure connectors will function for the LOCA prescribed operation time of the i penetrations (see Table 1.3.3) . As the clamp seal was able to maintain connector operability after a three-hundred (300) day salt spray test per stated MIL SPECS, it is concluded that properly maintained clamp seals will provide chemical spray protection for the required operational ti=es of electrical penetration day). connector circuits (thirty (30) minutes to one (1) l O I l

NRC Contract No. NRC 03 79-118 Page ehr:nklin UO0 Research Center FRC Project No.C5257 A DMs6on of The Frenkhn Instnute FRC Assignment No.13 3e 20th and Race Streets. Phila,. Pa, 19103 (215) 448 1000 FRC Task No. 8U EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .,2_,V No significant degradation due to thermal aging will be experienced by the connector during operation plant life due tomaterialsusedindesignandforfabrication. The connector

    .dssign temperature range is -80 F to 275 F and is sufficient to meet the operating and LOCA temperature range establisbed for H. B. Robinson.

The electrical penetrations utilize a combination of five- (5) and six- (6) foot lengths of single or multiconductor cable to connect the penetration feed-through conductors to the field (Al cable inside and outside containment. These " pigtail" cable ware installed by the manufacturer and sleeved at the penetration end with heat-shrink tubing. For selective conductors, connectors vsre installed while the majority of pigtail cables required butt-style splicing for field cable connection. Tha cabling used for pigtails was provided by CP&L/Ebasco . specification / purchase and shipped to Crouse-Hinds Company for fabrication use. For the Low Voltage Power, (600V) electrical pcnetrations, 500 MCM Kerite cable with HI TEMP conductor insulation was provided (see Section 3.2.4 for qualification cvaluation). For Low Voltage Control and Power (600V) electrical pinetrations, 3/C #16 and 2/C #16 Kerite cable with FR conductor inculation was provided (see Section 3.2.4 for qualification l cvaluation). For Instrumentation (600V) electrical penetrations 2/C #16 (shielded) and 4/C #16 (shielded), Continental Wire AI and Cable Company cable with PVC conductor insulation was ! provided. No qualification data is available for this cable. l CP&L has initiated a qualification test program to determine l tha ability of this cable to meet IEEE 323-1974 requirements

using FSAR established accident parameters. Spare pigtails i #ill be used and cable splices per Section 3.2.5 will be utilized to =aintain plant configuration during tests. Wyle Laboratories will perform the tests per Qualification Plan 543/4464/ES dated July 10, 1980. Testing and reporting will require thirty-five (35) weeks-af ter Receipt of Order. Major O time factor will be thermal aging to achieve forty- (40) years' operating life before LOCA testing can be performed.

After review of results, a report will be sent to NRC detailing any action by CP&L dictated by these tests. Thsse PVC insulated pigtails are used for instrumentation or within circuits which must. perform their functions after short elapsed time periods; therefore, their long-term operability I problems should not affect plant response to accident conditions. Rasults of the qualification test program will determine the lM ulti= ate disposition of these pigtails. If replacement is required, a plan and schedule for accomplishment will be included in the report already stated above. (I d '-'

NRC Contract N o. NRC-03-79-118 A[r$nklin dIlf Rrseuch Csnta FRC Project N3. C5257 P;g] A Dmuon of The Frankhn Institute FRC Assignment No.13 lc 20th and Race Streets. Phila . Pa 19103(215) 448-1000 FRC Task No. 6/l-EQUIPMENT ENVIRONMENTAL QUAllFICATION REVIEW OF EQUIPMENT ITEM NO. 6 1 EQUIPMENT ITEM NO. 25 j ELECTRICAL CABLE LOCATED IN THE CONTAINMENT ' CONTINENTAL WIRE AND CABLE MODEL CC2115 REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 25 LICENSEE REFERENCE (S): 2818 FUNCTION (PLANT ID): INSTRUMENTATION CABLE LICENSEE SUBMITTAL: SCEW(S): 21 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY (See Section 3 of this TER for Legend) T, W, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, 3b, A , ;d System Consideration Review P '5 '. T Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, 5f, Sg, 6h, 51, 4t Installed TMI Lessons Learned Implementation Sc , O Equipment Summary Maintenance ana Replacement Schedule Summary 7;, 7b, "';

'     A                                                          NRC Contract Nr. NRC-03 79118 Pa08 UO0hr:nkhn R:se:rch Center                                FRC Project N:. C5257 A Divmon of The Frankhn Institute                      FRC Assignment 30.13                              lb 20th and Race Streets. Phila.. Pa 19103(215) 448-1000  FRC Task No. 6 Il EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: 1 Tne Licensee (has/t ..wi.) provided a response to the SER concerns. 4 The Licensee (has/h : =t) specifically stated that the equipment is qualified andNr will function when exposed to the applicable DBE e:nvironmental service conditions. The Licensee has presented information which shows there are no cutstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: . Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Ralocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment - Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. l The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective , action .) The Licensee states that the equipment item does not require qualification

cnd/or should be exempted from environmental qualification.

DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW ! - CIRCLED ITEN ONLY: (See Section 3 of this TER for Legend) l 1.a Qualified II.c Qualified Life Deficiency I.b Modification III.a Exempt III.a Qualification Not Established) III.b Not in Scope II.b Not Qualified IV Documentation Not Available l \

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

NRC Contract N3. NRC-03-79-118 LO0hr nklin R: search C:nter FRC Project No. C5257 Page A Division of The Frankhn Institute FRC Assignment No.13 2 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. -6 I I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.a2.f EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately 1 Qualified Life or Replacement Schedule Established (If Required) 1 Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure. o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate 1 o Required Profile Enveloped Adequately 1 o Steam Exposure (If Required) Adequate , Criteria Regarding Spray Satisfied X Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalics (If Any) Satisfied Criteria Regarding Functional Testing Satisfied _ Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified j I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established X II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life 1 or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review

• IV Documentation Not Made Available

I 4 NRC Contract No. NRC-03 79-118 Pag]

l}00U Fr:nklin Research Center FRC Project No. C5257 A DMoon of The Frankhn Inmuuse FRC Assignment N1.13 3a 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. S(! _ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. s*LC LICENSEE RESPONSE TO NRC SER 4.2 Ecuipment Recuirinct Additional Information and/or Corrective Action (Apeendix B) Q ' The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the following:

                 -        Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981.
                  -       Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report
                          - Docket No. 50-261; Plant: H. 3. Robinson 2, dated November 6,1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Equiement Descriotion Manufacturer Model No. Location 1 pu-- rrter ":::in;;h u:: 505"??  ::::id:

trin.:nt 3 =^ter per:ter iiriter;n: " 0 0  ::nt i- :nt l ' --ter perrter ' ini::r quc M -00 :_:;il; eenc41 ament.

reter :;:::::: 11rit: ::: " - ! crt:1!:

nt inr:r!

5. fic tr:n::it::: ?ich;r i ?::::: 10" 2 ': " 5  ::::id:

noni,os -,,.,,,.m. 5 pr :: re tren:ritt:r ?ich:r i ?::::: 5 0 E? i:1  ::t:1!

                                                                              ' ' C7_'.              en!:fr r-t f r- -- t e r                       ":: tin @::::            555 5-5            ::rtrinc:nt

8. cable Continental Wire CC2115 contain=ent

                                                        & Cable A. Cable                               Continental Wire
                                             & Cable                 CC2115                   1         R,RT,P,H,CS,A AIte=s          reported as qualified within NRC Region II revised TER, dated 11/7/80.

NRC Contract No, NRC-03-79-118 l Pag] AUO0hr:nklin Research Center FRC Project No.C5257 A Division of The Franklin Institute FRC Assignment No.13 3b 20th and Race Streets. Ph61a.. Pa.19103 (215) 448-1000 FRC Task No. A Jl EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. M I 3.2.4 Electrical Cable The electrical equip =ent in containment and reported within , the equipment list of this report is connected by either l single conductors or multiconductor cables. These cables run via cable trays and conduit from the electrical penetrations to the equipment. Connections to the electrical penetrations are made by individual or grouped cable splices, or by elec-trical connectors. At the equipment end, formal component terminals with overall tape or crimped terminals with overall tape are used for connection. The connectors used (Crouse-Hinds Model No. RPC-ll7-150-POIN/PO8N) were supplied with the electrical penetrations and mounted on the matching cable during construction. For details concerning qualification of this connector, see Section 3.2.1. For details concerning cable splices and terminals see Section 3.2.5. For instrumentation within containment, a silicon rubber conductor insulation with glass binder, an untinned bare copper drain wire and an overall silicon rubber jacket cable is used. The manufacturer, Continental Wire and Cable Cocpany, used their formulated insulation type CC-2115. This formu-lation has been tested by the Franklin Institute Research Laboratories under Continental Wire and Cable Company instruc-tion. Final Report F-C2935 dated, October 1970 with addendum dated November 1970, details the testing specifics which included a preconditioning (aging) period of six (6) hourg at 151 F, and a subsequent test achieved exposures of 1 x 10 RADS. Also included was a chemical spray for one hundred and twenty (120) hours. The combined data for this cable insu-lation material indicates there should be no problems asso- , ciated with LOCA pressure, temperature, humidity, spray, or l radiation. At this time aging is the only' unknown variable. Basically, silicon rubber cable insulation is designed and recoc= ended for high temperature applications. CP&L has no plans to conduct separate testing to further qualify this cable. {/T] 1 1

NRC Contract No. NRC-03 79-118 phrinklin dO0 R:se:rch Center FRC Project No. C5257 Pag 3 A DMson of The Frankhn Institute FRC Assignment No.13 5 20th and Race Streets. Phita.. Pa. 19103 (215) 448-tm0 FRC Task No. .O/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.d5 ChecksheetCh&dgi have been removed due to the F proprietary nature of information contained therein.. l t l l

/% .                                                       NRC Contract N . NRC-03-79-118 LO0IFhinklin Rese:rch Centu                               FRC Project N;. C5257                    P:g a A Dwon of The Frankhn Instnute                        FRC Assignment No.13                      lc 20th and Race Streets. Phila.. Pa 19103 (215) 448 tm  FRC Task iJo. All EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.M EQUIPMENT ITEM NO. 26 ELECTRICAL CABLE LOCATED IN THE CONTAINMENT KERITE MODEL HIGH TEMPERATURE, FIRE RESISTANT REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 26 LICENSEE REFERENCE (S): 27, 4281, 4282 FUNCTION (PLANT ID):                CONTROL AND LOW POWER CABLE LICENSEE SUBMITTAL:                SCEW(S):        22 OF 25 [20]

DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY (S30 Section 3 of this TER for Legend) T, QT, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not otated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Sum: nary Forms 2 Lic:;nsee Response to NRC SER 3a, 3b, 3c, 3d

                                                                              **  2"   '"  , fr. S Syctem Consideration Review Equipment Environmental Qualification Review                                  Sa, Sb, Sc, 5d, Se, 5f, M , 55, Si, 6i y g

In*.,talled TMI Lessons Learned Implementation 5;, 05 Equipment Summary Maintenance and Replacement Schedule Summary 72, 75, 7;

i ,

&                                                        NRC Contract N 2. NRC-03-79-118                   '

000br nklinR:searchCcnter FRC Project NO. C5257 Page i A C: vision of The Franklin Instrute FRC Assignment No.13 lb I 20th and Race Streets. Phda. Pa 19103 (215) 448-10m FRC Task No. El I EQUIPMENT ENVI.90NMENTAL QUALIFICATION R*. VIEW OF EQUIPMENT ITEM NO. .n&,G SUeptARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: 1 Tne Licensee (has/h -- -^ t ' provided a response to the SER concerns. 1 The Licensee (has/h-- :tk specifically stated that the equipment is - qualified and)%( will function when exposed to the applicable DBE environmental service conditions. g The Licensee has presented information which shows there are no-outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not bee.1 fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by tha Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment' item that can be construed as a basis for justification for interim operation. " ' The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action *

                                                                                                .)

The Licensee states that the equipment item does not require qualification and/or should be exempted from enviroranental qualification. s DESIGNATION OF RESULTANT NRC QUALIFICATICU EV1.LUATION CATEGORY bSSED ON REVIEW

- CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

D Qualified _] II.c Dalified Life Deficiency I.b Modification 'III.a Exempt II.a Qualification Not Established III.b Not in Scope s II.b Not Qualified IV Documentation Not Available

As u00hnk!!n Research C:nter NRC Contract NO. NRC 03 79-118 FRC Project No.CS257 Page A Deion of The henkhn Insntute FRC Assignment No.13 2 20th and Race Streets. Phila.. Pe 19103 (215) M1000 ffl0TaskNo. $'/f EQUIPMENT ENVIRONMENTAL QUAL!FICATION REVIEW OF EQUIPMENT ITEM NO. 2 2 f, EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately Qunlified Life or Replacement Schedule Established (If Required) Program Established t'o Identify Aging Degradation Critcria Pegarding Aging Sinulation Satisfied (If Required) Critoria Regarding Temperatura/PressJte Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate . o Required Profile Enveloped Maquately o Steam Exposure (If Required) Adequate CritGria Regarding Spray Satisfied Critsria Regarding Submergence Satisfied . Crit 3ria Regarding Radiation Satisfled Crit 0ria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or; Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Critcria Regarding Instrument Accuracy Satisfied TGct Duration Margin (1 hour + Function Time) Satisfied _ Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC' QUALIFICATION CATEGORY X = CATEGORY l I.s Equipment Qualified y X I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established j II.b Equipment Not Qualified II.c Equipment Satisfies All Requirementis Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available

                  &                           f VW L.

if* l l NRC Contract No. NRC-03 79-118 . 1 00 Fr:nklin Research C;nter FRC Project No. C5257 - - Page i A DMston of The Frankhn Institute FRC Assignment N2.13 3a l 20th and : tace streets. Phda.. Pa. 19103 (215) 448 1000 FRC Tat k No. 6II _. l l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .eS6, . , n LICENSEE RESPONSE 'IO NI'.C SER 42 Ecutement Recuirine Additional Info mation an'd/or Corrective Action (Accendix 3) ,' The bulk of master list equipment was plar.ed in this categery and our review of deficiencies is based upon the following: g Deletion of deficient listed' equipment due to replacement prograus ,_ ' carried out and reported in our 90-day, Re. vision 3 response dated ' February 1, 1981.

                                                                                                                                                                                                          )
                                                                                                                         ,-a Re-evaluation of CP&L's updated submittals by PRC Region II,                                                                           .

Atlanta, GA, and reported in Environnenta'.- Qualification of Sifety , _ 3 ', Related Electrical Equipment IE3 79-O'.3.: ' Technical Evaluation Retprt'

                         - Docket No. 50-261; Plant: H. 3. Robinson 2, dated November 6,-- 1980 y
                                                                                            ~

c" ' and Revised November 11, 1980.  ; , y -a.__ - Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, ^

                        'et al.                                                               ,
                                                                                                                                                                        -                      s Equipment reported as qualified within NRC TER Revision 1, dated Novembe,t'llb                                                                                                                     ,

1980: 's +

                                                                                                                                                                              ,(

Ecutement Descrietion Manufacturer Medel No_., Location - i , .s

            ?. - ?u ;           ter                           :: t ingh o u c e MS" '                                      Z->n                            ,A c---,s.           m ;

_.1-r------

                                                                                  .y_

_,_2.._.,u,,,.- Q

          -2        meter : er.ter

_w---- . _rAc ? . aut M -

                                                                                                                  --                                    containt -t'
          ,'-       roter gerate
                                                                  .icium -               ~-
                                                                                                      .W2 1                                             cu-e :

m: 9 aea.s' 3- f1 = trcn:ritter ?ie.cr i ?:et:r 102 ': ' " 5  : :26 s 2

' '2 . ' ? 22-he s

                    " a '""_' r '   ~~ritt:r                  icher i 'cr :r                             ~ - - , ' ' _ '_

rp;;;a . - - _ - e - t e_ - -

           ^'
                . far "20 to r-                               *'cetingh6uca
                                                                                                           $ ?? 5- - -'                                 v - ,        .m     . -
             ? 02b i:                                          Cer tinAnta'. " ire                         C  " '_ ; T-h in- : :
                                                                                                                                                         '                                         [/

t 2 b '.a

                                                                                                                                           ~ , ','e'entain=ent.

9. cable ,

Ierite va pg 4 , V A. Cable Kerite High tamp, fire resistant 1- R,RT,P,H,CS,A g b b& A9 m e p 1 g 1 7

                                                                      ~ * * - - '

j

                            '. /

' NRC Contract N 3. NRC-03-79-118

     ;/
                                                                             . FRC Project No.C5257                      Page Fr:511n Research Center

, ' ' A Dhnskm of %e FrankPn 8nsutute FRC Assignment No.13 3b 20th and Race Streets. Phda.. Pa.19:03 (215) 448-lM0 FRCTask No. 5/ \ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITE,M NO. s_2f, 7 6 3.2.4 Electrical Cable

                                                                          )

The electrical equipmenti in containment and reported within i the equipment list of. t' tis report is connected by either single conductors or multiconductor cables. These cables run

                                      ,via cable trays and conduit from the electrical penetrations
                                     ' to the equipment.               Connections to the electrical penetrations are made by-individual or grouped cable splices, or by elec-
                       , .             trical connectors.               At the equipment end, formal component r<4 teruinals with.cverall tape or crimped terminals with overall tape are used for. connection.

The connectors tised (Crouse-Hinds Model No. RPC-117-150-

                                      'POIN/P08N) were supplied with the electrical penetrations and mounted on the matching cable during construction. For details concerning qualification of this connector, see Section 3.2.1. For details concerning cable splices and
                              .x      ;cerminstp see Section 3.2.5.
      ~

The electrical cable us'ad for equipment hookup is divided into j- throa (31. classificaticus: s o multiconductor.- 2/C #16, 3/C #16, 3/C 19/#22 I;' ' o multiconductor - 2/C #16, 4/C #16 (single drain wire utilized as shield) l j _ o single conductor - 500 MCM i The unshielded multiconductor cable is used to power the identified motor-operated valves (3C 19/#22), control the identified ' solenoid valves and provide limit switch outputs

                                ' (2/C #16, 3/C #16). The shielded multiconductor cable is used for analog signals obtained from the listed transmitter and th'e listed RTD temperature ele =ents (2/C #16, 4/C #16 shielded) .

The single conductor cable (500 MCM) provides power for the I it containment fans (HVH-1 through HVH-4). The shielded cables used for containment instrumentation utilize the provided  ; alectrical connectors at the penetration end. Inspection of in-containment field cable hookup to limit switches and solenoid valves performed the week of August 18, l 1980 through August 22, 1980 determined that Kerite fire- M l resistant conductor insulation with overall fire-resistant ~ j jacket cable is used. i i l 1 l

i NRC Contract No, NRC-03-79-118 Page l 00 Fr:nklin Research C;nter FRC Project No,C5257 A Division of The Frenkhn Institute FRC Assignment No.13 3c 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. 8 /I i i EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J!4 I The Kerite Company has attested to the ability of this cable supplied for H. B. Robinson to withstand the FSAR LOCA conditions of temperature, pressure and radiation. In addition, test qualification included forty- (40) year aging, borated spray and 100% relative humi'dity to meet IEEE 323-1974 and IEEE 383-1974 requirements. Referenced. reports are: Al FIRL Report F-C4020-1 dated March 1975. Kerite Proprietary Engineering Memo No. 178 entitled,

                " Determining Temperature Ratings of Cables and Pre-aging Requirements for LOCA Simulation Tests," dated December 27, 1974 (superseded by EM178A dated May 1, 1979).

For motor power required for valve operation, a Kerite dI. TEMP conductor insulation with asbestos fillers, nylon binder tape, neoprene treated tape, with fire-resistant jacket reinforced with a cotton-sleeve cable is in use within containment. For containment fan power, a Kerite HI TEMP conductor insu-lation with overall fire-resistant jacket, reinforced by cotton-sleeve cable is in use within contain=en;. The Kerite Company has attested to the ability of this cable supplied for H. B Robinson to withstand the FSAR LOCA conditions of temperature, pressure and radiation. In addition, test qualification included forty- (40) year aging, corated spray and 100% relative humidity exposure to meet IEEE 323-1974 and IEEE 383-1974 requirements. Referenced reports are: gg FIRL Report F-C4020-2 dated March 1975. Proprietary Engineering Memo No.178 entitled, " Determining Temperature Ratings of Cables and Pre-aging Requirements for LOCA Simulation Tests" dated December 27,1974 (superseded by EM 178A dated May 1,1979 and Di 178B dated December 1, 1979). To provide protection for cable te.r=1 nation at equipment end, when no formal termination method was provided, a silicone rubber tape was used. SCOTCH 70, high temperature silicone rubber tape, is used for safety-related terminations. This product has undergone radiation testing by the manufacturer, Minnesota Mining & Manufacturing Company (3M) up to 1.0x10 RADS at 40 C temperature with no major degradation of performance. g 1 i 1

NRC Contract N . NRC 03-79-118 g06,:nkiin U0 R: .rch cent., FRC Project N2.cs:sy Page A Division of The Frank!!n Institute FRC Assignment N?.13 3d 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. 6/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. s24 A more comprehensive testing program to meet.IEEE 323, 1974, requirements has been performed by Kerite Company utilizing SCOTCH 70 tape and Kerite Cable within LOCA testing chamber. Kerite has certified the use of SCOTCH 70 as detailed in Reference Number 50. ToassuretapequalificationforH,3)Robinsonapplication, SCOTCH 70 tape vill be used in conjunction with test control cables during qualification testing of the electrical penetrations PVC pigtail cable being performed at Wyle Laboratories. M after completionResults of PVCwill be docu=ented and available cable testing. 1

4UOOU Frink!!n Research Ccnter NRC Contract N o. NRC-03-79-118 FRC Project No. C5257 PaSe A Division of The Frankhn Institut2 FRC Assignment No.13 5a 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. ElI EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. & EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW Criteria: DOR Guidelines  ; NUREG-0588, Cat. I  ; NUREG-0588, Cat. II . NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) EQUIPMENT DESCRIPTION  !  !  ! Equipment Type 'g Electrical Cable Manufacturer's Name  !  ! The Kerite Company e (5.2.2/-/-)  !  ! j Model Number (5.2.2/-/-) . 7 /d.

                                                                      ,See Note 1 on pages

• Serial Number
• 511 and 512 f

pt [c s*- / 4 , Features / Mounting 2 3 C /k! 1000V power Cable  ; (5.2.6/-/-)  ! #DMC M  !

                                                  !                   ! 600V Control Cable             !

Connections / Interfaces  ! g, g d a . ! . g (5.2.6/-/-)  ! I

                                                                      ! Splices on Power Cable ee    te 2 Page 51 3             ## "

• Location / Elevation 74 4-s $ u s 1l'sA Co41*m & 'g N ot 9 Pment ID No. . A/ A Not Applicable f

QUALIFICATION REPORT  !  ! I (8.0/5.0/5.0)  !  ! I Report ID Number  ! b-C 840dtd*l ! F-C4020-1 l* 1 F-c'/oAo* ! F-C4020-2 Report Date I

• March 1975 *

                                                   ,  y/ yg' Issued by                                          { p-ikt

{FranklinInstitute f*

                                                              .

• Research Laboratories Prepared for 'ggg,,,Te *f.TheKeriteCompany f-Referenced Reports ,p A-f ac/. Not Applicable
• Qualification Method  !  ! Simultaneous Test (5.1, 5. 3/2.1, 2. 4/2.1, 2. 4) !  !

QUALIFICATION TEST PROGRAM  !  !  ! Functional Test Description !  !  ! (5.2.5/2.2.9/2.2.9)  ! MM g

                                                                       ! Insulation Resistance
                                                                       ! During Test g

g Operating Conditions  !  !  ! (-/2.2.10/2.2.10) Ikd I !1000V/50A-Power Cables I Ioad/ Cycles / voltage /  !  ! 600V/12A-Control Cables  ! Current /Freq.  !  !  !

NRC Contract No. NRC-08 79-118

  @QDFr:nklin R: search Ccnter U                                                            FRC Project No. CS257                    Page A cans on of The Frankhn Institute                      FRC Assignment No.13                     5b 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000  FRC Task No. X/ l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M NRC REQUIREMENTS                                                                          DEFICIENCY WITH SECTION REFERENCE                                LICENSEE             QUALIFICATION          (X OR (DOR /0588-I/0588-II)                                SUBMITTAL            DOCUMENTATION         NOTE NO.)

Acc:ptance Criteria  !  !  ! ( 5. 2. 5/2. 2.1/2. 2.1) 18//*  ! Maintain Current  !

                                                    ! #MM          ! carrying capability        1 Accuracy (5.2.5/-/-)                               ' g,           . Not Applicable f

Number of Specimens ' A(p4 . 10 Tcat Instruments Calibrated ' //,/8 . 7,3 j SRfsty Function (Active /  !  !

                                                                   ' Carry current P0ccive) (-/2.1. 3/2.1. 3)                        '                                           '

Test Duration (5.2.1/-/-) . Mh f100 Days f Accident Duration (Envir. 1- Not Applicable I Abova Normal) (5.2.1/-/-)  ! y l 4s30 .  ! Required Function Time . ggg .  ! h TJet Sequence (General)  ! g4  !  ! ( 5. 2. 3/2. 3.1/ 2. 3.1)  !  !  ! Tact Sequence (NUREG-0588,  ! gA,  !  ! Cat. I) (-/2.3.1/-)  !  !  !

1. Representative Sample  !  ! Yes Per IEEE-383-74  !

2. Baseline Data  !  ! NotApplicable I 3.

4. Performance Extremes Thermal Aging [M  ! Rated Current / Voltage  !

                                                                   ! Both Aged and Unaged       1

5. Radiation Aging  !  ! Simulated 40 years j

6. Wear Aging  !  ! Not Applicable *

7. Vibration / Seismic  !  ! Not Applicable I

8. DBE Exposure  !  ! Per IEEE-323-74 &383-74 1

9. Post-DBE Exposure  !  ! Simultaneous Gamma I

10. Inspection Visual /Megger/HiPot Aging  !  !  !

(5.2.4, 7.0/4.0/4.0)  !  !  ! Thornal Aging / Basis  ! Nd,  ! 101 hours @ 150*C  !

                                                    !              ! Arrhenius                  I Matorial Aging                                    !              !                            !

Evaluation (7.0/-/-)  ! M.A  ! See Note 3 Page 5f 3 1  !  ! Materials Susceptible  ! /A,  !  ! (Thermal) (5. 2. 4, 7. 0/-/-)  !  ! Not Stated 1 Radiction Aging, Type  ! g,4 1 g,,,, '.

l NRC Contract No. NRC-03-79-118

@0br:nklin Rrsearch Ccnt:r U                                                            FRC Project N2. C5257                       Page   j A Divisbn of The Frankhn institute                       FRC Assignment No.13                         $C 20th and Race Streets. Phda.. Pa. 19103 (215) 448-10m    FRC Task No. S/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. S A NRC REQUIREMENTS                                                                            DEFICIENCY WITH SECTION REFERENCE                               LICENSEE              QUALIFICATION            (X OR (DOR /0588-1/0588-II)                                SUBMITTAL              DOCUMENTATION         NOTE NO.)

Radiation Aging, Dose (rd) 48.9 to 50.4 Megarads Radiation Aging, Dose Rate 1"o-p,o 3 k h! 327 g to 337 Kilorads / hour

• Radiation Aging, Method { g, A

{ Test

                                                                  .                            f.

Materials Susceptible  !  !  ! (Radiation) (S.2.4, 7.0/-/-)  ! !Not Stated 1 Operational Aging !g, A  ! Current Maintained f (-/4.2/-) f.duringRadiationtest Other Age Conditioning  ! g ,4.  !  ! (-/4.2/-) . I Not Stated Qualiflad Life Claimed / !g 1 I 40 Years See note 2 Establi.shed (5.2.4/4.10/-)  !  !  !

                                                 !                 !page 5f                    1 Normal Ambient Temperature                       ! I i 6*F- AW. ! N                             I Normal Amoient Radiation                         ! So-a,pg/,h. ! ot Applicable Normal Ambient Humidity                          'g, A ,ywtg f.NotApplicable Not Applicable f.

On-Going Surveillance and  !  ! Not Applicable

                                                  !                !                            f.

Preventive Maintenance (7.0/-/-)  !  !  ! On-Going Analysis of  !  ! Not Applicable I Failures and Degradation  ! \[8,5  !  ! (7.0/-/-)  !  !  ! Margin (General)  ! I Stated f (6.0/3.0/3.0) { M {Not Margin (NUREG-0588,  !  !

• Cat. I) (-/3. 2/-)  ! I Stated *

1. Temperature (+15'F)  !

2. Pressure (+10%,  ! {Not 10 psig max) 1 1 *

3. Radiation  ! I *

(not required)  !  !  !

4. Time (+10%, +1 hour  !  !  !

     + function time minimum)                      !                !                             !

I

NRC Contract No, NRC 03 79-118 00 Fr:nklin R:serrch C:nter FRC Project N2. C5257 Page A Dwon of The Frankhn Institute FRC Assignment No.13 5d 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. E ll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .d.4 , NRC REQUIREMENTS DEFICIENCY 3 WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS  !  !  ! IDCA/MSLB/HELB/ Uncontrolled !MdA !LOCA/MSLB 1 (4.1, 4.2, 4.3.1,-4.3.3/  !  !  ! 1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) !  !  ! e e e Radiction Type ~ Gamma Radiation Dose (rd)  ! ' 148,9-155.6 Megarads ' (4.1.2/1. 4/1. 4)  !;q g . . Radiation Dose Rate (rd/hr) Radiation Qual. Method f84 f S1*+8d f. 337 - 352 Kilorads / Hour f. (5.3.1/-/-)  !  !  ! d ion gg-f Jta.tM Not Applicable f (4.1. 2/1. 4. 6/1. 4. 6)  !  !  ! Equipment Susceptible to  ! Beta Radiation (4.1.2/-/-) -!

                                                        #4+ 6 NiN Not  !

Stated  ! Radiation Dose (Normal + 1

                                                         ,f pg ' Not Applicable                       !

Accid:nt)p (4.1.2/-/-) .  ; j 1  !  ! i Platscut Dose Considered  ! gs/- $ 74'/ d !  ! l (-/1. 48/1. 4 8)  !  ! Not Applicable , Ganuna + Beta Dose (rd)  ! e (4.1.2/1.4.7/1.4.7) !gf g fgg g; Not Applicable , l \

A NRC Contract N A NRC-03 79-118 lj00hr:nklin Rise rch C:nter FRC Project No.C5257 Page A DtWon of The Frankhn Insntuti FRC Assignment NA 13 5e 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRC Task No. -81 I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. cG4 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION. NOTE No.) ENVIPONMENTAL PROFILE  !  !  ! OF ACCIDENT CONDITIONS  !  !  ! Rate of Temp./ Press. 28'F;7 Psi /second  ! Increase . g,gog 4O . . Peak: 'F/psig/RH/ Time .pty/q j,,/36 346/113/100%/6 hours 2 peaks 3 hrs each Decrease To: 'F/psig/RH/ Time sti4[#s/pvft 335/95/100%/3 hrs f Decrease To: 'F/psig/RH/ Time

                                                       /5'>[U'[/Hf,f315/69/100%/4 hrs               !

Decrease To *F/psig/RH/ Time !  ! 265/28/100%/4.5 days  ! 8 6 Equipment Surface Tempera-ture (MSLB) (-/1. 2. 5. C ,  ! jy/$'  ! 212/5-9/100%/96 days f* Not Applicable 2.2.6/1.2.5.C, 2.2.6)  !  ! g Spray Qualification Method  !  ! (5.3.2/1.3, 2.2.8/1.3,  ! N 4-  ! Test 2.2.8)  !  !  ! Spray Composition  ! g 1 (4.1.4/1.3, 2.2.8/ f, 0.28 Molar H 3B0

                                                    ! g ,g g ,!                                     I

1. 3, 2. 2. 8) #

d. M S #tdM! pH 10.5 0.064 Molar Na2S 023 Spray Density (gpm/f t 2)  !

fM93 - 1

                                                       / Fat J+e4ad g! 0.15 Spray Duration                                              j , gg

• 98.5 days submergence Duration  !  !  !

( 4.1. 3/2. 2. 5/2. 2. 5) !gst 51*fa i ! Not Applicable c  ! In-Leakage considered !g ,fSfwf*d! Not Applicable  ! ( 5. 2. 6, 5. 3. 2/-/-)  !  !  ! Time to Submergence !jvofSWd ! Not Applicable  ! Dust Environment  !  ! (-/2. 2.11/ 2. 2.11)  ! g p g g g ! Not  ! Applicable  !

• Interrupted at 23 days to remove test chamber from Hot Cell.

l

V NRC Contract No. NRC-03 79-118

  @LO0hrinkhn R:serrch Ccnter                                  FRC Project N3. C5257            Pag 3 A Divmon of The Frrnkhn Institut>                        FRC Assignment No.13              5f 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000   FRC Task No. 6iI EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQU!PMENT ITEM NO. .lf-
  " "* A)o+c L a) Two of the cable samples, one with a splice and one without a .plice                        -

were preaged in a circulating hot air oven for approximately 100 hour; at 1500C. The time-temperature necessary to preage these ca~ oles to - the equivalent of forty years's service was obtained from proprietary _ Arrhenius data presented in Kerite Engineering Memorandum No.178

                                                                     ~

dated December 27,1974 a) One of the 50 foot samples and one of the 10 foot sampics was preaged in a circulating hot air oven for approximately 100 hours at 150 C. The time-temperature necessary to preage these cables to the equivalent of forty years'se'rvice was obtained from proprietary Arrhenius data presented in Kerite ~' Engineering Memorandum No.178, dated December 27, 1974 LM d MM Au i A V AR/~ s - " u k 1W n. A K D GG-v t cwl-d n Mshr J w]JodA

        /        (;          -

onM g s l l l

A NRC Contract No. NRC-03-79-118 Page UO0hrrnklin R:sench Center FRC Project No,C5257 A Divisen of The Frankhn instituo FRC Assignment N2.13 Si, 20th and Race Str+2ta. Phda.. Pa. 19103 (215) 448-tmo FRCTaskNo. 8/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 24 was,No+ei

2. SPECIMEN DESCRIPTION This report covers six cables, E, F, G, H, I and J, which are described in Table 1. Cables F, H and J were thermally preaged by the Kerite Company prior to receipt by FIRL.

Table 1. Description of Specimens Wire Energizing Cable No. of Size Pre-Aged Potential No. DescrIDtion(,) Conductors AWO Condition (,) (Vac) Current load ,(A) E 600 V control cable. 30 7 12 Unaged 600 12 mits HTK, 20 mits FR (N-98/Hi-70) insulation, 65 mils FR (HC-711) Jacket. 0.75-in 0.0., 50 f t length. F 600 V control cable 30 7 12 Aged 101 hrs 600 12 mils HTK, '20 mils FR 9 150*C (N-96/HI-70) insulation, 65 mits FR (MC-7il) jacke t 0.75- 0.D., 50ftlength.{* G 1000 V power cable. 4/64 1 6 Unaged 1000 50 HTK (N-98) Insulation, 65 mits FR (HC-711) Jacket, 0 50-i 50 ft length. g 0.0., H 1000 V power cable, 4/64 1 6 Aged 101 hrs 1000 50 HTK (N-$6) insulation, 9 150'c 65 mils rn (HC-7]l) Jacket, 0.50-in. 0.0., 50 f t length. (b) i 1000 V spliced power cable, 1 6 Unaged 1000 50 4/64 HTK (N-96) Insulation, 65 mils rR (MC-711) Jacnet. 0.50-ie. 0.0., 10 ft length. (b) J 1000 V spilced power cable. 1 6 Aged 101 hrs 1000 50 h/64 MTK (N-9d) insulation. 0 150'c 65 mils FR fMC-7tl) Jacket. 0.50- a. 0.0., 10 ft length.jb) , t NOTES: (a) Cable descriptions were provided by the Karite Company. (b) Length inside pressure vessel.

NRC Contract No. NRC 03-79-118

  @O0hr:nklin U                         Research Center                         FRC Project No.C5257                      Ps08 A Dhns6on of The Frankhn Institute                         FRC Assignment No.13                        Si t FRCTask No. 1 f//

20th and Race Streets. Phila.. Pa 19103 (215) 448 1000 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. s&A anzss pote1,(con +'d)

2. SPECIMEN DESCRIPTION This report covers four cables, A, B, C and D, which are described in Table 1. Cables B and D were thermally preaged by The Kerite Company prior to receipt by FIRL.

Wire Energizing Current Cable No. of Size Pre-Aged Potential Lead No. Description (g) Conductors AWG Condition {g) (Vac) (A) A 600 V control cable. 50 mits 7 12 unaged 600 12 FR (HI-70) insulation, 65 mi'Is FR (HC-711) Jacket,(2) 0.74-In. 0.0., 50 ft length B 600 V control cable. 50 mils 7 12 Thermally aged 600 12 FR (HI-70) Insulation, for 101 hours

• 65 mils FR (HC-711) Jacket,(2) 9 150'c 0.74-in. 0.0., 50 f t length C 600 V spliced control cable, 7 12 Unaged 600 12 50 mils FR (HI-70) Insulation, l

65 0.74mils In.FR (HC-711) 0.0.,10 Jacket (2) f t length , 1 O 600 V spliced control cable, 7 12 Thermally aged 600 12 50 mils FR (Hl-70) Insulation, for 101 hours 65 mils FR (HC-711) Jacket,(2) @ 150'C 0.74-in. 0.0., 10 ft length l l (1) As reported by The Kerite Company. (2) Length inside pressure vessel. t i

NRC Contract N c. NRC-03-79-118 A@J d Fr:nklin Rese rch Center FRC Project No. C5257 P g2 A Division of The Frtnkhn Institute FRC Arsignm nt NA 13 10 20th and Race Streets. Phila.. Pa 19103 (215) 448-1000 FRCTaskNo. 8// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. *I7 EQUIPhENT ITEM NO. 27 (TMI ACTION PLAN ITEM-ALL) ELECTRICAL CABLE LOCATED IN THE CONTAINMENT ROCKBESTOS, MODEL NOT STATED REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 27 LICENSEE REFERENCE (S): 1391 FUNCTION (PLANI ID): ELECTRICAL DISTRIBUTION, TMI EQUIPMENT LICENSEE SUBMITTAL: SCEW(S): 14 0F 15 [15] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) R, T, QT, RT, P, H, CS, A, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, Not stated, No applicable ff ET M _ _ _ LISTING OF APPLICABLE CHECKSHEETS_: Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, L , L , 31 System Consideration Review 0-, L, eu, 2d, 4m, if ( Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, 5f,

                                                                                - 55 , Sh, Si, Sj-Installed TMI Lessons Learned Implementation                                   6a, 4b l  Equipment Summary Maintenance and Replacement Schedule Summary                                   7-, L , 7; l

l

NRC Contract N2. NRC-03-79-118 phrtnklin UO0 Riseirch Cantir FRC Project N2. C5257 Pa03 A Division of The Franklin Institute FRC Asaignment No.13 lb 20th and Race Streets. Phala.. Pa. 19103 (215) 448 1000 FRC Task No. 8/I l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. # 7

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. i The Licensee (has/has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE l environnertal service conditions. j The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment-item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment - Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

   - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend) l l

k.a Qualified] II.c Qualified Life Deficiency

 ~ I.b    Modification                                                III.a Exempt II.a Qualification Not Established                                 III.b Not in Scope II.b Not Qualified                                                 IV    Documentation Not Available l

NRC Contract N2. NRC-03-79-118 phr:nklin R:se:rch Ccnter FRC Project N . C5257 Page UO0 A Dtvlsion of The FrankhnInstitute FRC Assignment No.13 2 20th and Race Streets. Phila . Pa. 19103 (215) 448-1000 FRC Task No. SIf EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. cCZ l l l EQUIPMENT ENVIRONMFNTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY l Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately " o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified 1 I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available [ $

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                                                                                                                 'a" (2) See accident profLle - Temperature - Figure 3.1.1                                                     h (3) See accident prof 11e - Prensure - Figure 3.1.2                                                       :5              g (4)  In containment radiation level established for purchase of component-- - -                           E               a g

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NRC Contract No. NRC-03-79-118 4ll00U Fr:nklin R:se:rch Ccnter FRC Project Na. C5257 Page FRC Assignment N3.13 A Division of The Frankhn Instuuis 50 20th and Race Streets. Phila. Pa. 19103 (215) 448-1000 FRC Task No. 5 11 l EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _%1 EQUIPMENT ENVIRONMENTE QUEIFICATION REVIEW Criteria: DOR Guidelines  ; NUREG-0588, Cat. I N ; NUREG-0588, Cat. II . NRC REQUIREMENTS DFEICIENCY WITH SECTION REFERENCE LICENSEE QUEIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.)

                                                    !                     ! Es.ccTR.icAt C.Albt E          !

EQUIPMENT DESCRIPTION  !  ! Ei.tcynicAL !3 Fewen/ INSTRUMENT! CONTROL ! Equipment Type

                                                    ! CABLE               !                                !

Manufacturer's Name  !  ! (5.2.2/-/-) !M24.570s !EOCM.BESTOS CO. {' Model Number (5.2.2/-/-) ff~lR.E W A1.1. E i 2lC41%  !  ! Serial Number  ! 5/C:*> 14- !p , Features / Mounting . l/C,4 6,AwG,45r it,,FR,XLPE. (5.2.6/-/-) ' j 3/C SH4 Ko ;,[N STR.U Mf.NT 3COV

                                                                                                            ; NOTE.1 4/C S N 4 % !('/c# 1G AWG,20mu.,FR,XLPE) ;

Connections / Interfaces 1 * (5.2.6/-/-)  !  ! Co urs.ot. 600v - Location / Elevation

• NTAINW /c,4 2.AWG,50mii.,% Md f i - -

Equipment ID No.  !  !

• QUEIFICATION REPORT  !  !  ;

i (8.0/5.0/5. 0)  !  !  ! Report ID Number  ! -  !  ! Report Date  ! ~

                                                     !                    !        ~7 ~7 ~7'7              1 Issued by                                         2                     !                                !
                                                                          !Rocx,BesTos Co.                 !

Prepared for  !  !  !

                                                     .                    !  RotweEsros Co.                !

Referenced Reports ' NO . Qualification Method  ! ~ (5.1, 5.3/2.1, 2. 4/2.1, 2. 4) !  ! T'Y P E. 1 E.ST I QUALIFICATION TEST PROGRAM  !  ! e Functional Test Description ! 25 MtNu rc Dic.t.straic  !, (5. 2. 5/ 2. 2. 9/2. 2. 9)  ! !WlTHSTAN D "I~EST, T'AP , l WATER T.mmggggey  ; Operating Conditions BO VAC/MIt. { (-/2.2.10/2.2.10)  !  ! GOO VAC ,70 A (. Pow t R)  ! Load / Cycles / Voltage / S""E" h' , Current /Freq. ' Goo VAC,3OA (cowenoQ

• l

NRC Contract N2. NRC 03-79-118 00 Fr:nklin R: search Center FRC Project No. C5257 Paga A DMeson of The Frankhn Insutuu FRC Assignment N2.13 5b 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. 5 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 27 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) 7.cc1ptance Criteria { jPASS 8 VAC/mit {

                                                                                  ! Vos.TAoE W/sTANo TEST

( 5. 2. 5/2. 2.1/2. 2.1)  ! , Accurtcy (5.2.5/-/-) -

                                                                                  .;NA                 .

Number of Specimens  ! 2: 18 TEST SAMPLE.S NOTE 2 1 , T0ct Instruments Calibrated !  !:  ! SnfGty Function (Active / !y 4p  !  !' Paccive) (-/2.1. 3/2.1. 3) . Es.sr.vnicat f  ! Cauterw Nr- . Tect Duration (5.2.1/-/-) 1  !  ! Accidsnt Duration (Envir. 1 1 Abova Normal). (5.2.1/-/-)  !  !  ; 1  !  ; Required Function Time  ! goq 7g Tact Sequence (General)  !  ! * (5.2.3/2.3.1/2.3.1) -

                                                                                   ! TA/                                                                ' E SAMPLES

, 1 RAD /STm tCHSP/ l  !  ! POST LOC.A St%ULATION ; (hlOTE 2.) Tect Sequence (NUREG-0588,  !  ! - Cat. I) (-/ 2. 3.1/-)  !

1. Representative Sample  !  !

2'. Baseline Data  !  !  !

3. Parformance Extremes  !  ! 5

4. Thermal Aging  !  !  !

5. Radiation Aging  !  ! I

6. Wzar Aging  !  !  !

7. Vibration / Seismic  !  !  !

8. DBE Exposure  !  !  !

9. Post-DBE Exposure  !  !  !

10. Inspection  !  !  !

 - Aging                                              !                            !                                                                    !

(5.2.4, 7.0/4.0/4.0)  ! 1 1300 HR.@ 450.C./ Th:rmal Aging / Basis  !  ! 4O yr. @ optRATiNG  !

                                                      !                            ! TEMPERA,TURE Or 90 'C                                              !

Mat 0 rial Aging  !  !  ! Evaluntion (7.0/-/-)  !  ! kRR.H E.NtO S CATA . 1 1  ! Matsrials Susceptible  !  !  ! (Thstmal) (5. 2. 4, 7. 0/-/-)  !  !  !

                                                      ;                            j iMSubATING tAATER.1ALS                                          g Radiction Aging, Type                               1                            1 gamma 1
              - - _ _ _ _ _ _ . _ _ - _ - , . . ~ -     -.._ ,,.- - ,,           -       , - - . - -     , - . , _ _ - . , , - - _ - . , _ - , , , .          , , - , - - ,

A NRC Contract No. NRC-03-79-118 000hrinklin R:seirch Conter FRC Project N;. C5257 Page A Divisen of The Frankhn Instituti FRC Assignment N2.13 5c 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1M FRCTask No. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 27 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Radiation Aging, Dose (rd)

50. 0 x 10 " .

Radiation Aging, Dose Rate  !  !  !

                                                  !               !    O. (o5' Med/h           !

Radiation Aging, Method  !  !  !

                                                  !               !     TEST                   !

Materials Susceptible  !  !  ! (Radiation) (5.2.4, 7.0/-/-) !  !  ! Operational Aging  !  !  ! (-/4.2/-)  !  ! NA  ! Other Age Conditioning  !  !  ! (-/4.2/-)  !  ! NO  ! Qualified Life Claimed /  !  ! ~ Established (5.2.4/4.10/-) '

                                                                  !   4Q yg. /40yr.             '

Normal Ambient Temperature 120*F m . [ [ Normal Amoient Radiation !o.1 + 400 rJd !  ! Normal Ambient Humidity ' go  !  ! On-Going Surveillance and  !  !  ! Preventive Maintenance  !  !  ! (7.0/-/-)  !  !  ! On-Going Analysis of  !  !  ! l Failures and Degradation  !  !  ! (7.0/-/-)  !  !  ! Margin (General)  !  !  ! l , (6.0/3.0/3.0)  !  !  ! l i Margin (NUREG-0588,  !  !  ! Cat. I) (-/3.2/-)  !  !  !

1. Temperature (+15'F)  !  !  !

2. Pressure (+10%,  !  !  !

10 psig max)  !  !  ! l 3. Radiation  !  !  ! (not required)  !  !  !

4. Time (+10%, +1 hour  !  !  !

       + function time minimum)                     !               !                            !

NRC Contract No. NRC-03-79-118 00 Fr:nklin2:seirchCenter FRC Project NO. C5257 Page A Divwon of The Fr:nklin Institut2 FRC Assignment No.13 5d 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRCTaskNo. 511 EQUIPMENT ENVIPONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. 27 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS  !  ! .  ! IDCA/MSLB/HELB/ Uncontrolled ! (4.1, 4.2, 4.3.1, 4.3.3/  ! g

                                                                            !        LOG                1 1.1, 1.2, 1.5/1.1, 1.2, 1.5) !                                      !                           !

Radiation Type GAmwA MMA. i Radittion Dose (rd)  !  !

1. 5x 10 8 d 1 -

(4.1.2/1.4/1.4) s

                                                            !2.Ox lo ,.g,3                              :

Radiction Dose Rate (rd/hr)  !  ! Q, g g  ! Radiation Qual. Method ' ' ' (5. 3.1/-/-)  !  !  !

                                                            !               !                           !          ~

Proximity to Concentrated  !  !  ! Radiction  ! - (4.1. 2/1. 4. 6/1. 4. 6)  !  !  ! Equipment Susceptible to  !  !  ! Beta Radiation (4.1.2/-/-)  !  !  ! Radiation Dose (Normal + 1  !  ! Accident) (4.1.2/-/-)  !  !  ! Plateout Dose Considered  !  !  ! (-/1. 48/1. 4 8)  !  !  ! Gamma + Beta Dose (rd)  !  ! (4.1.2/1.4.7/1.4.7)  !  !  ! t L l l I __ _ __. _

NRC Contract No. NRC-03-79-118 L0bbnnkhn R:se:rch Center FRC Project No. C5257 Page A Division of The Franklininstituta FRC Assignment No.13 5e 20th and Race Streets, Phila.. Pa. 19103 (215) 448-1000 FRCTask No. 5 ti EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 21 NRC REQUIREMENTS DEFICIENCY l WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIRONMENTAL PROPILE  !  !  ! OF ACCIDENT CONDITIONS  !  !  ! Rate of Temp./ Press. 2 (. 5"/s  ! l40 - 34G /o- 113 1 g 2 gy 4, gggg,  ! Increase  !  !  ! Peak 'F/psig/RH/ Time 2(A.7/42/seo[4h 346[I13[100[3 HR. Decrease To: 'F/psig/RH/ Time 1219/20/soo/zth 3 335/93/100/3 HR  ! Decrease To: 'F/psig/RH/ Time 152/s.ofoo/+ '315/G9/too/4 HR ' Decrease To "F/psig/RH/ Time 2(oE/2.8/ loo /81 HR. Equipment Surface Tempera-  !  ! ~ I ture (MSLB) (-/1.2.5.C,  ! -

                                                                         !       90*C                 !

2.2.6/1.2.5.C, 2.2.6)  !  !  ! Spray Qualification Method  ! e (5.3.2/1.3, 2.2.8/1.3,  ! j Simut T ANEOUS T Egy { 2.2.8) g . ,

                                                     ! l.~1 s#40        3 Spray Composition
                                                     !N5 %

• 3 (4.1.4/1.3, 2.2.8/

                                                     ;Na.oH(ur H %3,300o         ps - 10.5ppm ecgoy.

1.3, 2.2.8)  !

                                                     ! /'# T 3

• l Spray Density (gpm/f t 2) g _ ,

O.15 - Spray Duration j f*

                                                               ~

24 HR . , Submergence Durati'on  !  !  ! (4.1.3/2.2.5/2.2.5)  ! - In-Leakage Considered  ! -  ! ND  ! (5. 2. 6, 5. 3. 2/-/-)  !  !  ! t Time to Submergence  ! ~ l  !  !  ! } Dust Environment  ! ~ l (-/2.2.11/2.2.11)  !  ! Nb  ! l l

I x NRC Contract No. NRC-03 79-118 Pag 3 e(100hnnklin R: search Center FRC Project N;.C5257 A Dwis6on of The FrankhnIncuu FRC Assignment No.13 5f 20th and Race Streets. Phila.. Pa. 19103 (215) 448-10m FRC Task No. 5 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2'I NOTES:

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4 NRC Contract No. NRC 03-79-118 UOOLIFrrnklin R:: search Center FRC Project No.CS257 Pa08 A DMeon of The Franidin inmuuo FRC Assignmentlig.13 60 20th and Rue Sereets. Phile. Pa. 19103 (215) 448-1000 FRC Task No. 3 11 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. #'7 , f INSTALLED TMI LESSONS LEARNED IMPLEMENTATION EQUIPMENT

SUMMARY

NBC requested an evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments required for TMI Lessons Learned Implementation. The objective is to evaluate qualification documentation of equipment within the scope of IE ' Bulletin 79-OlB, Supplement 3 (item 2) , in accordance with criteria established-by the NRC (see Section 2 of this report) in a manner identical to the evaluation of all other safety-related electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with specific sections of NUREG-0737 which have an instiallation implementation date of January 1,1981 (sections are identifiou below). Where applicable, a review is to be performed on installed equipment with implementation dates af ter January 1,1981 if adequately identified by the licensee. This plant is a PWR , BWR . The NSSS Vendor is Westinghouse (W) , Babcox & Wilcox (B&W) , 4 Combustion Engineering (CE) , General Electric (GE) . With respect to this equipment ites, it is noted (applicable section checked): The Licensee does not provide adequate information with respect to identification of TMI Action Plan equipment installed as of 1/1/81. i The Licensee has not provided the correlation of this equipment item with the specific sections of NUREG-0737. [The correlation is needed to ensure that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal

      .                blocks associated with the device also identified?)

The Licensee has not provided the approximate installation date for the TMI' Action Plan equipment items so that the appropriate qualification

{ criteria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. The Licensee has provided a standard Ownars' Group position with respect to a NUREG-0737 technical area. , The Licensee has requested extensions of implementation dates. i K The Licensee has stated that this equipment item is associated with the j following section of NUREG-0737. (This list of applicable NUREG-0737 sections has been identified by NRC as sections within the scope of this review): l II.8.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor ! Coolant and Containment . ! II.D.3 (ALL/1-1-81) Direct Indication of Relief and Safety Valve j Position j glGF),, YA [Of kb ' I il

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A NRC Contract N2. NRC-03-79-118 P g2 lb Franklin R:se:rch Cent:r FRC Project Na. C5257 A DMuon of The Frankhn Institute FRC Assignment No.13 lc 20th and Race Streets. Phila.. Pa 19103 (215) 448 1000 FRC Task No. 5// EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.el_I EQUIPMENT ITEM NO. 28 (TMI ACTION PLAN ITEM-ALL) ELECTRICAL CABLE LOCATED IN THE REACTOR AUXILIARY BLDG. ROCKBESIOS, MODEL NOT STATED REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 28 LICENSEE REFERENCE (S): 1391 FUNCTION (PLAlfr ID): ELECTRICAL DISTRIBUTION, TMI EQUIPMENI LICENSEE SUBMITTAL: SCEW(S): 14 0F 15 (15] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (Sto Section 3 of thia TER for Legend) R , T , ((t, RT, P, H, CS, A, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, f Not stated, No p ble LISTING OF A'PPLICABLE CHECKSHEETS: Contents checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a, OL, 2;, M Syst&m Consideration Review 4e, 15, 0;, Od, I-, 42 Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, 5f, 5,3 55 Ei, Oj Instelled TMI Lessons Learned Implementation 6a, eb Equipment Summary Maintenance and Replacement Schedule Summary 7a, 7L, 76

4 NRC Contract No. NRC-03-79-118 FRC Project N2. C5257 Pag 3 uCDu Frznklin Rrse:rch Csnt:r l A DMsion of Thi Frrnkhn Instituts FRC Asalgnment N2.13 lb 20th and Race Streets. Phda.. Pa- 19103 (215) 448 tmo FRC Task No. M ll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.Jf , i SIMMARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. The Licensee (has/has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions. g The Licensee has presented infcrmation which shows there are no outatanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment i Qualification testing of equipment in progress l Other ( ) ! The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. l The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

   - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)
 'lI.a Qualifiedl                                                   II.c Qualified Life Deficiency
 ~T b Modification                                                  III.a Exempt II.a Qualification Not Established                               III.b Not in Scope II.b Mot Qualified                                               IV    Documentation Not Available

s NRC Contract No.NRC 03 79118 0 Fr:nklin R:se:rch Ccnter FRC Project No.C5257 Pa08 A DMuon of The FrankhnInstuute FRC Assignment No.13 2 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTask No. M~ I f EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. df EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate __ Ad:quate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qunlified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Critaria Regarding Temperature / Pressure Exposures

 .       o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate i        o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Critsria Regarding Spray Satisfied Critcria Regarding Submergence Satisfied Crit 3ria Regarding Radiation , Satisfied Criteria Regarding Test Sequence Satisfied Critaria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Critaria Regarding Instrument Accuracy Satisfied Tact Duration Margin (1 hour .+ Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I)

DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified 1 I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.b Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available 1 I

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NRC Contract No NRC-03-79-118 00 Frs:nklin R: search Center FRC Project N2.C5257 Pa03 A D6vtsson of The Frankhn instituu FRC Assignment N2.13 50 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. Sti EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. _20 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW l Critarias DOR Guidelines  ; NUREG-0588, Cat. I1;NUREG-0588, Cat. II . NRCREQU$REMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR

         ,( DOR /0588-I/0iB8-II)                                       SUBMITTAL                       DOCUMENTATION            NOTE NO.)
                                                                    !                      ! Ei.tcra.icAt. CAet.E EQUIPMENT DESCRIPTION                                     !Et.zcranAc. !                                           !

Equipment Type  ! caste  ! EEhNSTR.UMW.NT/CONTR01. ! Manufacturer's thme !ROCKBESTOS I-I (5.2.2/-/-)  !  ! ROCKBE.STOS CO. g Model Nuraber (5.2.2/~/-)  !  !. FIR.EWAt.t. $  !

• 2/ce l4 I 5/c4PI4 l bsn ~G00V Faatures/ Mounting 2/CS I,b h !C'# b AWG'45mit 8FRJt.PE) e (5.2.6/-/-) 12/csM>l4 ! "S * *'"' 3ooV

                                                                    !3/cs 4 IG. !('/c# 1G AwG,20mu..FR,Xt.PE)                iNOTE.1
                                                                    !4ftsg.g lG !

g Connections /Intierfaces (5.2.6/-/-)  !  !-  !

                                                                    !                       ! Conra.ot.               600V   .

Location / Elevation  ! REACTOR  !(I/c,44'l2.AWG,30mu..M MN ! i

                                                                 ' ,A 1 Uytt.l ARY                                             .
                                                                    ! BulLOlN G E2t uipment ID No.                                                               g W.                                                  -!                      1,                                !

QUALIFICATION REPORT  ! l'  ! (8.0/5.0/5.0) , R:pcrt ID Number ' h '

                                                                    !       s
                                                                                's          !                  -             1 Rsport Date                                               !         %            !                                 !
                                                             '             ~
                       ,         ,                                  !                       !        's7    7 77             1 Ict?utd by             ' -
                                                                    !           \     T    !                                 !
                                       '                                   ~~

! .  !  ! RocKe'ESToS Co. ~

                                                  ~

l Prepared for s  !

                ., e             s
                                                                    !                       ! Rock.B ESTOS CO.               !
        , Referenced Reports                                        !      ~
                                                                                            !i    s
                                                                    .                       ! h ', NO                        .
         \                                                                 ~"~

, Qvalificaticx Method  ! 1-  ! l ((S.ir-5.3/(.1,2.4/2.1, 2.4) !  !' g p g .g d .T" I s s ,  !  !.  ! g)Kt.IFICATION TEST PROGRAM  !  !  !

       , hanctional Test Description !                                             =

• 5 minutc .OtELECTRtc,  !

        't5.2.5/2.2.9/2'.2.9)                                       !~   .
                                                                                       \    !WirHSTANL TEST. TAP             !
                                                                                            ! WATER, T.MMERStON              .
                                                                    !"             J
         .Opsrating Conditions                         '

f! , BO VAC/MT.t., g

                                                                    !              l                                         I

(-/2. 2.10/ 2. 2.10 )  ! GOO Nd*., 70 A (.PowtR.) Iotd/ Cycles / Voltage /  ! _  ! sCurrent/Freq. ,  !  ! 3OO VAC 22 A (INSTEumENh. p . s Goo VAC.130A (ConTnou') d; 2.::5 L= . . _.. . _ _ . f. . _ _ . _ _ _ ,

A NRC Contrat No. NRC-03-70-11 A 000F:nklin J Fr R: search Center FRC Project No. CS257 Pag]; FRC Aasignment NO.13

                                                                                                 ~

A Dwmon of The Franklin Institute

                                                                                                                       ' 5 t)
                                                                                                                        ~         ~

20th and Race Streets. Phda.. Pa. 19103 (215) 448 l @ 0 FRC Task No._511 _

                                                                                                                                        )

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQU?PMENT ITEM NO.:2:d. l NRC REQUIREMENTS DEFICIENCY*~ WITH SECTION REFERENCE LICENSEE QUALIYICATION (X,CR (DOR /0588-I/0588-II) SUBMITTAL DOCUMGTATION NOTE NO d ,,-

                                                    !              2
                                                                              ^

b Acceptance Criteria  !  ! Pass 80 VAc/ wit g 3g7 -! ( 5. 2. 5/2. 2.1/2. 2.1)  ! s!  !' Accuracy (5.2.5/-/-)  ! !NA -

                                                                                                        !                               i Number of Specimens                                 !              ! $ 7*EST SAFAPLC.S                  ! NOTE 2 1              1                                    :

Test Instruments Calibrated  !'l~MI- A F !  ! -'

                                                    !Es.ccTaicAt!                                       !             -

Safety Function (Active /  ! SER.Vt(f.  ! J , Passive) (-/2.1. 3/2.1. 3) . . g i Test Duration (5.2.1/-/-)  ! - Accident Duration (Envir.  !  ! . Above Normal) (5.2.1/-/-)  !  !.

• 1  ! ,,

Required Function Timat !LONG TMM! j~ - - Test Sequence (General)  !  !

                                                                    !T    [RAO/STm-yCHSP/              ', O 6.A M LES
                                                           ~

(5. 2. 3/2. 3.1/ 2. 3.1)  !

                                                    !              !       POST t.0cA 513t/ TAT 10N ; ( OTE 2.)

Test Sequence (NUREG-0588,  !  ! l  ; Cat. I) (-/2.5.1/-)  !

                                                            ~

1. Representative Sample  !  !

2. Baseline Data  !  !

3. Performance Extremes  !  !

4. Thermal Aging  !  ! .

5. Radiation Aging  !  ! *

6. Wear Aging  !  !  ;

7. Vibration / Seismic  !  !

8. DBE Exposure  !  ! I

9. Post-DBE Exposure  !  !  !

10. Inspection  !  !  !

^91"9

• I (5.2.4, 7.0/4.0/4.0)  ! -

                                                                    ! l3OO       HR.@ i50 *C./           -

Thermal Aging / Basis  !  ! 40 yr. @ oPFRATING  !

                                                     !              ! rEmPERATURE Or 90 C               !

Material Aging g g gg7g Evaluation (7.0/-/-)  ! - Materials Susceptible  !  !  !

                                                           ~

(Thermal) (5.2.4, 7.0/-/-)

                                                                    ,fINSULATING MATE.R.1ALS Radiation Aging, Type                               .              .                                   .

gamma

      #                                                                 NRC Contract No. NRC-03 79-118                  i F UO0hr%anklir. Rese:rch Ccnter                                     FRC Project No.C5257                       Page
 ;         ' A DMun of The Frankhn Institute                            FRC Asaignment No.13                        $C o           20th and Race streets. Phda.. Pa. 19103 (215) 448 10 @    FRCTask No. 511 7

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 2_,& ' NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0538-I/0 588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Padiction Aging, Dose (rd)  !  ! {Q,Q y {Q b  ! 1  !  !

     'Radiction" Aging, Dose Rate                         !                !                             !
                            ;                             1                1      O. (oE Mi-d/h          !

Rasinican Aging, Method  !  !  !

                                                          !                !        TEST                 !
     -Materialr. Susceptible                              !                !                             !

,, (Radiation) (5.2. 4, 7.0/-/-) !  !  ! Oparational Agtr3 1  !  ! (-/4.2/-)  !  !  ! Oth;r Age Conditioning  !  !  ! (-/4.2/-)  !  ! NO  ! Qunlified Life Claimed /  !  !  ! Estchlinhed (5.2.4/4.10/-)  ! No  ! 40 yr. /40 vr.  ! Normal Ambient Temperature  ! AmstENT  !  ! Normal Ambient Radiation  ! AmelENT  !  ! Norc:1 Ambient Humidity  ! AmelCNT j j

     ~On-Going Surveillance and                            !                !                             !

Ptsv3ntive Maintenance  !  !  ! (7.0/-/-)  !  !  ! On-Goiry Analysis of  !  !  ! i Failures and Degradation  !  !  ! l (7.0/-/-)  !  !  ! Margin (General)  !  !  ! l (6.0/3.0/3.0).  !  !  ! l  !  !  ! Margin (NUREG-0588,  !  !  ! Cct. I) (-/3.2/-)  !  !  !

1. Temperature (+15'F)  !  !  !

2. Pressure (+104,  !  !  !

10 psig max)  !  !  !

3. Radiation  !  !  !

(not required)  !  !  !

4. Time (+104, +1 hour  !  !  !

           + function time minimum)                         !                !                             !

l I

A NRC Contract No. NRC-03-79-118 000b nklinResearchC:nter FRC Project Nr.C5257 ' A DMoon of The Franklin Inurtute FRC Assignment No.13 5d 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. _ 5li EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS 1  !  ! IDCA/MSLB/HELB/ Uncontrolled !  ! ' (4.1, 4.2, 4.3.1, 4.3.3/

                                                    !wu             !      L O C.A                  i 1.1, 1.2, 1.5/1.1, 1.2, 1.5) !                                    !                               !

Radiation Type jGm j 6A M A. [ Radiation Dose (rd)  !  !  ! (4.1.2/1.4/1.4)  ! 2.Ox10g  ! i.5x 10 8 rd  ! Radiation Dose Rate (rd/hr')  !  !  ! Radlation Qual. Method  ! -  ! O.8 Mrd/h  ! (5.3.1/-/-)  !  !  ! Proximity to Concentrated  !  !  ! Radiation  !  !  ! ( 4.1. 2/1. 4. 6/1. 4. 6)  !  !  ! Equipment Susceptible to  !  !  ! Beta Radiation (4.1.2/-/-)  !  !  ! Radiation Dose (Normal + 1  !  ! Accident) (4.1.2/-/-)  !  !  ! Plateout Dose Considered  !  !  ! (-/1. 48/1. 4 8)  !  !  ! Gamma + Beta Dose (rd)  !  !  ! ( 4.1. 2/1. 4. 7/1. 4. 7)  !  !  !

NRC Contract No. NRC-03 79-118 phr:nklin UO0 R:se:rch Center FRC Project No.C5257 Pag 3 A Divtsson of The Franidin Insntute FRC Assignment No.13 5e 20th and Race Streets. Phde . Pa. 19103 (215) 448-1000 FRC Task No. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 20 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIROMENTAL PROFILE 1  !  ! OF ACCIDENT CONDITIONS  !  !  !

                                                 !                 ! 140 - 3.4G /O- il3         1 Ra t-   cf Temp./ Press.                          !                 !        IN L 6 MIN.         !

Incr00se  !  !  ! e e e Pock 'F/psig/RH/ Time , 346[113 / loo /5 HR. e e e Decrocse To: 'F/paig/RH/ Time 335/q3/ioO/3 aR i e e Decrocse To: 'F/psig/RH/ Time , 315/G9/100/4 HR k' Decrocse To *F/psig/RH/ Time !  ! 266/2.6/100/81 HR.  ! Equipment Surface Tempera-  !  ! I turo (MSLB) (-/1.2.5.C,  !  ! 90*C  ! 2.2.6/1.2.5.C, 2.2.6)  !  !  ! Specy Qualification Method  ! I (5.3.2/1.3, 2.2.8/1.3,

                                                                   ! SimuLT ANEcuS T"EST 2.2.8)                                            !                 !                            !

Sprey Composition  ! i H 3BO , 33000 ppm ECRON (4.1.4/1.3, 2.2.8/  ! H@O3  ! pH - 10 5 -

1. 3, 2. 2. 8) !NaOH  !  !

Sprcy Density (gpm/f t 2) . . O.15 f Spray Duration 2.4 HR Submergence Durati'on  !  !  ! ( 4.1. 3/2. 2. 5/2. 2. 5)  !  !  ! In-Le:kage Considered  !  ! NO  ! (5.2.6, 5.3. 2/-/-)  !  !  ! Time to Submergence  !  !  ! Duct Environment  !  !  ! (-/2.2.11/2.2.11)  !  !  !

A NRC Contract No. NRC-03-79-118 Pag] 000hr:nklin R: search Ccnter FRC Pro}ect No. C5257 A Division of The Frankhn Instatuu FRC Assignment N3.13 5f 20th and Race Streets. Phila.. Pa. 19103(215) 448-1000 FRCTask No. 511 EQUlPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 28 wrzs:

1. TL o ng,a, -b obo nn rto encre; Jno -hto.2 "

b-hmn n o, mdDM _0 m r.EEE, sTo. 3 83-

     %                                           G                                           c 74 (TAetE.1).                                                                   -

2. Tam A n3 en0A gnm (A,B a d C)

    .neut                  dodo SL _                 Ear L Aoi errudo-h41 oE.                                tum-
          ~                                                                                          B 10 n                    h m e A > . o.6               c210Au. Ta h ._um u . nodM s                                                                           -g b                                   <                 i cm.                      L          A , a cuvv0 C.                                        &c- MA n                 aan+,                         c-wm -

t  % A-enmeman 40 yc. noruan .0 L0 e E B - Lo C A 3sh Jm J m ata00e;D ._Ol m C - LO CA an.nh, jm innta%D be - 4 - R.co a n c m .c, b > t. u e u ; n.ubicbuO; ic- n meO; m . l . n nom 4) n m. 8 0 v A t / n o t. A r.e. M & - h m K )> duJ A a er mXiamc_o; . u.dik. r kEE sto 3 BS l autom 2 . 3 . 3 . 4-l T1o LOCA mbnto, m a ort 0 m m ) 1 M b

  <ib,        ca_OrQ_e.           ama.nitAuG ct3 vtrch20 AroQ tLo3J osvuO; e scrowerd. .

T.An- B anfrve bo ao un. a Mo muD l

                                                                      -i rtr a m. n o tRt' M

! 10 0 co cy n+ 200 F afrf) 100% r-k, ome con cate;O l l GMA SA,, A e O_b t (3) c -% t 0

A NRC Contract Nr. NRC-03-79-118 1b nklinR:se:rchCanter FRC Project No.C5257 Page A DMs6on of The Frankhn insatuu FRC Assignment N .13 60 20th and Race Screets. Phile.. Pa. 19103 (215) 448 1000 FRC Task No. /I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.M 4 INSTALLED TMI LESSCNS LEARNED IMPLEMENTATION EQUIPMENT

SUMMARY

NRC requested an evaluation of the environmental qualification of safety-1 rolcted electrical equipment located in harsh environments required for TMI Le sons Learned Implementation. The objective is to evaluate qualification documentation of equipment within the scope of IE Bulletin 79-01B, Supplement 3 (item 2), 'in accordance with criteria established-by the NRC (see Section 2 of this report) in a manner identical to the evaluation of all other safety-rolated electrical equipment. The scope of this review is limited to TMI j Acticn Plan equipment associated with specific sections of NUREG-0737 which hnve cn instiallation implementation date of January 1,1981 (sections are id:ntified below) . Where applicable, a review is to be performed on installed equipment with implementation dates after January 1, 1981 if adequately idsntified by the licensee. - This plant is a PWR d , BWR . The NSSS Vendor is Westinghouse (W)1, Babcox & Wilcox (B&W) , Combustion Engineering (CE) , General Electric (GE) .

 ,  With respect to this equipment item, it is noted (applicable section checked):

The Licensee does not provide adequate information with respect to identification of TMI Action Plan equipment installed as of 1/1/81. The Licensee has not provided the correlation of this equipment item with the specific sections of NUREG-0737. [The correlation is needed to ensure that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan ites, are the cable and the terminal blocks associated with the device also identified?] The Licensee has not provided the approximate installation date for the TMI' Action Plan equipment items so that the appropriate qualification criteria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. j The Licensee has provided a standard Owners' Group position with respect I to a NUREG-0737 technical area. l The Licensee has requested extensions of implementation dates. The Licensee has stated that this equipment item is associated with the following section of NUREG-0737. (This list of applicable NUREG-0737 ccctions has been identified by NRC as sections within the scope of this rcview): II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment II.D.3 ( ALL/1-1-83 ) Direct Ir.dication of Relief and Safety Valve Position .

          $W                                                 T/*1.5 f f        ^^^  - i?

  /M                                                          NRC Contract N;. NRC-03-79-118 Pag 3 LOOU Frsnklin Rese:rch Centu                              FRC Project N2. C5257 A Dwiwa o The Fr nklin Institute                       FRC Assignment NP,13                         la 20th and Race Streets. Phila . Pa 19103(215) 448 1000  FRC Task No. 6/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM EQUIPMENT ITEM NO. 29 (TMI ACTION PLAN ITEM-ALL)

ELECTRICAL CABLE LOCATED IN THE CONTAI!NENT SAMUEL MOORE, THERMOCCUPLE EXTENSION REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 29 LICENSEE REFERENCE (S): 677 FUNCTION (PLANT ID): ELECTRICAL DISTRIBUTION, TMI EQUIPMENT LICENSEE SUBMITTAL: SCEW(S): 15 0F 15 [15] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLY: (See Section 3 of this TER for Legend) R, T, (r, RT, P, H, CS, A, S, (R), M, I, QM, MN, EXN, SEN, QI, RPS, None, 1 Not stated, No p le LISTING OF APPLICABLF. CHECKSHEET_S: Contents checksheet Page No. l l Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Licensee Response to NRC SER 3a , 2'.,

                                                                                        . 2u, 2d A=       'r, id, 0;, 'f System Consideration Review

Equipment Environmental Qualification Review Sa, 5b, Sc, 5d, Se, 5f, h, %, Si,g Si z

, Installed TMI Lessons Learned Implementation G a , ditr l Equipment Summary l Maintenance anc Replacement Schedule Summary  ?:, 75, ?c

i I AUO0hr:nkhn R:sesrch Crnter NRC Contract Nr. NRC-03 79-118 FRC Project No.C5257 Page A DMoon of The Frankhn Instaurs FRC Assignment N3.13 lb 20th and Race Streets. Phda.. Pa. 19103 (215) 448-m FRC Task No. CH t EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .mL9 l

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: Tne Licensee (has/has not) provided a response to the SER concerns. The Licensee (has/has not) specifically stated that the equipment is qualified and/or will function when exposed to the applicable DBE environmental service conditions.

                                                                                                                            ~

d The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. - Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source l Verify qualification by additional (testing / analysis) 1 Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification cnd/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

      - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified I.b Modification __ KI.c QualifiedLifeDeficiench III.a Exempt II.a Qualification Not Established III.b Not in Scope II .b Not Qualified IV Documentation Not Available - _- ___.____ev_w_=_._h-- -

                                              '-e re me-+ t - -   e *-****----W-        * - * - * * " " - - ~ - ' * = - - - * " " " * ' * ' * ' ' " ' - " - ' ' ' -   ~ ' ' ' ' '

A NRC Contract No. NRC-03-79-118 Page l!00hFr nklinR:searchCcnter FRC Project N2, C5257 A De of The FrankhnInstitute FRC Assignment N2.13 2 2(kh and Race Streets. Phda.. Pa. 19103 (215) 44810m FRC Task No. f# I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. SLp EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate , Adequate Similarity Between Equipment and Test Specimen Established ' Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Criteria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Criteria Regarding Submergence Satisfied Criteria Regarding Radiation Satisfied Criteria Regarding Test Sequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Test Duration Margin (1 hour + Function Time) Satisfied Criteria ?egarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification II.a Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified X III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available

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(2) To be utilized during Tt!I-2 accident scenario per procedure :E g9z (3) See accident profile - Temperature - Figure 3.1.1 no m j (4) See accident profile - Pressure - Figure 3.1.2 In containment radiation g 4 g (5) Radiation exposure split level established for purchase of component c y into two parts - half before LOCA simulated environment and half af ter 5 g g m o. Z

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NRC Contract N3. NRC-03-79-118

                @DDUr nk!!n Reserrch Center U                                                                     FRC Project No. C5257                                    Page A D6vmon of The Frankhn Instituts                            FRC Assignment No.13                                        5a 20th and Race Streets. Phda . Pa. 19103(215)448 tm           FRCTaskNo. 81I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. .si!.9 EQUIPMENT ENVIROletENTAL QUALIFICATION REVIEW Criteria: DOR Guidelines                                  ; NUREG-0588, Cat. I2_;NUREG-0588, Cat. II                                  .

NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) EQUIPMENT DESCRIPTION  !

• Equipment Type  ! /L4I 1 Electrical Cable  !

                                                                         ! M                  !                                  !

Manufacturer's Name !A - -4  ! Samuel Moore and Company ! (5.2.2/-/-) .%- - " ().  !  ! Model Number (5.2.2/-/-) 1 / a >AJ! See Note 1 Pages 511 & Sij

                                                                         !4 / /'              !                                  !

Serial Number  ! /0  ! Not Applicable  ! tur unting M Trade Name - DEKORON Connections / Interfaces h k Not Stated (5.2.6/-/-)  !  !  !

                                                                         !          ,      ,1 Location / Elevation                                     ! Q ;        .

efNot Stated (wound on f* Equipment ID No.

f. f.MandrelinAutocalve)

Not Applicable f QUALIFICATION REPORT  !  !  ! (8.0/5.0/5.0)  !  !  ! Report ID Number

                                                                         ' NC3&(3                 F-C3683 f

Report Date

                                                                         ! f//73              . November 19/3

• Issued by  ! p#  ! Franklin Institute  !

                                                                         .                    1Research Laboratories            !

Prepared for Samuel Moore and Company f S. No m G. *

                                                                                              *Dekoron Division Referenced Reports                                                                                              I
                                                                           )7j                .Not Stated Qualification Method                                     !                    ! Sequential Test                 I (5.1, 5. 3/2.1, 2. 4/2.1, 2. 4) !                             M              !                                 !

QUALIFICATION TEST PROGRAM  !  !  ! Functional Test Description !gg  ! 1 Visua1 Inspeetion/ (5.2.5/2.2.9/2.2.9) 1 g

                                                                         !                    ! Insulation Resistance           !

Operating Conditions  !  !  ! (-/2.2.10/2.2.10) !y  ! Not Stated  ! Ioad/ Cycles / Voltage /  !  !  ! Current /Preq.  !  !  ! . ~ _ . _ . - _ _ - . . . _ _ . _ _ . _ _ _ _ _ _ _ _ . _ _ _ - _ . . , _ _ _ - - _ - _ . _

Q~ UQ0Er:nklin R: search C:nter NRC Contract No. NRC-03-79-118 FRC Project No.C5257 Page A Dien of The Franklin Institut2 FRC Asalgnment No.13 5b 20th and Race Streets. Phila.. Pa. 19103(215) 448 1 2 0 FRCTask No. 6II EQUIPMENT ENVIRONMENTAL QUALIFIL.ATION REVIEW OF EQUIPMENT ITEM NO.d NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Acc:ptance Criteria  !  ! (5.2.5/2.2.1/2.2.1)  ! p g ! Provided! No Specific Criteria  ! Accurccy (5.2.5/-/-) . . Not Applicable . Number of Specimens f / !/l/. h 7 1  !  ! Tact Instruments Calibrated ! g . ,/9 .  ! Yes  ! S2foty Function (Active /  ! ' Paccive) (-/2.1.3/2.1.3) 1  ! Cany Cunent g Test Duration (5.2.1/-/-) g.f4

                                                                      ,f30 Days                    f Accidant Duration (Envir.                          1 7l             !

Not Applicable Abova Normal) (5.2.1/-/-) . Required Function Time  ! f . T;ct Sequence (General)  !  ! g, g ( 5. 2. 3/2. 3.1/ 2. 3.1) f fResistance *

                                                         /Fg               ema Aging Test Sequence (NUREG-0588,                                                                       {

Cct. I) (-/2.3.1/-)  !  ! Irradiation ,

                                                     ,                , LOCA Simulation            ,

1. Representative Sample  !  ! Trradiation  !

l 2. Baseline Date  !  ! Inspection  ! ! 3. P0rformance Extremes  !  !  !

4. Thermal Aging  !  !  !

5. Radiation Aging  !  !  !

l 6. W;ar Aging  !  !  ! l 7. Vibrat. ion / Seismic  !  !  !

8. DBE Exposure  !  !  !

9. Post-DBE Exposure  !  !  !

10. Inspection  !  !  !

Aging  !  !  ! (5.2.4, 7.0/4.0/4.0) !M  ! 7 days @ 250'1 !X Th rn.cl Aging / Basis  !  ! Basis Not Stated 1/f/M A Matorial Aging  !  !  ! Evcluttion (7.0/-/-) . Not Stated ' Matorials Susceptible !p  !  ! l (Th:rmal) ( 5. 2. 4, 7. 0/-/-)  ! M! Not Stated g Radiction Aging, Type  ! Ga:::ma  ! 8 l

A NRC Contract No. NRC-03-79-118 t!0fjiFr2nklin Rrsench Center FRC Project No. C5257 Page A Dwision of The Frrnkhn Instnuu FRC Asaignment N2.13 $C l 20th and Race Streets. Phila. Pa. 19103(215)448-13 2 FRC Task No. Til l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d2 9 NRC REQUIREMENTS DEFICIENCY I WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Radiation Aging, Dose (ed) M 100 Megarads Radiation Aging, Dose Rate !ss4.uaje4[ht 1 to 1.5 Mrd/hr Radiation Aging, Method  ! gg ,  ! Test  ! Materials Susceptible  !  ! Not State'd  ! (Radiation) (5.2.4, 7.0/-/-) . . . Operational Aging  !  !  ! p' (-/4.2/-)  !  ! Not Stated 3 1  !  ! Other Age Conditioning  ! M.  ! Not Stated (-/4.2/-) 1  ! 3 Qualified Life Claimed /  !  !  ! Established (5.2.4/4.10/-)  !  ! Not Stated 3 1  !  ! Normal Ambient Temperature  ! f f f a/' ,4g ,! Not Applicable I Normal Amoient Radiation !p ., 4! Not Applicable Normal Ambient Humidity p,

• Not Applicable On-Going Surveillance and  !  !  !

Preventive Maintenance ' N5  ! Not Applicable (7.0/-/-) .  !  ! On-Going Analysis of  !  !  ! Fa 1 s and Degradation '

                                                                                                            /M          fNotApplicable
                                                                                                                        ,                          f 1                 !                          !

Margin (General)  !  ! Not Stated I (6.0/3.0/3.0)  !

• Margin (NUREG-0588,  !  ! Not Stated

Cat. I) (-/3. 2/-)  !  !  !

1. Temperature (+15*F)  !  !  !

l 2. Pressure (+104,  !  !  ! 10 psig max)  !  !  !

3. Radiation  !  !  !

(not required)  !  !  ! l 4. Time (+10%, +1 Mur  !  !  !

                                                         + function time minimum)                      !                 !                          !

A NRC Contract No. NRC 03-79118 (DDE,nuiina.1,csccni., U FRCProi ctNo.Csasy Page A Division of The Franklin Insettute FRC Assignment No.13 5d 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRCTask No. fil EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J 9 NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS  !  !  ! IDCA/MSLB/HELB/ Uncontrolled !  ! ' (4.1, 4.2, 4.3.1,'4.3.3/  ! d LOCA / MSLB l 1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) !  !  ! Radiation Type  ;;z ,r Gamma Radiction Dose (rd)  ! 1 100 to 130 Mrd I (4.1.2/1.4/1.4)  ! ,y y jg 7  ! !gA 3 Radiation Dose Rate (rd/hr')  !  ! 1 to 1.15 Mrd/hr  ! Radiction Qual.' Method  !  !  ! (5.3.1/-/-)  !  !  ! Proxicity to Concentrated  !  !  !

                                                     ! / g / Y 7 ~/ !! Not Applicable Radiction                                          !                                           1 (4.1. 2/1. 4. 6/1. 4. 6)                                                                      !

Equipment Susceptible to !M  ! Not Stated I Beta Radiation (4.1.2/-/-)  ! ' Radiction Dose (Normal + .'! M. p

                                                                >pd !Not Applicable I

Accid 3nt) (4.1.2/-/-) .r .  ! Picteout Dose Considered  ! )#s _ D! b '~ ~' ! Not Applicable (-/1. 4 8/1. 48)  ! g Gaiana + Beta Dose (rd) 1 1 1 (4.1.2/1.4.7/1.4 7)  !  ! Not Applicable  ! 7

d

#A                                                            NRC Contract No, NRC43 79-118 FRC Project N2. C5257                     Page 000hr:nklin R:se:rch Center A Dmson of The Frankhn insatuti                         FRC Assignment NO.13                       5e 20th and Race Streets PMa . Pa 19103 (215) 448 1 2      FRC Task No. ft/

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /9588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE No.) ENVIRONMENTAL PROFILE'  !  !  ! OF ACCIDENT CONDITIONS  !  !  ! Rate of Temp./ Press.  !.24.r*/C ;4pi 25'F;7.5' Psi / second Increase f PaaA: 'F/psig/RH/ Time y[y.t//ref24* 340/105/100%/3 Hrs f. Decrease To: 'F/psig/RH/ Time 'ot./f/.1o[/j2f A{ 320/75/100%/3 hrs [ Dacrease To: 'F/psig/RH/ Time / fA/.T h 250/15/100%/ 3.75 Days Decrease To 'F/psig/RH/ Time

• 200/0/100%/26 Days f

Equipment Surface Tempera-  !  !  ! ture (MSLB) ' (-/1. 2. 5.C,  ! M  ! Not Stated I 2.2.6/1.2.5.C, 2.2.6) 1 1 1 Spray Qualification Method  ! jt/g  !  ! (5.3.2/1.3, 2.2.8/1.3,  !  ! Test g 2.2.8) 1  !  ! Spray Composition h/ . 2000 ppm Boron as Boric (4.1.4/1.3, 2.2.8/

1. 3, 2. 2. 8)

                                              !p g,7 g j j !, Acid buffered with Na0H         -
                                                         , .3         to a pH of 9 to 11       j spray Density (gpm/f t 2)                                           ! 0.15 Spray Duration                                  'M                        30 Days

{ Submergence Durati'on ' ' I ( 4.1. 3/2. 2. 5/2. 2. 5) . 2

                                                                    , Not Applicable          f In-Leakage Considered                                                 Not Applicable (5.2.6, 5.3.2/-/-)                             !                    '

{ Time to Submergence k ,Not Applicable Dust Environment IM f,W ! Not Applicable I (-/2. 2.11/ 2. 2.11)  ! 8~~ ~ ! I

s NRC Contract No. NRC-03-79-118 phr:nklin LO0 R:sersch Ccnter FRC Project N2.C5257 Pago A DeWon of The Frankhn Institut2 FRC Assignment N2.13 5f 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. S /l l l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. Af. NOTES: Note 2. The Licensee has not nrovfdod any pun 1nneinn nf Aga related degradation nor estimnted the ann 14ffad lif nf thfe equipment. Note 3. The total test dose consista of cha aging Anea af inn v.a plus the accident dose of 100to130 Mrd fnr n enen1 nf ?nn en 97n v a The Licensee SCEW sheet provides a snecifiad Anaa nf ? vin 8 ,w4,n is in excess of any of the radiation dose vninaa nenvidad in tha table of doses calculated for Robinson Plant . Tha Tnbla fa ranenAne=A in Appendix A of the TER,

Conclusion:

The cited test report envelopes all of the 11 canaan provided environmental conditions with the excention of nga valaead degradation. Therefore the equipment is assinned to catocorv TTc_

                            &                                                                          NRC Contract No NRC 03-79-118 FRC Project No. C5257                 Page UOOU Fr::nklin Research Ccnter A Division of The Frankhn inwause                         FRC Assignment No.13                   Si, 20th and Race Streets. Phde.. Pa. 19103 (215) 448-1000    FRC Task No. S//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. A 9 NOTES:

2. SAWl.E IDENTIFICATION Conductor Nos.

Sample Number or Color

• Description -

1 Eed and Yellow Samuel Moore and Company Type 1902 - 636 16 gauge solid thermocouple wire 30-mil EPDM I insulation, 15-m11 Hypalon I conductor Jacket 45-mil Hypalon I overall jacket 2 klack and White Samuel Moore and Company Type 1952 - 686 16 gauge 7-strand tinned copper conductors 30-mil EPDM I insulation, 15-mil Hypalon I conductor jacket 45-mil Hypalon I overall jacket 3 Elack and White Samuel Moore and Company Type 1952 - 686 16 gaugo 7-strand tinned copper conductors 20-mil EPDM I insulation, 10-mil l Hypalon II conductor jacket 45-mil Hypalon II overall jacket 4 1 and 2 Samuel Moore and Company Type 1952 - 686 16 gauge 7-strand tinned copper conductors 30-mil EPDM II insulation, 15-mil Hypalon II conductor jacket 45-mil Hypalon II overall jacket l l i ( l l

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

NRC Contract No. NRC-03-70118 FRC Project N 3.C5257 Page LUDGr:nklin R: search C:nter A Divmon oiThe Franklin Institute FRC Assignment No.13 Sis 20th and Race Streets PN!a.. Pa 19103 (215) 448 1000 FRC Task No. 6 /I 2 EQUIPMENT ENVIRONMENTAL QUALIF! CATION REVIEW OF EQUIPMENT ITEM NO. s2.g NOTES: Conductor Nos. Sample Number or Color

• Description 5 1 and 2 Samuel Hoore Splice and Repair Evaluation Cable A. Single Splice No. I-Self-fusing

                                                  ,.                   EPDM Scotch Electrical tape
                                                                       #23     -

B. Single Splice No.II-Polyimide-silicone Scotch Electrical tape #92 C. overall Jacket repair - Samuel Moore Hypalon repair tape 6 combination 4 pair special bundle. Silicone Tubber-fiberglass fire barrier tape. 60-mil Hypalon I overall jacket. Individual Fairs: 1 and 2 15-mil EPDM I, 10-mil Hypalon I on 20 gauge JX thermocouple wire 3 and 4 20-mil EPDM I, 15-mil Hypalon I on 18 gauge 7 strand tinned copper conductors 5 and 6 30-mil EPDM I,15-mil Hypalon I on 16

               .                                         gauge 7 strand tinned copper conductors 7 and 8       20-mil EPDM I, 10-mil Hypalon I on*16 gauge 7 strand tinned copper conductors 7                                conibination 4 pair special bundle.

Asbestos-glass fire barrier tape. 20-mil Hypalon I pair jacket. 60-mil Hypalon I overall jacket. Individual Pairs: 1 and 2 15-mil EPDM I,10-mil Hypalon I on 20 gauge JI thermocouple wire 3 and 4 20-mil EPDM I,10-mil Hypalon I on 16 gauge, 7 strand tinned copper conductors 5 and 6 20-mil EPDM I,15-mil Hypaion I on 13 gauge, 7 strand tinned copper conductors 7 and 8 20-mil EPDM I,10-mil Hypalon I on 16 gauge 7 strand tinned copper conductors All cable lengths were approximately 35 ft.

i gp NRC Contract No. NRC 03-79118 Page UUIlU Fr nklin R: search Ccnter FRC Project No.CS257 A DMe6on of The Frankhn Insmuu FRC Assignment 10.13 60 20th and Race Serests. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. O ll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d:$ INSTALLED TMI LESSONS LEARNED IMPLEMENTATION EQUIPMENT SLBOGARY NBC requested an evaluation of the environmental qualification of safety-related electrical equipment located in harsh environments required for TMI Lessons Learned Implementation. The objective is to evaluate qualification ! documentation of equipment within the scope of IE Bulletin 79-013, Supplement 3 (item 2) , in accordance with criteria established-by the NRC (see Section 2 of this report) in a manner identical to the evaluation of all other safety-related ' electrical equipment. The scope of this review is limited to TMI Action Plan equipment associated with specific sections, Jf NUREG-0737 which have an instiallation implementation date of January 1,1981 (sections are identified below). Where applicable, a review is to be performed on installed equipment with implementation dates after January 1, 1981 if adequately identified by the licensee. I This plant is a PWR N , BWR . The NSSS Vendor is Westinghouse (W)g, Babcox & Wilcox (B&W) , Combustion Engineering (CE) , General Electric (GE) . With respect to this equipment item, it is noted (applicable section checked): The Licensee does not provide adequate information with respect to identification of TMI Action Plan equipment installed as of 1/1/81. The Licensee has not provided the correlation of this equipment item with the specific sections of NUPEG-0737. [The correlation is needed to ensure i that all items are included in the review, e.g., if a transmitter is identified as a TMI Action Plan item, are the cable and the terminal blocks associated with the device also identified?] The Licensee has not provided the approximate installation date for the TMI' Action Plan equipment items so that the appropriate qualification criteria (NUREG-0588 or DOR Guidelines) can be used in the EEQ evaluation. The Licensee has provided a standard Owners' Group position with respect to a NUREG-0737 technical area. The Licensee has requested extensions of implementation dates. . g The Licensee has stated that this equipment item is associated with the following section of NUREG-0737. (This list of applicable NUREG-0737 sections has been identified by NRC as sections within the scope of this review): II.B.3 (ALL/1-1-81) Post-Accident Sampling Capability of Reactor Coolant and Containment II.D.3 ( ALL/1-1-81) Direct Indication of Relief and Safety Valve Position

1. ax.L T/e- qf?dn TmZ a= M 491%.

  /%                                                           NRC Contract N3. NRC-03-79-118 l.0 ! Fr:nklin R:seirch Csntir                               FRC Project N2. C5257                    P ga A Dwisson of The Frankhn Institute                     FRC Assignment No.13                      lc 20th and Race Streets. Phila.. Pa 19103(215) 448 1000  FRCTask No. S//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.dd_ EQUIPMENT ITEM No. 30 ELECTRICAL CABLE SPLICE LOCATED IN THE CONTAINMENI, ELEV. 234'-246' RAYCHEM, MODEL NOT STATED REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET No. 30 LICENSEE REFERENCE (S): 815 FUNCTION (PLANI ID): SINGLE CONDUCTOR AND MULTICONDUCTOR CABLE SPLICING LICENSEE SUBMITTAL: SCEW(S): 24 0F 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITEM (S) ONLYI (S:o Section 3 of this TER for Legend) QT, RT CS A, S, (R), M, I, QM, RPN, EXN, SEN, QI, RPS, None, l Not otated, Not applicable-LISTING OF APPLICABLE CHECKSHEETS: Cnnt"nts Checksheet Page No. Equipment Item la Summ ry of Licensee Responset to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Lic2nsee Response to NRC SER 3a , 3 b , Sc. --3d Systcm Consideration Review 1e, 4w, be io, 9e, 55 Equipment Environmental Qualification Review Sa, Sb, Sc, 5d, Se, 5f, 59y-sh,5j,6:*g Inntclied TMI Lessons Learned Implementation 5- , L Equipment Summary Maintenance and Replacement Schedule Summary -7a, ?b. "'r

NRC Contract Nr. NRC-03 79-118 pb.r:nklin Riserrch Canter FRC Project N3. C5257 Pag] A DMson of Th2 Frtnkhn Instituti FRC Assignment No.13 lb 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. SII EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.d.Q SUetMARY OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: [ Tne Licensee (has/;m ..e t) provided a response to the SER concerns. g The Licensee (has/h:2 =ct) specifically stated that the equipment is qualified andge will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. Corrective action specified by the Licensee: Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source verify qualification by additional (testing / analysis) Equipment relocation to a mild environment Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. The Licensee (has/has not) provided a schedule for the proposed j corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

 - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified lII.c Qualified Life Deficiencv] i I.b Modification III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available

NRC Contract NJ. NRC-03-79-118 POD L #r:nklin Research Ccnter FRC Project No. C5257 Page A Divmon of The Frankhn Instuute FRC Assignment No.13 2 20th and Race Sweets Phda.. Pa. 19103 (215) 448 1000 FRC Task No. f II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.J0. EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM 1 I DESIGNATION: NRC REQUIREMENTS X = DEFICIENCJ Documented Evidence of Qualification Adequate Adequ te Similarity Between Equipment and Test Specimen Established Aging Degradation Evaluated Adequately 1 Qualified Life or Replacement Schedule Established (If Required) Y Progtr:2 Established to Identify Aging Degradation Critoria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposures o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately I o Steam Exposure (If Eaquired) Adequate l CritOria Regarding Spray Satisfied Critoria Regarding Submergence Satisfied Critoria Regarding Radiation Satisfied Critcria Regardin) Test Sequence Satisfied Critcria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Criteria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tact Duration Margin (1 hour + Function Time) Satisfied _ Critcria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.0 Equipment Qualified I.b Equipment Qualification Pending Modification II.e Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirement.J Except Qualified Life or Replacement Schedule Justified X III.c Equipment Exempt From Qualification III.b Equipment Not in the Scope of the Qualification Review IV Documentation Not Made Available (6 5 . l

NRC Contract No. NRC-03-79-118 000 Fr:nklin Research Center FRC Project No.C5257 Page l A Dwwon of The Franklin Institute FRC Assignment No.13 3a 20th and Race Streets. Phde.. Pa. 19103 (215) 448 1000 FRC Task No. S1l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. d_d LICENSEE RESPONSE TO NRC SER l 4.2 Youiement Recuiring Additional Information and/or Corrective Action (Accendix 3) 0b ' The bulk of master list equipment was placed in this categorv and our review of deficiencies is based upon the following: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated yebruary 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, CA, and reported in Environmental Qualification of Safety-Related Electrical Equipment IE3 79-013. Technical Evaluation Report

                      - Docket No. 50-261; Plant:                     H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al.

       "quipment reported as qualified within NRC TER Revision 1, dated November 11, 1980:

Ecutement Seserietion Manufacturer Model No. Location 13.cablesplicesj Raychem ibOO-12N containment

14. cable splices- Rayche: 500-12N contain=ent

15. cable splices- Raychen 300-12N containmen:

16. cable splices- Raychen 200-12N containment

17. cable splices- Rayche: 115-6N containment

18. cable splices ,

Rayche: 070-6N contain=ent

19. cable terminais- A 9. 53548-1 centainment and splices

          ,'These items also included 4                   -'

• Md Wa M estion test 31, Qualificatten 7,3 p.,33 333g7, o supply acceptable aging, ra 13:te.
• and *CCA :est da:a c ,, ,. e 3 '
• A. Cable Splices RaycheN 1hc-12 ,

                                                                                           -        R.T.R.,P,H,CS,A A. Cable Splices                      Raychem                     500-12N              1        R,T,RT,P,H,CS,A A. Cable Splices                     Raychem                     300-12N              1        R,T,RT,P.H,CS,A A. Cable Solices                     Raychem                     200-12N              1        R,T,RT,P,H,CS,A A. Cable Splices                     Raychem                     115-6N               1        R,T,RT,P,H,CS,A A.   ~ Cable Solices                     Raychem 070-6N                1       R ,T_, RT , P. , H , CS , A ,
   ^!: ems reported as qualified within NRC Region II revised TIR, dated 11/7/80.                                               l l

NRC Contract No., NRC-03 79-118

  @d.

uu Frankhn Research Center FRC Project No. C5257 FRC Asalgnment N ^.13 Page A Dwon of The Frankhn Institute 3b 20th and Race Streets. Phda.. Pa. 19103 (215) 448-1000 FRC Task No. 811 EEUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.JD 3.2.5 Cable Terminals and splices g.- As no qualification information could be obtained on the , current in containment cable splices to the listed electrical equipment, it was decided to change out the splices with qualified co=ponents, prescr! bed tools and approved procedure. This changeout was co=pleted during the plant refueling outage (August - October) 1980. Individual conductor splices will utilize AMP Radiation Resistant /150 C Preinsulated Splices (#53548-1), T&B 2-way Cable Connectors for Copper Cable, 500 MCM and T&B 2-way Cable Connectors for Copper Cable, #9 AWG. The splice / connector component will be cri= ped to the designated conductors using the manufacturer's specified crimping tool. . An appropriate sized RAYCHEM SHRINK TUBING will be applied over the individual conductor cable splice and heat shrunk using the manufacturer's specified torch. For the two- (2) and three- (3) conductor cables after the individual conductors are spliced using AMP PlDG (53548-1) splices, an overall jacket RAYCHEM SHRINK TUBING will be applied and heat shrunk. The work described above has been detailed within H. B. Robinsen S.E.P. Modification and Setpoint Revision Form No. M-521 (revised) and will be the means to sign off the completed work. Original splices specified as AMP Muclear Preinsulated Environ =entally Sealed Splices (#52979) were found to be incompatible with the conductor insulation thickness of installed cable. Therefore, another butt-splice component, AMP Radiation resistant /150 C preinsulated splice (#53548-1)'vas ordered and installed. AMP Qualification Test Report 110-11002 dated October 1, 1978 describegaprogramthatincludedtotalradiationexposureof 2.0 x 10 RADS, maximum temperature of 350 F, maximum pressure of 137 PSIA and a borated chemical spray lasting four (4) days. To assure qualification of the H. B. Robinson in-containment splices, cable undergoing testing at Wyle Laboratories l will be connected with AMP PILG terminals Raychem thermofit (. heat shrink) tubing overall per the Installation Procedure M-521, Safety-Related Cable Splices Inside Containment. Appropriate i matrix combinations of splice / cable and individual cables and ! splices will assure identification of any single component failure which could occur during qualification testing. Each co=ponent has sufficient c. ..acturer-supplied test data to assure qualification by analytical = cans. The opportunity to R2 obtain actual test results is available and will be used. 1

A NRC Contract No. NRC-03 79-118 Page 000Fcnklin Research C:nter FRC Pro}ect Nr.C5257 A Division of The Franklin Instaute FRC Assignment No.13 3c 20th and Race Streets. Phda.. Pa. 19103(215) 448-1000 FRCTask No. 8 II EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 32.4 RAYCHDI Thermofit Insulation Systems (heat-shrink tubing) used to complete the replacement splice have been qualified per the. H. B. Robinson accident parmeters. Franklin Institute Research Laboratories Technical Report F-C4033-3 dated Jan-uary1975describesaprogramthatineguded40-yearaging, total irradiation exposure of.2.1 x 10 RADS, maximum tem-perature of 351 F, maximum pressure of 85 PSIA and a borated spray in excess of nine days. The results of this documented test are acceptable to CP&L that the heat-shrink tubing to be used in changeover is fully qualified. {l I e t ( I l I l

  #                                                                 NRC Contract N 2. NRC-0379-118 000Mnklin Research Ccnter                                       FRC Project No.C5257                            Page A Diwuon of The Frankhninstitme                             FRC Assignment No.13                             5a 20th and Race Strecs. Phda . Pa. 19103 (215) 448 1310       FRC Task No. 6/ /

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. JJ EQUIPMENT ENVIROMENTAL QUALIFICATION REVIEW Crit 0ria DOR Guidelines 1 ; NUREG-0588, Cat. I  ; NUREG-0588, Cat. II . NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) EQUIPMENT DESCRIPTION  !  !  ! I Equipment Type  ![dh /C- .fElectricalCableSplice

                                                   ! sfLiC *                                               !

Manufacturer's Name Raychem Corporation (5.2.2/-/-) f

                                                   .MdYCbem              .                                 f.

Modal Number (5.2.2/-/-) p gjns Itf'{ Raychem Thermofit f*

• WCSF . . .N Serial Number  ! pg *  !  !

                                                   !                     g Not Applicable                   g Factures/ Mounting                               'hf3faM
                                                      /                 '

(5.2.6/-/-) . . Conn:ctions/ Interfaces  !  !  ! (5.2.6/-/-)  ;  ; Test Item Is a Cable  ! g gSplice (Note 1 p 51 &51 1 ).2 . Location / Elevation  ! I  ! g Id/Z/ #u s Not Applicable  : Equipment ID No. jf //p*Not Applicable OUALIFICATION REPORT  !  ! g (S.0/5.0/5.0)  !  !  ! Report ID Number F-C4033-3  ! CF033-3 . Report Date { ,fp1f{ January 1975 f Iccu:d d,y

                                                                         ! Franklin Institute               g
                                                   .[/h g                     g Research Laboratories            :

Prspired for 1 Ofen Raychem Corporation RefGrenced Reports

                                                          / Vt h d'      {NotApplicable f

Qu:lification Method  ! p  ! Simultaneous Test I l (5.1, 5.3/2.1, 2.4/2.1, 2.4) !  !  ! QALIFICATION TEST PROGRAM  !  !  ! Functional Test Description !  ! (5. 2. 5/2. 2. 9/2. 2. 9) g NA {' Insulation Resistance /. l

                                                    ;                     ; Current Carrying Capabilitay Op;rcting Conditions                              !             -
                                                                          ! and HiPot                       g

(-/2.2.10/2.2.10) !jp pff /o,/g !  ! See Note 1 p 511 & 512 Ioad/ Cycles /Valtage/  !  ! Current /Freq.  !  ! g i I

A NRC Ccntract No. NRC 03-79-118 3 7 (I 000Eanklin Research Center J FRC Prrject No. C5257 Pego _ A Dhns cn of The Frankhn Institute 13 FRC Assignm:ntoNg,I( 5b 20th and Race Streets. Phila . Pa 19103 (215) 448 1000 FRC Task No. 1 _ EQUIPMENT ENVIRONMENTAL QUAllFICATION REVIEW OF EQUIPMENT ITEM NO. J.d 2 NRC REQUIREMENTS WITH SECTION REFERENCE LICENSEE DEFICIENCY g QUALIFICATION (X OR = (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) Acceptance Criteria  !  !  ! (5.2.5/2.2.1/2.2.1) !gg  ! Not Stated  ! Accuracy (5.2.5/-/-)  ! gg .  ! ' NR Mbm 1 Number of Specimens . jy, d

• 30 Test Instruments Calibrated  ! jr A .  ! 7,,  ! ' -

N Safety Function (Active /  !

• Y# Active.. Carry current .

Passive) (-/2.1. 3/2.1. 3)  !  !

                                                      !               !                           !                                      m Test Duration (5.2.1/-/-)                               /VA.      ,f    30 Days f

Accident Duration (Envir. 1  !  ! -- Above Normal) (5. 2.1/ -/-)  ! *! Not Applicable  ! [  !  !  ! J "E Required Function Time Can-fMhad C ! Not Applicable g Test Sequence (General) !g  ! ' p. ( 5. 2. 3/2. 3.1/ 2. 3.1)  !  ! Visual Inspection . pr

                                                      !               ! Insulation Resistance     I                             k-Test Sequence (NUREG-0588, Cat. I) (-/2.3.1/-)
                                                      ! /VA
                                                                      ! Thermal / Radiation Aging
                                                                      ! Visual Inspection 1

I T k *

                                                      !                ! Insulation Resistance    !

1. Representative Sample

                                                      !               ! LOCA Simulation            !

2. Baseline Data  !  ! Visual Inspection /  !

s M -

                                                                                                                       '\

3. Performance Extremes  !  ! Insulation Resistance /  ! Sk',

4. Thermal Aging  !  ! HiPot  !

                                                                                                                                $=

5. Radiation Aging  !  !  !

6. Wear Aging  !  !  ! '

g

7. Vibration / Seismic  !  !  !

f

                                                                                                                                      ~l

8. DBE Exposure  !  ! I

9. sast-DBE Exposure  !  !  ! al "

10. Inspection  !  !  ! U *

                                                                                                                               .M Aging                                              !               !                           .

M (5.2.4, 7.0/4.0/4.0)  ! 7 Days @ 150*C 'A/ofe.2. Thermal Aging / Basis  ! ' Not Stated . g 7 Material Aging  !  !  ! l Evaluation (7.0/-/-)  ! N  ! Visual Inspection /  ! s

                                                       !               ! Insulation Resistance     !                            E Materials Susceptible                              '               '

(Thermal) (5.2.4, 7.0/-/-) d+ M C -! Not Stated  ! j

                                                       !               !                           !                                    l Radiation Aging, Type                              !q        g     !

• Gamma _

4

 -                            _ _ _ .                                                                                          =

                ~ 's                                                NRC Contrtet No. NRC-03-79-118                                                                       0                   - ' ,.. .
'pM._2dFrankBn Asearch Center                                       FRC Project No. C5257                                                                     P:go A Cux,c of 7he FrarE.n astetute                              FRC Assignmsnt No.13                                                                       Sc   : ' f                                ,

20th and Race Streets. Phh . Pa. 19103 (215) 448 1 0 FRC Task No. E/I * .

                                                                                                                                                                           .. A, EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. _52.c)                                                                                                ..:

n

'.;. e~

• NRC REQUIREMENTC,. DEFICIENCY (X OR

                                                                                                                                                                    -{

WITH CECTION REFput.HCE LICENSEE QUALIFICATION , (DOR /d588-I/0588-TI) SUBMITTAL DOCUMENTATION NOTE NO.) ],_ , , ,

                                                 !                                   !                                                        s    !                            . .,            :?                ,
            ,                  i                 !                                     !                                                           !               : - Q,.                                            .; :

Radiat. ion Aging, Dose (rd) I ' '

                                                 ' ppt Sta.ted !

5x10 7  ;- , ' Radiation Aging, Dose Rate . fo -y d.Not Stated , Radiation Aging, Method f /t/ h fTest , f h'

4. ~ y

                                                                                                                                                                       }.

Materials Susceptible g  ! Stated g, (Radiation) ,(5.2,4,,7. 0/-/-) ! #8 ,. f. Not.  ! ' , _

                                                                                                                                                                                         .f- '                                 '

Operational Aging  !  !  ! -

 - (-/4. 2/-)                                     !M#I D 'I d                         Not   !                                    Stated             !                                                   .
                                                  !                                          !                                                      !                j_-9, , ; , .. 3 Other Age Conditioning                           ! j/4                                      !                                                      !                                y                            - 
                                                                                                                                                                              .. '_ _ , j

(-/4.2/-) i !Not Stated 1

                                                  !                                           !                                                     !                      '. j ~ .;; i Qualified Life claimed /                         !                                            !                                                    !                                                           .
                                                                                                                                                                                                                                +.
                                                                                              ! Not Stated                                 in Test  ! # p / d ,7                                           .' T.

Established (5.2.1/4.10/-)  !

                                                   !                                            ! Report                                            !! p g4            t *"' ,

j Normal Ambient Temperature  ! //i8f s. a. ! ~ ^ Normal Amoient Radiation  ! g..gg//,1 hh cS 0 1 i Hormal Ambient Humidity ' A p g *Not Applicable  ! p ' On-Going Surveillar.ca and  ! ,  !  ! ' ,. 3 I

                                                                                                                                                                                                                                   ~

Preventive Maintenance  ! ,

                                                              #'$                                  ! Not Applicable                                                    Ir                       .'.                           .

(7.0/-/-)  !  !  ! .y ' m

                                                   !                                                 !                                                                  i." "                     ..

On-Gcing Analysis of j  !  !  !;

• Pnilures and Degradation  ! N.S  ! Not AppI1 cable I ' "

l . . (7.0/-/-)  !  !  ! -

                                                    !                                                  !                                              !                !!.._--(;
                                                    !                                                 !                                               I Margin (General) j Not Stated
                                                                                                                                                                         ..[

(6.0/3.0/3.0)  ! -

                                                    !                                                   !                                             !                ."                    !                             (

Margin (NUREG '.588,  !  ! Not Stated i Cat. I) (-/3. /-)  !  !  ! n. -

                                                                                                         !                                            !                              .'             p' s.'T                     ..

1. Temperatu.4 (+15'F)  ! ' ' '

2. Pressure (+10%,  !  !  ! .i 10 psig max)  !  !  ! NL . .

-%.j 1

3. Radiation  !  !  ! ~);t"4 -

(not required)  !  !  ! 4 f

4. Time (+10%, +1 hour  !  !  ! [ ,5 ;# ' -

       + function time minimum)                      !                                                       !                                         !

4. . ..

                                                                                                                                                                                                                      ,g l                       :.7.[.

_;ga '

A NRC Contract No. NRC-03-79-118 000hr:nklin R: search Center FRC Project N2. C5257 Pag] i A Diwsson of The Frankhn Insutute .13 5d ' 20th and Race Streets. Phila.. Pa. 19103 (215) 448 1000 FRCTask FRC Assignment No. 5 Np/ I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.W NRC REQUIREMENTS DEFICIENCY WITH SECTION REFERENCE LICENSEE QUALIFICATION (X OR (DOR /0588-I/0588-II) SUBMITTAL DOCUMENTATION NOTE NO.) ACCIDENT CONDITIONS  !  !  ! IDCA/MSLB/HELB/ Uncontrolled !  ! LOCA/ MSLB  ! (4.1, 4.2, 4.3.1, 4.3.3/  ! 4  !  ! 1.1, 1. 2, 1. 5/1.1, 1. 2, 1. 5) !  !  ! Radiation Type pm A Gamma  ! Radiation Dose (rd)  !  ! 197.7-209.8 Megarads ' ( 4.1. 2/1. 4/1. 4) !p g, . . Radiation Dose Rate (rd/hr) !Akt Sta-lsti ! !Not Stated  ! Radiation Qual. Method  !  ! (5.3.1/-/-)  !  ! Test  ; s Proximity to Concentrated Radiation  ![d

                                                      !     Tu-icd 5     {' Not Applicable             {

( 4.1. 2/1. 4. 6/1. 4. 6)  !  !  ; Equipment Susceptible to  ! pg!  ! Beta Radiation (4.1.2/-/-) ,!  !  ! Radiation Dose (Normal + 1 e Accident) (4.1.2/-/-) !g,f ytsfedg* Not Applicable , Plateout Dose Considered  ! ggg! g (-/1. 48/1. 4 8)  !  ! Not Applicable , Gamma + Beta Dose (rd)  !  ! (4.1.2/1.4.7/1.4.7)  ! g' Not Applicable .

l

      &                                                                        NRC Contract No. NRC-03-79-118 Page 000Erinklin R:se:rch Ccnter                                             FRC Project N2. C5257 A Dmpon of The FrankhnInstitute -                                  FRC Assignment No.13                                            5e 20th and Race Streets. Phda.. Pa. 19 03 (215) 448 1000             FRC Task No. '6'li EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.M NRC REQUIREMENTS                                                                                                        DEFICIENCY WITH SECTION REFERENCE                                 LICENSEE                                 QUALIFICATION                       (X OR (DOR /0588-I/0588-II)                                 SUBMI'PfAL                               DOCUMENTATION                   NOTE No.)

ENVIRONMENTAL PROFILE 1 1 1 OF ACCIDENT CONDITIONS  !  !  ! Rato of Temp./ Press. Incrocse . ga;cf(,jjf'c .10*F;7 Psi /second

• i 1  !  !

Packs *F/psig/RH/ Time I

                                                          .2M/faf**[J/ff 357/70/100%/10 hrs                                      .

Decrease To: 'F/psig/RH/ Time  ! 1 9/ 24// h 357-275/70-31/100%/2

                                                                                     .                                 hrs Decrecae To *F/psig/RH/ Time ! f                        f G S')/                 275/31/100%/4 days Decrocse To 'F/psig/RH/ Time '                                               ! 212/10/100%/26 days                           !

Equipment Surface Tempera-  !  ! Not Applicable 1 turo (NSLB) (-/1.2.5.C,  ! //  !  ! 2.2.6/1.2.5.C, 2.2.6)  !  !  ! Sprey Qualification Method (5.3.2/1.3, 2.2.8/1.3, gg  ! Test 2.2.8)  ! {3000ppmBoron

                                                                                                                                                     ~

Spray Composition /7wt 4, { O ! 0.064 Molar Nags 023  ! (4.1.4/1.3, 2.2.8/ 1.3, 2.2.8) !1 d4*vP M l78#ddM. NaOH for pH 1 of 10.5 o .

                                                       ! pH -13                  !                                               !

Specy Density (gpm/f t 2) M 4 ffa+.d! 0.15 . .

  ' Spray Duration                                     ! ygg,g gfat[' 30 days

{ I Submergence Duration

• M#I S
• f M , Not Applicable

( 4.1. 3/2. 2. 5/2. 2. 5) J *  ! In-Lockage Considered !jyj.y g g p f' Not Applicable  ! (5.2.6, 5.3.2/-/-)  ! . 1 Time to Submergence ' y, f. 3 51 Not Applicable Dust Environment  !  ! Not Applicable  ! l (-/2. 2.11/ 2. 2.11)  !  !  !

                        $Q                   :MSf'd                                                 f~                 .        .

n, w g w d ,a y + 1 i h zw:, pg s

1. - - . . . - - , , , . , - . . . . . _ . . . . . _ _ . , . - - -

A NRC Contract No, NRC-03-79-118 lj00hrinklin R:se:rch Crnter FRC Project No. C5257 Pag 3 j A Dwon of The Fr:nkhn Institut2 FRC Assignm:nt N;.13 5f l 20th and Race Streets. Phila.. Pa. 19103 (215) 448-tmo FRC Task No. ElI l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J o NOTES: Note 2.The test conditions reported on pages 5a through 5e envelop the accident conditions described by the Licensee.for the Robinson Plant. It is therefore concluded that the equipment is qualified for the application described on the Licensee SCEW sheets However, the licensee has not identified a qualified life nor evaluated age related degradation applicable to the Robinson Plant conditions from the accellerated aging test data.

NRC Contract No. NRC-03 79-118 pbtnklin R:Search Ccnter U FRC Project No. C5257 Pag 3 A DNmon of The Frankhn Institute FRC Assignment No.13 5i .o' 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1 2 0 FRC Task No. 6/I EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. J.D NOTES:

2. TEST SPECIMEle tested and also shows the eastglaing voltags and )

currents levels. ' Table 1 presents a description of the specismens f i l Table 1 Test Spemmens Spetimen Electrical Imading Voltagt Initial Current Desertation

• Numberi Ianzth St)8 (Vrms - 60 Hz) (A)'

Raychem DermoSt8 In-Con *ainment '9X 20 600' C Field Splice Cable - Raychem Adverse Service Coaxial Cable, AWG 22 conductor 1st insulation layer - 8 mil war of Alkane-imido polymer 2nd insulation layer - 49 mil wall of Rayolin R" radiation cross-linked polyolean Braided Copper Shield Raychem Flamtrol" Jacket - 34 mil , nominal wall . Part No.10483 Run No J7-5-10-72-6 . Splice Components for one splice Raychem DermontS WCS?-115-4-N Soldered connection , (See Figure 1)

           , Raychem normont8 In-Containment                         13            35             2000                70 Field Sphces Cable AWG 4 insulated with EPR-neoprene (not a Raychem product) 3plice Components for six splices (Note 1)

Raychem Thermofits WCSF-200-6-N 2 each of compression connectors: Burndy Hylink YS4C-L T&B 2F-4 3M #4 Raychem Thermont8 In-Containment 14 37 1000 65 Field Splices Cable AWG 6 insulated with Raychem Flamtrol" . Splice Components for six splices (Note 1) Raychem WCSF-200-6-N 6 each of compression connectors: Burndy Hylink YS6C-L Raychem ThermoSt8 In-Containment 15 32 2000 25 Field Splices , Cable AWG 12 insulated with EPR . neoprene (not a Raychem product) Splice Components for six splices (Note 11 Raychem WCSF-115-6-N 3 each of compression connectors: Burndy Hyhnk YSV10 T&B 2C-10 Raychem ThermontS In-Containment 16 33 1000 25 Field Splices. Six splices. Same construction as Sample #15 except that ..aychem Flamtrol"

                    . wire was used

NRC Contract No. NRC-03-79-118 pbr:nklin U Rrsearch C:nter FRC Project No.C5257 Page A Dimion of The Frankhn Institute FRC Asaignfnent No.13 Si g 20th and Race Streets. Phda.. Pa 19103 (215) 448-10 @ FRC Task No. ElI' EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.30 1 NOTESt Table 1 Test Specimens (continued) - Specimen Electrical Imading voltage Initial Current Description

• Numbert Isnath (ft)' (Vrms - 60 ffr) (A)'

Raychem Thermo5t8 In-Containment 17 23 1000 65 Transition Splices Cable AWG 6 insulated with Raychem Flamtrol", spliced to three cables of AWG 12 insulated with Raychem Flamtrol" and reconnected to an - AWG 6 cable insulated with

• Raychem Flamtrol" Splice Components for two sp!!ces (Note 1)

Raychem ThermontS WCSF-200-6-N Raychem DermaSt heat-shrinkable 3-Snger cable breakout (Part Number 403A112-4[83) used to provide seal at the transition between the AWG 6 and the three AWG12 cables. 2 each of compression connectors: Barndy l{ylink YS6C-L 8 and " Trademarks of Raychem Corporation

• Description of specimens provided by Raychem i Specimens 1 thru 8 and 10 thru 12 were other test specimens supplied by Raychem. De test results on these specimens are presented in report numbers F-C4033-1 and -2.

8 Specimens cut to lengths shown. Apprtudmately 4 ft of the length extended outside of the test vessel (2 ft on each end of the specimen). 8 Initial currents were applied at room temperature. and allowed to drop to a lower level during com-hined radiation and thermal aging and simultaneous 14CA-simulation testing. See text for discussion. Note 1 - Each in-line splice or transition was covered with tinned copper wire mesh to aid in providing a close proximity ground plane as shownin Figure 2 l l l l

   /;%                                                           NRC Contract NO. NRC-03-79-118 bl!00 Fr:nklin Resezrch Cent:r                               FRC Project N . C5257                                   P .g2 A Dmsson d The Frankhn Institute                        FRC Assignment No.13                                     lc 20th and Race Streets. Phila.. Pa 19103 (215) 448 IN    FRC Task No. S//

EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.E EQUIPMENT ITEM NO. 31 ELECTRICAL CONNECTOR LOCATED IN THE CONTAINMENT, ELEV. 234'-246' AMP MODEL 535481, WIRE SIZE 16 . REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 31 LICENSEE REFERENCE (S): 2068 FUNCTION (PLANT ID): CONDUCIOR BUTT SPLICE LICENSEE SUBMITTAL: SCEW(S): 25 OF 25 [20] DESIGNATION FOR DEFICIENCY IDENTIFIE BY THE NRC SER - CIRCLED ITEM (S) ONLY: (SM Section 3 of this TER for Legend) CShS,

     ,      rJr, RT                                  (R) , M,   I, QM RPN, EXN, SEN, QI               RPS, None, Not stated, Not applicable-LISTING OF APPLICABLE CHECKSHEETS:

Contents Checksheet Page No. Equipment Item la Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Lic nxee Response to NRC SER 3a, 3b, L , Sa 1 Sycten Consideration Review 4a, L, =w, ,J, b, 42 ' Equipment Environmental Qualification Review L , ,L, Su, ;J, Sc, 5f, 53 , Oh, Si, Sj Installed TMI Lessons Learned Implementation 5;, Cb

 . Equipment Summary Maintsnance and Replacement Schedule Summary                                     7a, 7L, 7e

_ __ ___ _ _ _____ _ ____m

1 NRC Contract N2. NRC-03 79-118 l pbr UO nklin Riseirch Ccntrr FRC Project N . C5257 Page A Dtvison of The Fr:nkhn Instituti FRC Asalgnment  ;]3 lb 20th and Race Streets. PMa.. Pa 19103 (215) 448-10m FRC Task No. // j EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: [ Tne Licensee (has,t 2:0 provided a response to the SER concerns. [ The Licensee (has/.'.. ..n) specifically stated that ide equipment is qualified andhe will function when exposed to the applicable DBE environmental service conditions. The Licensee has presented information which shows there are no outstanding qualification deficiencies. The Licensee (has/has not) proposed a corrective action for this equipment item whose qualification has not been fully established. Justification for interim operation (has/has not) been provided by the Licensee for this equipment item. 1 Corrective action specified by the Licensee Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source Verify qualification by additional (testing / analysis) Equipment relocation to a mild environment X Qualification testing of equipment in progress Other ( ) The Licensee has provided other information for this equipment item that can be construed as a basis for justification for interim operation. _j(,The Licensee Weefhas not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action .) The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATION CATEGORY BASED ON REVIEW

- CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency l l.b Modification] III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available I _ . _ . _ .. _ l

NRC Contract No. NRC-03-79-118 p[Frrnkhn UOO R: search Ccnter FRC Project No. C5257 Page A D6vakm of The Frankhn Institute FRC Assignment No.13 2 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRC Task No. T // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUlPMENT ITEM NO. O I EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequate Similarity Between Equipment and Test Specimen Established ' 1 Aging Degradation Evaluated Adequately Qunlified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Critoria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate Criteria Regarding Spray Satisfied Critsria Regarding Submergence Satisfied Crit:ria Regarding Radiation Satisfied Critoria Regarding Test Sequence Satisfied Critsria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Critaria Regarding Functional Testing Satisfied Criteria Regarding Instrument Accuracy Satisfied Tact Duration Margin (1 hour + Function Time) Satisfied Criteria Regarding Margins Satisfied (NUREG-0588, Cat. I) DESIGNATION: NRC QUALIFICATION CATEGORY X = CATEGORY I.a Equipment Qualified I.b Equipment Qualification Pending Modification X II.c Equipment Qualification Not Established II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.D Equipment Not in the Scope of ,the Qualification Review IV Documentation Not Made Available

                                                             ]h & Ch

NRC Contract No. NRC-03 79-118 phranklin UO0 R: search Center FRC Project No. C5257 Page A Dwision of The FrankhnInstitute FRC Assignment No.13 30 20th and Race Streets. Phas.. Pa. 19103 (215) 448-1000 FRCTask No. # // l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. G). LICENSEE RESPOllSE TO NRC SER 4.2 Eculement Recuiring Additional Information and/or Corrective Action (Accendix 3) Mo1 ' The bulk of master list equipment was placed in this category and our review of deficiencies is based upon the folloding: Deletion of deficient listed' equipment due to replacement programs carried out and reported in our 90-day, Revision 3 response dated February 1, 1981. Re-evaluation of CP&L's updated submittals by NRC Region II, Atlanta, GA, and reported in Environmental Qualification of Safety-Related Electrical Equipment II3 79-013. Technical Evaluation Report

                   - Docket No. 50-261; Plant:                  H. 3. Robinson 2, dated November 6, 1980 and Revised November 11, 1980.

Telecons with NRC, Bethesda, MD reviewing personnel July 29, 1981, et al. Equipment reported as qualified within NRC TER Revision 1, dated November 11, 1980: Ecutement Descriotion Manufacturer Model No. location 2

19. cable terminals AMP 53548-1 containment and splices 2

These items also included in conductor pig-tail qualification test ('#1e Qualification Test Plan 45307-0 to supply acceptable aging, radiation, and LCCA test data for R. 3. Robinson qualification. A. Cable Terminals and Splices AMP 53548-1 1 R,T,RT,P,H,CS, A,QM,Q1 AItems reported as qualified within NRC Region II revised TIR, dated 11/7/80.

                                                                     =

NRC Contract No, NRC-03 79-118 00J Fr:nklin Research Center FRC Project No. C5257 Page A DMs6on of The Frankhn Institute FRC Asaignment No.13 3b 20th and Race Streets. Phae.. Pa. 19103 (215) 448-10m FRC Task No, _ 6/l EQUIPMENT ENVIR0f4 MENTAL QUALIFICATION REVIEW OF EGulPMENT ITEM NC. .d.1 Cable Terminals and Splices g{ Ao no qualification information could be obtained on the current in containment cable splices to the listed electrical equipment, it was decided to change out the splices with qualified co=ponents, prescribed trols and approved procedure. This changeout was completed during the plant refueling outage (August - October) 1980. Individual conductor splices will utilize AMP Radiation Rasistant/150 C Preinsulated Splices (#53548-1) . T&B 2-way Cable Connectors for Copper Cable, 500 MCM and T&B 2-way Cable Connectors for Copper Cable, #9 AWG. The splice / connector component will be crimped to the designated conductors using the manufacturer's specified crimping tool. An appropriate sized RAYCHEM SHRINK TUBING will be applied over the individual conductor cable splice and heat shrunk using the manufacturer's specified torch. For the two- (2) and three- (3) conductor cables after the individual conductors are spliced using AMP P1DG (53548-1) splices, an overall jacket RAYCHEM SHRINK TJBING will be applied and heat shrunk. The work described above has been detailed within H. B. Robinson S.E.P. Modification and Setpoint Revision Form No. M-521 (revised) and will be the means to sign off the completed work. Original splices specified as AMP Nuclear Preinsulated Environmentally Saaled Splices (#52979) were found to be incompatible with the conductor insulation thickness of installed cable. Therefore, another butt-splice component, AMP Radiation resistant /150 C preinsulated splice (#53548-1) was ordered and installed. AMP Qualification Test Report 110-11002 dated October 1, 1978 describes a program that included total radiation exposure of 2.0 x 10 RADS, maximum temperature of 350 P, maximum pressure of 137 PSIA and a borated chemical spray lasting four (4) /s), days. To assure qualification of the H. 3. Robinson in-containment splices, cable undergoing testing at Wyle Laboratories will be connected with AMP PIDG terminals Raychem thermofit (. heat shrink) tubing overall per the Installation Procedure M-521, Safety-Related Cable Splices Inside Containment. Appropriate matrix combinations of splice / cable and individual cables and splices will assure identification of any single component failure which could occur during qualification testing. Each component has sufficient =anufacturer-supplied test data to assure qualification by analytical means. The opportunity to R2 obtain actual test results is available and will be used.

l

                     ,                                           NRC Contract No. NRC-03-79-118       I FRC Project No. C5257          P go  l 00 Frinklin R:se:rch Csnter A Den of The Frr.nkhn Instnut2                        FRC Assignment N2.13            5f   I 20th and Race Streets. Phda.. Pa. 19103 (215) 448 lWW FRC Task No. 511 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. 21_.

l I NOTES: The Licensee states that AMP oreinnulated solices model #51548.1 have been installed at H.B. Robinson. The Licennee states that AMP Oualiftation Test Reoort 110-11002 nrovides evidance of analif f ention testing for the installed eauipment. The test Recorr describes the samples as E/N 53408-1. The licensee has not orovided any information which demonstrates that the models tested and the models installed are equivalent. The Licensee also states in reference 15 that Solices in the installed configuration are undergoing test in conjunction with the penetration pigtail cables.When the tests are completed actual test results will be used. Therefore this equipment is assigned to NRC Category Ib because the Licensee states that qualification testing to plant conditions is in progress.

l A NRC Contract N A NRC-03-79-118 LO0iFrinklin R:sench Csnta FRC Project NL C5257 P g2 A Division of The Franklin Institute FRC Assignment N913 Ia 20th and Race Streets. Phila.. Pa. 19103(215) 448 1000 FRCTaskNo. S/l EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO3.el EQUIPMENT ITEM No. 32 ELECTRICAL TAPE LOCATED IN THE CONTAINMENT 3M/ ELECTRO PRODUCTS MODEL SCOTCH 70 (SILICON RUBBER) REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 32 ^ LICENSEE REFERENCE (S): NOT CITED FUNCTION (PLANT ID): CABLE TERMINATION PROTECTION LICENSEE SUBMITTAL: SCEW(S): 25A 0F 25 [20] l DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CfRCLED ITEM (S) ONLY: l (Sto Section 3 of this TER for Legend) RT P H CS A, S, (R) , M, I, QM RPN, EXN, SEN, QI RPS, None, Not ctated, Not applicable LISTING OF APPLICABLE CHECKSHEETS: Centents Checksheet Page No. Equipment Item la j Summary of Licensee Responses to the NRC SER lb Equipment Environmental Qualification Summary Forms 2 Lic;nsee Response to NRC SER 3a, 3b, L., 3d-Syctim Consideration Review St. 55, 52, fl, eu, 42' Equipment Environmental Qualification Review 52, *N 5 0, 50, L , 52, 5;, Sh, Si, Or Installed TMI Lessons Learned Implementation ir a , T.,0 Equipment Summary Maintenance and Replacement Schedule Summary -7., 7L, 7;-

4 NRC Contract No. NRC-03 79-11t ll00u Franklin Resetrch Ctnter FRC Project N3. C5257 Pa03 A Dimon of Ths Frankhn Insntuts FRC Assignment N3.13 lb 20th and Race Streets. Phila.. Pa. 19103 (215) 448-1000 FRC Task No. S // EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. M l

SUMMARY

OF LICENSEE RESPONSES TO THE NRC SER - ONLY CHECKED ITEMS ARE APPLICABLE: h Tne Licensee (has/t .M) provided a response to the SER concerns.

!-   [ The Licensee (han/ hee -no4) specifically stated that the equipment is j              qualified and,4or will function when exposed to the applicable DBE environmental service conditions.

The Licensee has presented information which shows there are no outstanding qualification deficiencies.

     .)[,_ The Licensee (hasA.;; .4 proposed a corrective action for this equipment item whose qualification has not been fully established.

Justification for interim operation (has/has not) been provided by the

• Licensee for this equipment- item.

Corrective action specified by the Licensee I Equipment replacement with qualified equipment Equipment modification Equipment relocation above submergence level Relocate or shield equipment from radiation source l Verify qualification by additional (testing / analysis) ! Equipment relocation to a mild environment X Qualification testing of equipment in progress Other ( ) i g The Licensee has provided other information for this equipment ites that can be construed as a basis for justification for interim operation a A p e / #f/M DC I The Licensee (haa/has not) provided a schedule for the proposed corrective action. (Schedule for accomplishing the corrective action . ) ! The Licensee states that the equipment item does not require qualification and/or should be exempted from environmental qualification. DESIGNATION OF RESULTANT NRC QUALIFICATION EVALUATIOt1 CATEGORY BASED ON REVIEW

     - CIRCLED ITEM ONLY: (See Section 3 of this TER for Legend)

I.a Qualified II.c Qualified Life Deficiency JI .b Modification _) III.a Exempt II.a Qualification Not Established III.b Not in Scope II.b Not Qualified IV Documentation Not Available i 1

   - - -                                             -       -,-,--.e a - -~ , - - , -,,       ,- , - - - - - - , .      . , , , , - -   ,,e     ,----e..--,--a

p NRC Contract No. NRC-03-79-118 FRC Project No.C5257 Page UOO rrnklin Rtsearch Center A D6 vision of The Franklin Institute FRC Asalgnment No.13 2 20th and Race Streets. Phila.. Pa. 19103(215) 448-1000 FRCTask No. M/ EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. Gal l EQUIPMENT ENVIRONMENTAL QUALIFICATION

SUMMARY

FORM DESIGNATION: NRC REQUIREMENTS X = DEFICIENCY Documented Evidence of Qualification Adequate Adequnte Similarity Between Equipment and Test Specimen Established X Aging Degradation Evaluated Adequately Qualified Life or Replacement Schedule Established (If Required) Program Established to Identify Aging Degradation Critoria Regarding Aging Simulation Satisfied (If Required) Criteria Regarding Temperature / Pressure Exposure: o Peak Temperature Adequate o Peak Pressure Adequate o Duration Adequate o Required Profile Enveloped Adequately o Steam Exposure (If Required) Adequate CritGria Regarding Spray Satisfied Critcria Regarding Submergence Satisfied Critsria Regarding Radiation Satisfied Crit 0ria Regarding Test Fequence Satisfied Criteria Regarding Test Failures or Severe Anomalies (If Any) Satisfied Crit 0ria Regarding Functional Testing Sctisfied Critoria Regarding Instrument. Accuracy Satisfied Tcst Duration Margin (1 hour & Function Time) Satisfied CritGria Regarding Margins Satisfied (NUREG-0588, Cat. I) l DESIGNATION: l NRC QUALIFICATION CATEGORY X = CATEGORY ! I.a Equipment Qualified __ l I.b Equipment Qualification Pending Modification >( l II.c Equipment Qualification Not Established l II.b Equipment Not Qualified II.c Equipment Satisfies All Requirements Except Qualified Life or Replacement Schedule Justified III.a Equipment Exempt From Qualification III.o Equipment Not in the Scope of the Qualification Review IV Doce pntation Not Made Available x x ,4. n,own# M n A n & =r Apo cs ar3 na ar-

                                                 &M $ M.

l l 4 NRC Contract No. NRC-03-79-118 FRC Project No. C5257 Page UOOU Fr:nklin Research Center A DMsion of The Frankhn Institute FRC Assignment No.13 3a 20th and Race Streets. IMs.. Pa. 19103 (215) 448-10m FRC Task No. Jll EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO.J.6 LICENSEE RESPONSE TO NRC SER Silicon Rubber 3M/ Electric Tape Products Division Scotch 70 1 R,T,QT,RT,P,H, CS,A,QM,QI The items within Appendix 3 not fully covered by eith'er TER classification or SCEWS's are as follows: Ecutoment Descriotion Manufacturer Model No. Location Motor Operator Limitorque SMB-3 containment Transmitter Rosemount 1153A containment Level Switch Madison 5602 containment Silicon Rubber Tape 3M Scotch 70 containment The Scotch 70, silicon rubber tape used as part of our splicing procedure has been tested within the containment cabla qualification test program reported for Appendix A listed equipment. Complete splice materials, per CP&L splice procedure M-521 (Rev. 0), were installed on both contair:nne cable under test and ' mown qualified control cable to establish qualification per H. B. Robinson environmental parameters. When this test report is reviewed, CP&L will inform the NRC of any additional actions, if any are required concerning Scotch 70 tape. ho -

NRC Contract No NRC 03-79-118 00 Franklin Rese:rch Center FRC Project No.C5257 Page A DMs6on of The Franklin Instuute FRC Assignment No.13 3b 20th and Race Streets. Phata.. Pa. 19103 (215) 448 1000 FRC Task No. S l'l EQUIPMENT ENVIRONMENTAL QUALIFICATICN REVIEW OF EQUIPMENT ITE,M NO. M l The Kerite Company has attested to the ability of this cable supplied for H. 3. Robinson to withstand the FSAR LOCA conditions of temperature, prescure and radiation. In addition, test qualification included forty- (40) year aging, borated spray j and 100% relative humidity exposure to meet I C E 323-1974 and gg i IEEE 383-1974 requirements. Referenced reports are: l FIRL Report F-C4020-2 dated March 1975. Proprietary Engineering Memo No. 178 entitled, " Determining Temperature Ratings of Cables and Pre-aging Requirements for LOCA Simulation Tests" dated December 27, 1974 (superseded by EM 178A dated May 1, 1979 and Di 178B dated December 1, 1979). To provide protection for cable terminction at equipment end, when no formal termination method was provided, a silicone rubber tape was used. SCOTCH 70, high temperature silicone rubber tape, is used for safety-related terminations. This product has undergone radiation testing by the manufacturer, Mingesota Mining & Manufacturing Co=pany (3M) up to 1.0x10 RADS at 40 C temperature with no major g degradation of performance. A more comprehensive testing program to meet IEEE 323, - 1974, requirements has been performed by Kerite Company utilizing SCOTCH 70 tape and Kerite Cable within LOCA testing chamber. Kerite has certified the use of SCOTCH 70 as detailed in Reference Number 50. hc r#% L. .: . '. . " n ,% . m j To assure tape qualification for H, 3) Robinson application, SCOTCH 70 tape will be used is conjunction with test control cables during qualifAcation testing of the electrical penetrations PVC pigtail cable being perfor=ed at Wyle A 2-( Laboratories. Results will be documented and available after completion of PVC cable testing. Cis3

i TER-C5257-511 2 5

5. CONCLUSIONS The tabulations in Section 4.2 represent a summary ' of the results of the

   'cquipment environmental qualification (EEQ) assessment conducted in accordance -

with the . methodology presented in Section 3. The evaluations are based on the

    .cynilcble qualification documentation provided by the Licensee, complemented 2

3 in several cases by other relevant technical information. The major qualification deficiencies that have been identified and the results of the synluation are shown in the Equipment Environmental Qualification Summary Forms (Tables 4-1, .4-2, 4-3, and 4-4) . Although Sections 4.3, 4.4, and Appendix C of this report present a datailed evaluation of (1) the Licensee's qualification methodology, (2) the equipment environmental qualification of each equipment item, and (3) the Licanzee's response to the NRC SER, it is appropriate to highlight for the Licensee and the NRC certain conclusions and concerns reached as a result of the raview which require special attention. These concerns are summarized balow. o Section 4.1 of the NRC SER [16] identified the following concern:

                   "4.1          Equipment Requiring Immediate Corrective Action Appendix A identifies equipment (if any) in this category. The licensee was asked to review the facility's safety-related electrical equipment. The licensee's review has concluded that the conductor pigtails of some electrical penetrations are unqualified, and a licensee event report (LER) number RSEP 80-1037, addressing this issue, was submitted to the NRC on July 3,1980. A qualification testing program, which is scheduled to be completed by May 1981, has been initiated by the licensee, and results will be submitted to the NRC.          The results will enable the licensee to determine whether further action is required. The licensee further stated that analysis i

of operating-time radiation exposure led to the conclusion that the i plant can continue operation until the testing is completed and the [ results reviewed. In this review, the staff has not identified any safety-related electrical equipment which is not able to perform its intended safety function during the time in which it must operate." l

5-1 b Franidin A oeaman at m n.mnResearch in. u. C. enter

TER-CS257-511 In response, the Licensee stated [20):

       "4.1        Equipment Requiring Immediate Corrective Action (Appendix A)

Conductor Pigtails of Electrical Penetrations, B-1, B-2, B-5, B-9, C-1, C-2, C-3, C-4, C-6, C-8, C-9, D-1, D-2, D-3, D-5, D-8, D-9 Manufacturer: Continental Wire and Cable Company Jacket Material: PVC Test Laboratory: Wyle Laboratories, Huntsville, Alabama Qualification Test Plan: 45307-1 dated January 12, 1981 Status: All test sequences stated within the Final Qualification Test Plan (45307-1) were completed on July 17, 1981. The test cables, test control cables and splices were removed from the LOCA test chamber on July 20, 1981 and are undergoing evaluation. A test report is scheduled for issuance September 1, 1981. Review of this report will be made before final disposition of this ratter will be made to the NRC. Preliminary data indicates no failure of the cable or splices which would require any immediate corrective action by the plant. Therefore, the statement found at the end of the SER Appendix A. . ..

        ' Licensee integrated dose assessment provides justification for continued operation until testing is completed and analyzed' remains valid."

It is concluded that the Licensee's approach is satisfactory. o Equipment Items 12,13,14, and 15 (Rosemount transmitter Model 1153A) have been placed in NRC Qualification Category II.b because the Licensee has reported current Rosemount testing which resulted in failure of the test specimen (IEEE-3231974 criteria applied). The Licensee has stated that the H. B. Robinson accident profiles were enveloped by successful transmitter testing (References 1764 and 4423). The Licensee has provided (1) an 0-ring replacement schedule and (2) a statement that current testing by Rosemount represents an "over-test condition" with regard to H. B. Robinson parameters. This provides a technically sound basis for justification for interim operation. However, because the current Rosemount test report is not avialable for review to allow independent verification, this equipment item is considered unqualified. Since all transmitters inside containment are Rosemount Model 1153A, an assessment of the current Rosemount test program should be conducted by the NEC. o Equipment Items 16 and 17 (Gems level sensor Models XM 36495 and XM52495) were placed in Category II.b because the referenced test report (FIRL F-C3834) was considered inconclusive and the equipment failed to meet the requirements of NUREG-0588 Rev.1 Category 1 and the DOR Guidelines. A supplement to the referenced report (FIRL S-C3834) indicates that the equipment failed to operate satisfactorily during testing. A 5-2 Obranklin Research Center A Dinneon of The Frankan insatute

TER-C5257-511 o It appears that the Licensee has not resolved the NRC concern regarding temperature, pressure, and humidity conditions inside containment. Since the Licensee is responsible for identifying the environments, the parameters identified by the Licensee have been used in the evaluations contained in this Technical Evaluation Report. These parameters are reproduced in Appendix A (see Section 4.3.2.2). o The Licensee has not resolved the NRC concern regarding submergence,

       . but is currently in the process of evaluating the concern (see Section 4.3.3).

o A review of the SCEWS for instruments reveals that the specified operating times for several key instruments are too short. For example, pressurizer pressure transmitters have required operating times of 1 hour to 1 day. A further review of the SCEWS does not reveal any RCS pressure transmitter which will be available for long-term monitoring of reactor coolant system pressure. Additionally, 4 the Licensee states that steam generator level transmitters are required to operate for only 30 minutes. While these transmitters are not necessarily required for long-term monitoring, these operating , times are not consistent with the general requirements for achieving long-term shutdown cooling modes and do not adequately reflect the , potential need to remain in a hot-shutdown condition for an interim period be, fore reaching a stable long-term cooling condition. (See Appendix C of this report for futher details.) With respect to justification for continued operation, the Licensee (ctated(20):

        "SECTION IV - Justification for Continued Operation Based upon our review of the items listed within Appendix B of the NRC issued Environmental Qualification of Safety-Related Electrical Equipment - Safety Evaluation Report as herein reported (Section I) and noting that no deficiency resolution alters the status of the equipment covered, the concluding statement within the SER should continue to be valid:
        'The staff further concludes that there is reasonable assurance of continued safe operation of this facility pending completion of these corrective actions. This conclusion is based on the following:

(1) That there are no outstanding items which would require immediate corrective action to assure safety of plant operation. (2) Some of the items found deficient have been or are being replaced or relocated, thus improving the facility's capability to function following a LOCA or HELB. l nklin Research Center A DMaon of The Franhiin m

TER-CS257-511

                  -(3) The harsh environmental conditions for which this equipment must be qualified result from low probability events; events which might reasonably be ' anticipated during this very limited period would lead to less demanding service conditions for this equipment.'

CP&L is confident the master listed and reviewed equipment will work in an accident environment, we-have documented our opinion, and qualification testing will be completed by the date established by the NRC for conclusion of qualification of safety-related electrical-equipment." The review of the Licensee's rationale presented as justification for interim operation is presented in Appendix D of this report. With respect to TMI Action Plan items, the Licensee has provided the following information [15]:

                   "7.0       TMI Action Plan Equipment TMI-2 Lessons Learned Task Force Status Report and Short-Tern Recommendations, NUREG-0578, dated July 1979, contained twenty-three (23) specific recommendations in twelve (12) broad. areas (nine (9) design and analysis and three (3) operations). Based on these recommendations, a TMI Task Force at HBR reviewed equipment and operations to either record current or propose new means to comply where or when required.

In response to NRC IE Bulletin 79-01B and subsequent supplements, the

                   'TMI-2 Lessons Learned' electrical equipment installed to date at HBR has been reviewed for qualification and reported herein. A listing of modifications resulting from the Task Force review is shown in Table 7.1.       Included are the NUREG 0578 paragraph numbers to which these modifications apply and the installation status to date. From the bill of materials for each-installed modification, the electrical items determined to be reportable under 79-OlB are compiled within a Master List of TMI Action Plan Equipment and presented in paragraph 7.1.       The Master List also identified those items in containment (harsh environment) and those items outside of containment (non-harsh environment).

Paragraph 7.2, Environmental Qualification of Electrical Equipment Required for TMI-2 Lessons Learned Modifications (Installed) contains a System Component Evaluation Work Sheet for each of the Master List items--both harsh and non-harsh environments. The major difference for TMI lessons learned equipment and accident condition equipment is the source radiation exposure postulation. For this report, a total radiation integrated dose, as determined by a Reactor Building Radiation Shielding Design Review (HBR-2) performed by Ebasco Services nklin Research Center A DMeson of The Frankan Insenae

TER-CS257-511 for CP&L, is utilized for each outside-of-containment identified item. Also, the figures utilized for qualification in designated areas are conservative in that after installation of identified shielding or new equipment the radiation levels are significantly reduced. Another posculation is that components exposed to radiation levels equal to or less than 1 x 100 R, total integrated dose, due to. location need not undergo special qualification in that materials utilized are not affected during a forty- (40) year life and accident mitigation conditions by these levels of radiation. 6 l 8 5-5 0000 Franklin Research Center A Dhemen of The Frenten bueue

TER-C5257-511 Table 7.1 TMI-2 Lessons. Learned Modifications (HBR) Modificction NUREG No. Title 0578 No. Status M 501 Core Subcooling Monitor 2.1.3b Installed [II.F.2*] . M 502 Direct Position Indicator of 2.1.3a Installed Pressurizer Safety Relief Valves [II.D.3] M 504 Auxiliary Feedwater Flow 2.1.4b Installed Indication to Steam Generators [II .E .1.2. 2 ] M 505 Interir. Plant Vent High 1.1.8b Installed Radiation Monitor (II.F.1] r ! M 506 Fuel Handling Bldg. Basement 2.1.8b Installed Exhaust High Radiation Monitor [II.F.1] M 509 Auto Trip of Pressurizer Heater 2.1.1 Installed Breakers Under Blackout Conditions

                                             ~                 [II.E.3.1
                                                               & II.G.1]

M 510 Containment Isolati G 2.1.4 Installed [II.E.4.2 ] M 520 High Point Venting 2.1.9 Installed [II.B.1] (but iso- ' Denton lated from

                                                               *1                primary)

M 525 Containment Vessel Water Level ACRS-2 Installed- [II.F.1.5] M 530 Alarm Indication for Opening of 2.1.3a Installed Pressurizer PORVs [II.D.3] i M 532 Tech Support Center Radiation Suspended Monitor Pending issuance of NUREG 0696 M 542 PRT/RCDT Sample Lines 2.1.4 Installed" to Gas Analyzer [II.B.3] f

• Numbers in brackets, added to table for reference purposes, indicate applicable NUREG-0737 section.

nklin Research Center A Dhman of The Franhan Insende

TER-C5257-511

6. REFERENCES The references listed in this section of the report were used to develop ths Equipment Environmental Qualification evaluation for this plant. The rcfersnces have been separated into two lists: (1)' Plant-Specific References cnd (2) Plant Generic References. All non-generic documents are listed on the "Plcnt-Specific References" list. All qualification documents that could be cpplicable to equipment installed in several plants were listed on the " Plant G:nsric References" list. These documents include topical reports, test r:psrts, component and material analyses, etc. cited by the Licensee as evidence of qualification in accordance with the documentation reference instructions s:tchlished by IE Bulletin 79-01B. Since these documents were compiled by a computer data base, the citation numbering was computer generated and the same document has the same generic reference number in all Technical Evaluation Rsparts prepared under this equipment qualification program.

Throughout the text of the report, references are designated by a brzeketed number; the reference numbers are not presented in sequential order. l 6-1 000 AFranklin Research Center

             % et m Franan wn,.

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

l TER-C5257-511 PLANT-SPECIFIC REFERENCES

1. L. W. Eury

. Letter to J. P. O'Reilly, NRC.

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2, IE Bulletin 79-01B - Ninety-Day Report Carolina Power & Light Co. , 07-Jul-80 Serial No. 80-1004

2. Environmental Qualification of Electrical Equipment - H. B.

Robinson E. G. Plant Unit 2. NRC IE Bulletin 79-01B (90-Day Report) Carolina Power & Light Co, 00-Jun-80

3. Environmental Qualification of Electrical Equipment - H. B.

Robinson E. G. Plant, Unit 2. NRC IE Bulletin 79-OlB (90-Day Report), Revision 2. Carolina Power & Light Co. , 01-Nov-80 i

4. B. J. Furr Letter to N. C. Moseley, NRC.

Subject:

IE Bulletin 79-01B Revisions - Additional copies Carolina Power & Light Co., 21-Nov-80 Serial No.-80-1691

5. G. Lainas Letter to A. Schwencer, NRC.

Subject:

Electrical Equipment Environmental Qualification USNRC, 19-Fe b-80

6. Environmental Qualification of Electrical Equipment USNRC/IE, 14-Jan-80 IEB 79-01B

7. Environmental Qualification of Class IE Equipment USNRC, 29-Feb-80 IEB 79-OlB, Supp. 1

8. N. C. Moseley Letter to B. H. Grier et al. , NRC.

Subject:

Supplement No. 2 to Bulletin 79-OlB, Environmental Qualification of Class IE Equipment USNRC, 29-Sep-80 6-2 Y "n N *E' $

 ---t.

TER-C5257-511

9. N. C. Moseley Letter to B. H. Grier et al., NRC.

Subject:

Supplement No. 3 to Bulletin 79-01B, Environmental Qualification of Class 1E Equipment USNRC, 24-Oct-80

10. S. J. Chilk Memorandum and Order pursuant to Union of Concerned Scientists Petition for Emergency and Remedial Relief USNRC, 23-May-80 CLI-80-21

11. D. G. Eisenhut Letter to All Power Reactor Licensees, Applicants, Vendors.

Subject:

Environmental Qualification of Safety-Related Electrical Equipment; NRC Staff Positions USNRC, 20-Apr-82 Gen. Ltr. 82-09

12. A. J. Szukiewicz Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment; Including Staff Responses to Public Comments USNRC, 00-Jul-81 NUREG-0588, Rev. I

13. Clarification of TMI Action Plan Requirements USNRC, 00-Nov-80 NUREG-0737

14. B. J. Furr

        .            Letter to J. P. O'Reilly, NRC. 

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2, Revision 3 to IE Bulletin 79-OlB Ninety-Day Report. Carolina Power & Light, 30-Jan-81 Serial: NO-81-12

15. Environmental Qualification of Electrical Equipment; H. B. Robinson E. G. Plant Unit 2; NRC - IE Bulletin 79-01B (90 Day Report) (Supplement No.2) (Supplement No.3). Rev. 3 Carolina Power & Light, 01-Feb-81

16. Office of Nuclear Reactor Regulation Safety Evaluation Report for H. B. Robinson Unit 2 USNRC, 21-May-81 6-3 000hranklin Research Center A DMuon of The Frenten Inseawee

TER-C5257-511

17. E. E. Utley Letter to C. Crane, FRC.

Subject:

H. B. Robinson Steam Electric Plant Unit No. 2, Environmental Qualification, with Attachments Carolina Power & Light Co., 31-Jul-81

18. Postulated Pipe Failure Analysis Outside of Containment Westinghouse, 09-Nov-73

19. Steps Contained in H. B. Robinson General Procedure GP-6, Plant Cooldown from Hot Shutdown to Cold Shutdown Conditions '

Carolina Power & Light Co. GP-6

20. E. E. Utley and M. A. McDuffie Letter to S. A. Varga, NRC.

Subject:

H. B. Robinson Steam Elec-tric Plant, Unit No. 2 - Response to May 21, 1981 letter and Safety Evaluation Report Carolina Power & Light Co. , 31-Aug-81 NO-81-1432

21. R. B. Starkey, Jr.

Letter to J. P. O'Reilly, NBC.

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2; Licensee Event Report 80-014, Update Report No. 1 Carolina Power & Light Co. ,19-Oct-81 RSEP/81-1617 I

22. Environmental Qualification of Electrical Equipment.

H. B. Robinson E. G. Plant Unit 2. NRC IE Bulletin 79-01B (45-day Report) Carolina Power & Light Co. , 00-Mar-80

23. S. A. Varga Letter to C. J. Crane, FRC.

Subject:

Transmittal of WCAP-8587, and Correction of Limitorque Test Report Number as listed in Robinson 2 RFI USNRC, 25-Ja n-82

24. E. E. Utley Letter D. G. Eisenhut, NRC.

Subject:

H. B. Robinson i Steam Electric Plant, Unit No. 2 Request for. Additional Information - Environmental Qualification Carolina Power & Light Co. , 01-Mar-82

25. Westinghouse letter CPL-77-550

26. Emergency Instructions (E.I. - 1) Incident Involving Reactor Coolant System Depressurization

] nklin Research Center A DMesan of The Franhan insatute

d n l

                                                               ' TER-C5257-511

27. Kerite Company letter dated August 5,1980 l

28. Kerite Company letter dated October 21, 1980, regarding

             -Qualification Data on use of Scotch 70 Silicone Rubber Tape

29. H. B. Robinson Steam Electric Plant Unit 2; TMI Project Modification Design Criteria Carolina Power & Light, 01-Jun-80

30. Request for Additional Information: Equipment Environmental Qualification (EEQ); Review of Licensees' Resolution of Outstanding Issues from NRC Equipment Environmental Qualification Safety Evaluation Reports (SER) and TMI Action Plan Installed Equipment; Carolina Power & Light Company, H. B. Robinson Steam Electric Plant Unit No. 2 FRC, 24-Nov-81

31. - Request for Additional Information: Equipment Environmental .

Qualification (EEQ); Review of Licensees' Resolution of Outstanding

'             Issnes from NRC Equipment Environmental Qualification Safety Evaluation Reports (SER) and TMI Action Plan Installed Equipment; Carolina Power & Light Company, H. B. Robinson Steam Electric Plant Unit No. 2; Revision 1 FRC, Ol-Feb-82

32. Request for Additional Information: Equipment Environmental Qualification (EEQ); Review of Licensees' Resolution of Outstanding Issues from NRC Equipment Environmental Qualification Safety l Evaluation Reports (SER) and TMI Action Plan Installed Equipment;

Carolina Power & Light Company, H. B. Robinson Steam Electric Plant i

Unit No. 2; Revision 2 FRC, 07-Apr-82 i 33. C. J. Crane and J. A. Murphy i Telecon with J. Sheppard and B. Schwager, CPL.

Subject:

Request , for Additional Information FRC, 21-Jul-81 1 As " 6-5 UO0hranidin Researc,n A OMmen of The Frenh h Center buesuee l

1 l TER-C5257-511 i l PLANT GENERIC REFERENCES 606. C. V. Fields Fan Cooler Motor Unit Test Westinghouse, 00-Apr-72 WCAP-7829 637. J. Locante and E. G. Igne Topical Report: Environmental Testing of Engineered Safety Features Related Equipment (NSSS - Nonstandard Scope). Volumes I and II. - i Westinghouse, 00-Sep-70 WCAP-7744 3 639. J. Locante j Topical Report: Environmental Testing of Engineered Safety Features Related Equipment (NSSS - Nonstandard Scope). Volumes I and II. l Westinghouse, 00-Dec-70 WCAP-7410-L, Proprietary - 640. C. V. Fields Fan Cooler Motor Unit Test Westinghouse, 00-Jan-69 WCAP-9003, Proprietary ? 645. J. P. Waggener and L. E. Witcher Qualification Tests of Pressure and Differential Pressure Transmitters Under Simulated Post-Accident Nuclear Reactor Containment Environmental Conditions FIRL, 00-Nov-69 F-C2639 , 649. Qualification Tests of Solenoid Valves by Environmental Ex-

posure ' to Elevated Temperature, Radiation, Wear Aging, Seis-mic Simulation, Vibration Endurance, Accident Radiation ...

Isomedix Inc. , 00-Jul-79 AQS21678/TR, Rev. A, Proprietary J ! 662. T. Hess, Jr. Qualification Type Test Report: Limitorque Valve Actuators for Class 1E Service Outside Primary Containment in Nuclear Power Station Service

l. Limitorque Corp. , 28-May-76 B0003 i

nklin Research Center A Oswision of The Frenidin Inseeute

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

TER-C5257-511 663. S. P. Carfagno, L. E. Witcher, and W. H. Steigelmann Qualification Test of Limitorque Valve Actuator

            ^

in a Steam Environment FIRL, 00-Feb-72 F-C3271, Proprietary 677. Report: Qualification Tests of Electric Cables Under Conditions Simulating Normal Raactor Containment Service and a Loss-of-Coolant Accident FIRL, 00-Nov-73 F-C3683 I 687. A. E. Ellis and R. B. Miller Environmental Qualification of Safety Related Class lE Process Instrumentation Westinghouse, 00-Sep-77 WCAP-9157, Proprietary 688. R. M. Satterfield I Letter to J. F. Stolz, NRC.

Subject:

Westinghouse Topical Report WCAP-9157 l USNRC, 28-Sep-79 815. L. E. Witcher and D. V. Paulson Tests of Raychem Thermofit Insulation Systems Under Simultaneous Exposure to Heat, Gamma Radiation, Steam, and Chemical Spray While Electrically Energized FIRL, 00-Jan-75 F-C4033-3 1391. G. S. Buettner and J. R. March Qualification of Firewall III, Class lE Electrical Cables Rockbestos Co., 07-Jul-77 . 15 96. S. H. Wood and L. S. Eytel Nuclear Qualification Test Procedure... For Babcock and Wilcox Valve Monitoring System Approved Engineering Test Lab, 07-Jan-81 QTP 548-8955, Rev. A 1764. H. Nordeen Qualification Test Report for Rosemount Pressure Transmitter i Model 1153 Series A ! Rosemount Inc. , 23-Mar-78 3788 i I nklin Research Center A Drasson of The Frerwen enestuee

                                                                          -TER-C5257-511
      -1887.      N. M. Burstein and L. E. Witcher Technical Report: Test of a Liquid Level Sensor Under Condi-tions Simulating a Loss-of-Coolant Accident within the Containment of a Nuclear Power Generating Station FIRL, 00-Mar-74                                                         ,

F-C3834 1888. Supplementary Test of a Liquid Level Sensor Under Conditions Simulating a Loss-of-Coolant Accident within the Containment of a Nuclear Power Generating Station FIRL, 00-Mar-74 F-C3834, Suppl. 2068. AMP Radiation Resistant PIDG Terminals AMP Incorporated, 01-Oct-78 110-11002 (formerly GPR 575-98) 2096. A. Bereza Qualification Tests for a Modular Penetration 5" Diameter (Prototype B1) Hestinghouse, 12-Nov-73 AB-11/12/73 2818. S. P. Carfagno and L. E. Witcher Technical Report: Test of Electrical Cables under Simulated Post-Accident Reactor Containment Service FIRL, 00-Oct-70 F-C2935, Proprietary 2850. Qualification Specification for Automatic Switch Co. (ASCO) of Florham Park, N. J. for Solenoid Valves Isomedix Inc. AQS-21678/Rev. B 3184. G. Butterworth and R. B. Miller Methodology for Qualifying Westinghouse WRD Supplied NSSS Safety Related Electrical Equipment Westinghouse, 00-Feb-79 WCAP-8587, Rev. 2 4281. k. E. Fleming LOCA Qualification of Kerite 1000 Volt FR/FR Control Cable, Pilgrim Nuclear Power Station Kerite Co., 18-Jul-80 4282. R. E. Fleming LOCA Qualification of Kerite 1000 Volt HTK/FR Power Cable,

 ;                Pilgrim Nuclear Power Station Kerite Co., 18-Jul-80 nklin Resear
          ~ ~-_ch         Center          .

TER-C5257-511 4423. H. Nordeen Nuclear Steam Test Performance Evaluation; Model 1153 GA9 Rosemount Inc., 24-Aug-78 37821, Rev. B t 9 m i nklin Research Center A Dmman of N rm %

TER-C5257-511 APPENDIX A - ENVIRONMENTAL SERVICE C6NDITIONS This appendix contains a summary of the information concerning expected cuvironmental service conditions in various plant locations, as provided in Rafsrences 17 and 20. Figure A-1 depicts the arrangement of the reactor centeinment and defines specific" locations where radiation levels are measured. Based on these considerations, each equipment item was evaluated with i racpset to the environmental service conditions presented in this appendix. Within Containment Normal Operation [17] Temperature: At full power 120*F (specified maximum) At shutdown 88'F (estimated) Average 115'F* l Radiation: See Figure A-1, Figure A-6, and Table A-2. The following are typical nuclear radiation exposures: Components physically 200 rd/h contacting the RC loop Components in close 50 rd/h proximity to RC loop Components outside RC loop 0.1 rd/h compartment shield (crane) wall l

      *This value is based on a plant availability of 84% and "is conservative
       -because the temperature is maintained below the specified maximum temperature l        during operation."

A-1 N Franklin Research Center A%.tn=re m

TER-C5257-511 , Accident Conditions For PWR plants, the Guidelines (Section 4)' state that the environmental l service conditions inside containment for the loss-of-coolant accident (LOCA)- should be established by the Licensee based on the Final Safety Analysis' Report (FSAR) analysis. In addition, for plants equipped with automatic containment spray systems not subject to single component failure or delayed initiation, the Guidelines state that equipment qualified for the LOCA environment is also considered qualified for the postulated main-steam-line-break accident (MSLB). The' design of the H. B. Robinson Unit 2 plant satisfies these criteria. In addition, the Licensee has stated the f ollowing with regard to the environmental parameters used for the assessment of qualification of equipment inside containment [20): [ "The SER requires the licensee to verify that the containment spray

;                                     system is not subjected to a disabling single-component failure and i                                      therefore satisfies the requirements of Section 4.2.1 of the DOR

] Guidelines. H. B. Robinson FSAR Section 6.4.3, Design Evaluation, j describes the capabilities of the containment spray system and addresses the single failure analysis for this system within Table 6.~4-4 entitled, Single Failure Analysis - Containment Spray System, (See Appendi A). As this system is not subject to a single component' failure affecting its performance the MSLB accident environment is not the limiting parameter i for qualification per the DOR Guidelines Section 4.2.1. To further , support this conclusion a study performed for NRC IE Bulletin 80-04, Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition . indicates a maximum containment pressure of 34.4 psig and a temperature of 257'F f or the f eedwater augmented MSLB." ] ! With respect to in-containment temperature / pressure profiles, the Licensee stated [20):

                                      "The SER questions the pressure value as stated in our submittals and

found within the H. B. Robinson FSAR. Apparently, a comparison with j other plants' specified pressure values is used as the basis for this

questioni ng. As reported in our prior responses to IE Bulletin 79-01B, 4 the H. 8. Robinson containment volume is 2.1 x 106 ft3 . This effectively accounts for both a lower pressure value and radiation level when defining LOCA parameters. Therefore, it is not practical to use comparisons in determining H. B. Robinson adequacy. Our FSAR has been 4

reviewed by the U. S. Atomic Energy Commission and after several A Dhimon of The FrenNin insomme 4

  - . . . _ . . _ . . , . - , _.                                           ..__.,,.__.___-__..___._._________...,m._.__..           -.-__,_.m.__           .

i-I TER-CS257-511 oxchanges requiring amendments to this document, a Safety Evaluation Report was issued on May 18, 1970 accepting the LOCA evaluation as presented for operation. Further review of LOCA conditions was performed by the AEC when the plant requestad_ permission to increase power. A Safety Evaluation Report was issued on May 20, 1974 accepting the LOCA conditions and approving power increase. Per the DOR Guidelines Section 4.1.1 Service conditions Inside containment for a Loss of Coolant Accident (LOCA), Temperature and Pressure Steam Conditions, the FSAR cualysis for containment temperature and pressure conditions is used for establishing the qualification of electrical equipment located within containment. The service condition analysis was performed by Westinghouse Electric Company and the method utilized was reported to the AEC and subsequently 4 snelosed as a Status Report by the Directorate of Licensing, dated October 15, 1974 within the Safety Evaluation Report by the Directorate of Licensing, U.S. Atomic Energy Commission for CP&L H. B. Robinson Unit

 ,                     #2, dated December 27, 1974.                                                 ~ Fee Appendix B, Westinghouse ECCS i                     Evaluation Model).

Of fur'ther note, the H. B. Robinson calculated maximum pressure casociated with a double-ended break is 38 psig (peaking at 12 seconds ofter LOCA and reducing to 32 psig after 3000 seconds). The stated 42 psig within our IE Bulletin 79-01B responses refers to the containment design pressure; therefore, a margin of approximately 11% above the conservative value of the blowdown peaks is available. H. B. Robinson Unit 2 FSAR, Section 14.3.4, Containment Integrity Evaluation, contains data and parameters associated with containment pressure. See Figure i 14.3.4-2, Containment Pressure Transients for a Range of Break Sizes,

Figure 14.3.4-4, Structural Heat Transfer Coef ficient, and Figure 14.2.4-6, Containment Capability Study, All Available Energy for graphic presentation of H. B. Robinson LOCA profiles.

Per the above, we do not believe it is justified to recalculate the LOCA pressure and temperature profiles. The conservatisms involved with the values and the tested values for equipment as recorded on the System Component Evaluation Work Sheets indicate there are no conflicting or questionable pressure and/or temperature values involved. Addressing stratification within Containment, the upper regions where stratification may affect temperature do not contain any instrumentation or equipment related to IE Bulletin 79-OlB. Only the containment fans cre located on the crane deck level (elevation 275') and their test temperature exceeds LOCA temperature by 16% (11% if the saturation temperature associated with LOCA is considered)." l l Ag A-3 branklin Research Center j A Onesson of The Fransen inessume

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

TER-C5257-511

                  . Temperature                          Figure A-2 Pressure                              Figure A-3 Pressure (Transients)                 Figure A-4                            i Pressure (Available Energy)          lFigure A-5                         .)

Humidity 100% (nominal) l Spray ~ Solution of sodium hydroxide and f boric acid in water (see note 1) Radiation See Table A-1, Note 2, Figure A-7, and Figure A-8 Flood Depth 3.2 feet (elev. 231.2 feet) Note 1:

              "The chemical spray consists of sodium hydroxide, boric acid, and -

refueling water. Mixing of the refueling water from the refueling water storage tank, the boric acid from the boric acid tank, the borated water contained within the accumulators, and primary coolant will bring the weight percent solution caustic and 1.7 weight percent boric acid. This maintains a pH of at least 9.3. Spray additive educators are designed to provide enough sodium hydroxide in the mixture so as not to exceed pH 10 during the injection phase." Note 2: With respect to radiation inside containment, the Licensee stated [20]:

              "The SER second paragraph for Section 3.8_ states that the values              '

submitted within CP&L's H. B. Robinson 90-day response do not envelop the DOR Guidelines (4 x 107 rads) requirement and therefore are not acceptable. Radiation values listed on the submitted System Component Evaluation Work Sheets within the specification column reflect a series of calculations based upon containment volume, internal shielding, and instrumentation /- equipment location. These calculations follow the procedures referenced as acceptable in the DOR Guidelines and provided within Appendix B. Sample calculations and representative nomogram use were presented as Appendix A within CP&L 90-day submittals; Rev. O, Rev.1, Rev.- 2, and Rev. 3. Of note is the reduced level radiation number due to oversized l containmentvolume (2.1 x 106 ft3) and shield wall thickness (36 l inches) when using the nomograms. Each instrument or equipment as represented on the work sheets was dimensioned by level within containment or Reactor ' Auxiliary Building and located by compartment or shield wall to determine the maximum radiation level experienced under LOCA conditions. This figure was added to the normal operating radiation l dose (40 year life) and a margin assigned. Section 1.3.2 of the i H. B. Robinson 90-day Rev. ~ 3 report provides additional insight into the assigned radiation levels. Individual dosages used on the work sheets l l A -4 t ! Olq Franidin Research Center ! Aom n.tw r m u.

i l TER-CS257-511 . cre' summarized and listed in Table 1.3.3 of the above mentior.ed report. For review purposes, response ' submitted figures and tables are included in this section to aid in evaluation of our radiation assignments. When operating time for equipment / instrumentation was less than one (1) hour, a minimum of one (1) hour was picked for establishing dosage reduction based on the nomogram entitled 30 Day Dose Connection Factor vs. Time Required to Remain Functional (HRS). This should establish sufficient margin and encompass existing test data. For items located close to sump water flooding -levels an additional radiation dosage was assigned based on actual operating time. As stated in Table 1.3.3 Notes (8) & (9), data used can be found in NUREG-0588, Appendix D Table D-8, Containment Sump Gamma Dose Rates and Integrated i Dose Versus Time. Beta radiation was considered using Appendix C, Table D-6, Beta Dose Rates and Integrated Doses at the Containment Center Versus Time in Air. Based on the time of operation, equipment location, shield wall

 !      .cbsorption, compartment wall absorption, insulation thickness, instrumentation housing absorption, motor case shielding, et. al. , beta contribution is less than 10% of the total gamma dose experienced by the l         listed equipment. This is a conservative assumption based on the DOR Guidelines requirement of the beta dose to be less than or equal to 10%

of the total gamma dose to which an item of equipment has been qualified. l The above is the basis, assumptions,. and basic analysis of the option chosen to justify the choice of lower service conditions than the ! generalized screening radiation service value stated in the SER and ~ presented at the NRC 79-01B meeting held in Bethesda, Maryland on July 7-10, 1981. Sample calculations as included in our 90-day, Revision 3 l response to IE Bulletin 79-OlB are repeated as Appendix C of this report." Outside Containment , With respect to environmental service conditions outside containment, the Liczncee stated [20): o "As stated in the SER, ambient temperature conditions have been used in some areas outside containment. As H. B. Robinson 2 has master i listed equipment located on the turbine deck which is an open air area, it is impractical to utilize an arbitrary value such as ambient I saturation temperature for qualification purposes. Therefore, the l System Component Work Sheets listing turbine Deck Area location will not be summarily revised. Considering the Auxiliary Building, the following quote from the Report entitled: H. B. Robinson No. 2 Postulated Pipe Failure Analysis Outside of Containment, Section 10.0 Description of Compartment Environmental Ef fects Analysis, indicates only one A A-5 branklin Research Center A Dheemn of The Fransen sneutuee

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

TER-C5257-511 4 enclosed volume subject to pressure and temperature buildup following rupture. This is the pipe penetration gallery. An analysis indicates a calculated pressure buildup of 0.2 psi and a maximum temperature , increase of 2.4*F. This consequance is the result of the limiting-  ; 4 postulated steam generator blowdown line rupture. These limiting 1 environmental <onditions will have no effect on the structural adequacy of the auxiliary building or on plant operation. It would be arbitrary to assume the ambient saturation temperature for equipment qualification purposes. Review of the System Component Work Sheets

designated within the Reactor Auxiliary Building show qualification l temperatures well in excess of the area requirement. Therefore, the System Component Work Sheets for the Reactor Auxiliary Building will not be changed to reflect a screening number when actual conditions have been calculated."

l o " Temperature in the control room and electronic equipment areas is . maintained at 70*F + 10*F by air conditioning. When considered over the plant life, the down time of air conditioning is negligible. Therefore, the 40 year average ambient. temperature of these areas is less than 80*F. For other areas outside containment in which safety related equipment may be located such as the auxiliary building the ambient temperature is subject to seasonal variation. The estimated 40 year average ambient temperature is 85'F in these areas. This estimate assumes 100*F summer and 70*F winter temperatures. Normal radiation in the control and electronic equipment rooms is less than 0.2 milli-rad per hottr and is therefore insignificant and does not degrade any component over the 40 year plant life. The radiation environment at majority of other Class IE equipment locations outside the containment is correspondingly insignificant. However, the radiation parameters will be considered in the qualification of any ' additional Class 1E equipment which may be located in a significant i i radiation field [17]." , Pipe Penetration Gallery (Auxiliary Building) Temperature Ambient + 2.4*F Pressure Ambient + 0.2 pai i i A A -6 bhranklin Research Center A Chesson of The Frenthn h sueute

TER-C5257-511 l

                                                                                                                                      \

O Operating Floor

                                     -          Compartment Q~._~ %]

0 0 f, p _ _ _ __ m, , ____._____

                     . _ _ .1_ _ _ 4_ _ _ _ _ __,_ _ p_g                                                    7g,n,_  _ _ _ _ _
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                ! l'"                                                           / c~l~."                          ll                    Equipment
                           ~~ ~!_~_'~, l ( )fi Id 8--]_~'ll                                                                     N              ***"*

____.[' l

                                   >                                                 8 i      i t

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                        -          I                                                .:      ii               iI ,i1 i               e t)         '                                                1n      l
                                                                                            .      'O!f.i i          t      i l
 'A            _

N *

 ?                                               ,

s . (Arrangement rotated for graphic presentation) l 1 CV Operating Deck (Pressurizer) 2 CV Lower Level Polar Crane Wall (Rcgen. Heat Exchanger) 3 CV Second Level Seal Tr. ole Room 4 RCactor Coolant Pump Bay A 5 Reactor Coolant Pump Bay B' FIGURE SUPPUED 6 Reactor Coolant Pump Bay C BY THE LICENSEE Figure A-1. H. B. Robinson Reactor Containment Radiation Level Neasurement Locations nklin Researd Center

                                                                 ^^
       ~ ~ . - -
                                     . - _ .         . _ . . _ _ - - - _ .                      _ _ _ _ . -               . - _ _ _         -.      __ ~

                =

at 00 - ENVIRONMENTAL CONDITIONS g"g, 350 FOR EQUIPHENT TESTING TEMERAW RE VS TIME Y

r A 300 - 286*F Test Conditions i3 g 264.7'F HBR . Conditions m 250 -

g ' 219'F 200 - T 152'F co y . 150 - 8 100 -

                                         ' 50   -

1 I I i 10 see 1 hour'10,000 secs. 1' day M

                                              ,                                                                          TIME                                    [
                                                                                                                                                                 ~

Figure A-2. Containment Temperature vs. Time Following LOCA/MSLB [17] FIGURE SUPPLIED

c-E ENVIRONMElffAL CONDITIONS 90 -

   >h                                      FOR EQUIPMENT TESTING h

80 - PRESSURE VS TIME l fe$.

   's4 S        3     -

l D, .E .70 5 60 PSIG TestCondEtions y 60 - a in

• l 50 -

42 PSIG HBg Conditions . d 8 30 -

                                                                                   . 20 PSIG               .

! g. 20 ,

o. .

!  ! 10 - f, .5 PSIG u

                          ,, g .,    ...... . .. ...          .__                1
                                                                          , 4 9 9g   ,        .g.g             . . ..                                   . . . . . . . _

g TIHR f a Figure A-3. Containment Pressure vs. Time Following LOCA/MSLB [17] O y w FIGURE SUPPLIED BY THE LICENSEE

              ,                                                               A RANGE OF BR       S IN. SAFETY FEA1URES OPERATING)
             !!                 IWE lllE                                                    ll100llWE ElllllHOOMEX Il    "lIll  ll Illlit              lilll!!!rE Qll"R                            IlllHIEEn                        lillllHOIEE Ei ER

I!

' "Ill IE E ELlil!!l!!llIl llllll BL E llililliER E lillHORIERGEL

                ' lll lE illi IllHH lllIlO QR E lilllillWllK EtllillllHEE El i

lillHO REMElillHIREE ME kit l"Illlll .!ln ll!!f Il!!!IllillE ll!!r I!!!IllillK1l epi!!!!IllEEEIE ele E i l IR E lilHO Ek E ll10H1EEEELlilHHIlilDRslEk i"lll $llE E E lilHH EE R lilHRIM E K llHHOWEE M Ek 0 1 IR W R R llHIH M E F lillHH E E k E r lilHlHW E R E E 10 100 1000 b ~ FIGURE SUPPLIED k

                            '                                                                            BY THE LICENSEE                     O L                          :

Figure A-4. Containment Pressure Transients [17] ' l __-_. - - -- ._ - .

CONTAIttfENT CAPABILITY STUDY ALL AVAILABLE ENERGY 35 a,5 N '! 40' . [ , y j i - -- 0l I T Ig. g:: --- "' '

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                                                                                                                                                                                            ;                I                                           l i::~                                           ,ture witti continued addition of                                                                     1

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        % 30      .

d- - the care. residual energy and bot ' ' s  ! I

                                                                                                                                                                                                                                                         'r'!l

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                                                                                                                                                                                                                                               ,i 0

1 10 100 1000 7 T HE, SECONDS FIGURE SUPPLIED d I BY THE LICENSEE 5 Figure A-5. Containment Pressure (all available energy)

H. B. ROBINSON CONTAINHENT RADIATION LEVEL MEASUREMENTS c= ES ' Recording Stations

• 9 1. CV Operating Deck (pressurizer)

E Note 1 E3 2. RADS MREMS CV Lower Level Polar Crane Wall 27 (Regen. Heat Exchanger) 3 6 9 10 10 [2 r

                          = r:g                                                                                                      3. CV Second Level - Seal Table Room
                                                                                              ,                                      4. Reactor Coolant Pump BAY-A
                          *$'          10     10        .

f A. 5. Reactor Coolant Pump BAY-B

                                                                                                      /        \
                                                                                                   / /           N                   6. Reactor Coolant Pump BAY-C 4      7                                            8,/     /A           N 10     10        -

_ _/ /f -f - sq%

                                                                                      //

6 f NN 10 10 .

                                                                                    /         i                             N   N.
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                                >                           g                                                                    \

h n 10 2 10 8 m-

                                                                                                - ~ ~ ~

1 4 - 2 10 10 - -- 8 g _. '" * -- ' ' 3 - 10 10 , e ! 2 Notes: 10 1 No data recorded for the 1 , year 1976 10 - H

                                                                                                                                           .     . Known data         N

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                                                                                                                                                                                                                                                                                                                                                                                                                         ^"                                    " I A an                                                                                                                                                                                                                                                                                                                                                                                                                                           Figure 3.1.3 OUUJ Franklin Research Center 1-14 A Dhanson of The Franhan insatute
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T:ble A-1. Equipment Tctcl Radiction Accumuletion [17] EQUIPMENT TOTAL RADIATION ACl'JMULATION 3Y LOCATION AND LOCA OPERATING TIME TER-C5257-511 Camponens Location Level (f t) Time of Radiation t p. Acetdeas I3) Marsta Total Aat141pete4 ( A eo row. ) coerne ton f40 n s)(1 tadiation Esp. (10%) Lsetation Exposure TRANsMITTT1ts 3 PT-444(2) CT 231.3 30 m !'I 2.3 a 10 9.3 a 10 - 1.0 m 1 FT 443(2) CT 231.3 30 m!N 2.3 a 10 3 9.3 x 10 3 , t 0 ,1,f 3 3 6 FT-436(2) CY 231.3 30 m !'I 2.3 a 10 9.3 a 10 - 1.0 a 10 2 3 FT-437(2) CT 231.5 30 m !'I 2.3 s 10 9.3 x 10 - 1.0 a 10' 0 FT-433 CT 231.38 30 m b 2.3 a 10 g.3 a 10 - 1.0 a 10 0 LT-474 CT ' 233 1 DAT 2.3 x 10 3 3.5 s 10 3.3 a 10 3 3.3 a 10 0 6 3 0 LT-473 CT 233 1 DAY 2.3 a 10 3 3.5 a 10 3,3 , gg 3.4 s 10 0 3 1T.476 CT 233 1 DAT 2.3 s 10 3 3.3 s 10 3.3 a 10 3.8 a 10' 3 0 3 LT-477 cv 233 1 DAT 2.3 s 10 3.3 s 10 3.3 x 10 3.8 a 10' . 233 1 DAT 2.3 s 10 3 3.3 a 10 6 3,3 ,gg 3 3,g ,gg 6 LT-AaA CT LT-443 CT 233 1 DAT 2.3 a 10 3 3.3 s 10 6 3,3 ,gg3 ' 3.8 a 10 6 0 0 LT-446 CT 233 1 DAY 2.3 s 103 3.3 a 10 3.3 s 103 3.3 a 10

           -447           CT           233         1 DAT         2.3 s 10 3       3.3 s 10 6

3.3 s 10 3 3.8 a 10' LT-494 cv 233 1 DAT 2.3 s 10 3 3.3 s 10 6 3,3 ,gg*3 3.8 x 10' 3 3 0 LT-493 CT 233 1 DAT 2.3 a 10 3.3 a 10 3.3 a 10 3.a a 10 3 0 LT-494 CT 233 1 DAT 2.3 a 10 3 3.3 a 10 3.3 a 10 3.8 a 10 0 12-497 CT 233 1 DAT 2.3 a 103 3.3 a 10' 3.3 s 103 3.8 a 10 LT-439(2) CT 130 30 m!'I 2.3 a 103 9.3 a 103 - 9.3 a 103 LT-440(2) CT 230 30 m!'I 2.3 s 103 9.3 10 3 - 9.3 a 103 3 3 1T.461(2) CT 230 30m!'I 2.3 a 10 9.3 a 10 - 9.3 s 1E FT-474 CT 231.3 1 DAY 2.3 a 10 3.3 a 10 3.3 a 10 3.0 s 10 3 0 3 231.3 2.3 s 10 3.3 s 10 3.3 a 10 FT-473 CY 1 DAT 3.0 a 10' 6 W , FT-444 CT 231.3 1 DAT 2.3 s 103 3.3 a 10 6 3.3 1 10' 3.0.3.10 Q 3 0 3 7T-443 CT 231.3 1 DAT 2.3 a 10 3.3 a 10 3.3 s 10 3.0 a 10' 3 FT-494 CT 231.3 1 DAT 2.3 a 103 3.3 a 10 6 3.3 a 10 3.0 a 10' FT.493 CT 231.3 1 DAY 2.3 a 10 3.3 a 10 3.3 s 10 3 3.0 s 10 6 N (6) 1.1 s 100 FT-940 RAS 230 30 DAYS 1.0 s 10 (6) 1.0 a 10 FT-943 3AS 230 30 DATS - 1.0 a 10 1.0 a 10 1.1 x 10 0 3 0 FT-934 RAS 230 30 DAYS - 1.0 a 10 1.0 m 10 1.1 a 10 FT-940 RAS 230 30 QAYS - 1.0 s 10 1.0 a 10 1.1 a 10 FT-943 ' aAs 230 30 DAYS - 1.0 a 10 1.0 a 10 1.1 a 10 M

         .T-646A           CY            241         1&           2.3 a 10 3       9.3 s 10         9.3 s 10'        1.0 a 10*

f Y-4468 CT 241 1E 1.3 a 10 9.3 a 10 9.3 a 10 1.0 a 10 0 3 6 . V869 RAS 241 30 DATS - 1.0 a 10 1.0 a 10 1.1 a 10 l 3 T-744A CT tto 3Mts!'I 2.3 a 10 9.3 a 10 - 9.3 10 V-7 44 6 CT 260 3 MIN!"I ,2.3 10 3 9.3 a 10 3 - 9.3 x 10 3

                                                                                                                                          ^

FIGURE SUPPLIED A-15 BY THE LICENSEE N nkiin a.3.orCn cen(er A Dewmon of The Franhan heuture

Table A-l. (Co nt. ) EQUIPMENT TOTAL RADIATION ACCUMULATION BY LOCATION TER-C5257-511 AND LOCA OPERATING TIME Ceeposest Laceties Level (ft) Time of Radiaties Emp Accidest(3I Marste Total Anticipated (A pp res. ) Oseretten (40 ves)(1) tadiattee Esp. (102) udiation Emeesure V-4404 RAS 212 30 DAYS - 1.0 a 10 0 1.0 m 10 5 1.1 a 10' 6 v 460s RAS 212 30 DAfs - 1.0 a 10 1.0 a 10 5 1.1 a 10 T-setA ras 212 30 DAT3 - 1.0 x 10 6 1.1 a 10 1.1 a 10 Y-4618 11Aa 212 30 QAYS - 1.0 a 10 6 1.1 a 10 1.1 a 10 6 I v-443A 0 5 6 l RAS . , 212 30 DAYS - 1.0 x 10 1.1 x 10 1.1 a 10 6 0 v-4633 ras 212 30 Ot.YS - ' 1.0 x 10 1.1 x 10 1.1 x 1 0 CYC-341 RAS 240 30 DAYS - 1.0 x 10 1.1 x 10 3 1.1 x 10 $ Sotte0TDS T12-7 CT 233 5MIMb 2.3 x 103 9.3 x 105 , g,3 ,gg5 3 712-9 CT 233 3MIr$'I 2.3 s 10 3 9.3 x 10 - 9.5 x'osl T12-11 CY 233 5MIM!'I 2.3 x 103 9.3 a 103 - 9.5 's 10 3 Y12-13 CT 233 5 xmf'I 2.3 x 103 9.3 x 10 - 9.3 x 103 MOTORS Eva-1 C7 273 3 Ens. 1.9 x 102 3.1 x 10 0 3.1 a 10 3 3.4 x 10'

 '                                                                   2 sys-2          CT        275        3 Eks.      1.9 x 10           3.1 x 10   3.1 s 10  3 3.4 x 10 6 E73-3                                                    2 CT        273        3 ERS.      1.9 x 10           3.1 x 10   3.1 a 10'     3.4 a 10 395-4          CT        275        3 as.       1.9 z 102          3,g , gg 6 3,g ,gg 3     3,4 ,gg 6 E12CTRtcAL PDM

• RATIONS Type 2 CT 234 -244 30 2.3 x 10 3 . - 1.6 x 10 mrmtm 11EMElff3 TI-4123 CT 243 (7) 1.1 x 10 0 - - 1.3 a 107 TE-412D C7 243 (7) 1.1 s 10 0 - . - 1.3 10 I

TE-422's C7 243 (7) 1.1 x 10 6 - - 1.5 x 10 I TI-422D CT 243 (7) 1.1 x 10 - - 1.3 a 10 243 6 I3) TE-4323 CT (7) 1.1 a 10 = = 1.3 a 10 F TE-432D C7 243 (7) 1.1 x 10" - - 1.3 3 107 I1I tatropelated from plaat data (See Table 1.3.1) j (2)t4mipment Leested in imetrummet cabinets. II Calculatten based es 1E Su11stia 79-013. Appendia S. CMART3/CRAFES. Frecedures for traluattag Cams Radiattee Service Condittees. Charts /Craphe per IC Sulletas 79-013. Appendia S alleu calculaties to a sintaus of 1 hour

         ,  espesure. This figure is cesservative--ee mergia required.                             -

I , Total Estegrated Radiattee for accident condittee (30 days) per 1E Su11stin 79-013. Ap=eedtz s. l CMART5/CIAFMS. Calculattoe base 4 es Accident Radiation figure - 2 a 10 RADS. Not required for Det--used only for outside contatement *tLS protecties. Includen .mided 7.9 s 10 4 ADS for 1 hour recal 1stentares gamma dose at the surface of concatament aus, unter ( rer Appendia 0. Table 3-4. MtitKC 0534).

• Includeo Mded 1.15 a 10" 4 ADS for i day total toteerstra c.weis deee at the surface of M

testatament same meter ( Per Aeoendts 3. Taste D-4. Isuus t; Osas). - A A-16 FIGURE SUPPLIED dEranklin,n,esearch me e r-e R center BY THE LICENSEE

I-TER-C5257-511 Table A-2. Calculated Radiation Accumulation TABLE 1.3.1 H. B. ROBINSON CALCULATED RADIATION ACCUMULATION AREA YR. ACCUM. 40 YR. ACC ELEV.(ft) lM

1. CV Operating Deck (Pressurizer) 4.8 x 10 '1.9 x 102 280

2. CV Lower Level Polar Crane 5.7 x 10 2.3 x 10 233

3. CV Second Level-Seal Table Rm. 8.5 x 10 3.4 x 10 254

4. Reactor Coolant Pump - Bay A 1.1 x 10' 4.4 x 10 243 6

5. Reactor Coolant Pump - Bay B 2.8 x 10' 1.1 x 10 243

6. Reactor Coolant Pump - Bay C- 9.6 x 10 3 3.9 x 10 243 A

3 7.2 x 10 2.9 x 10 (1) See. figure 1.3.1 for locations. (2) Calculations in (RADS) (3) Total Contaizunent (Averaged) TABLE 1.3.2 REACTOR COOLANT SYSTDi DOSES l LOCATION DOSE r/hr l PIPE CENTER 820 l i l PIPE ID 470 f-

         .                     PIPE OD                   200 n m m. AREA                5 FIGURE SUPPLIED BY THE LICENSEE
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Research Center

TER-C5257-511 1 APPENDIX B - LISTING OF SAFETY-RELATED ELECTRICAL EQUIPMENT The following table lists the groupings of safety-related electrical cquipm:nt items for the H. B. Robinson Unit 2 Nuclear Power Plant. Equipment itema provided in the table are used in the detailed equipment environmental qualification evaluation presented in Section 4.4 and summarized in Section 4.2. This table was generated from the lists of equipment provided by the Liesnase [15, 20). The Licensee identified an extensive list of safety-related electrical cquipm:nt in various locations of the plant. The equipment listed by the Licznsse was analyzed, and all identical equipment located within plant areas that are exposed to the same environmental service conditions was grouped togsthar and designated an " equipment item." In this report, the term "squipment item" refers to a specific type of electrical equipment, designated by nanufacturer and model, which is representative of all identical equipment in a plant area exposed to the same environmental service conditions (e.g., Flow Transmitter, Fischer & Porter, Model 10B2496, located within containment). This analysis resulted in a reduced listing of equipment (equipment items) thIt formed the basis for the review. This appendix contains the tabulation of tha equipment items, locations, function, plant identification numbers, raquirsd operating time, and applicable qualification documentation references. 4 B-1 0000 Franklin Research Center e A om.on or n. rr=*aa in.ou.

4 TER-C5257-511 EQUIPMENT ITEM NO. 1 (TMI ACTION PLAN ITEM II.E.4.2) SOLENOID VALVE LOCATED IN THE REACTOR AUXILIARY BLDG. ASCO MODEL LB8320A185 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 1 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): FUNCTION AND PLANT ID NOT STATED I LICENSEE SUBMITTAL: SCEW(S): 8 0F 15 [15] EQUIPMENT ITEM NO. 2 SOLENOID VALVE LOCATED IN THE CONTAINMENT, ELEV. 283'0" ASCO MODEL NP831665E REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. 2 LICENSEE REFERENCE (S): 40, 649 FUNCTION (PLANT ID): NOT STATED (V12-7, -9, -11, -13; CVC-200A, B, C) LICENSEE SUBMITTAL: SCEW(S): 20 0F 25 [20] EQUIPMENT ITEM No. 3 SOLEN 0ID VALVE LOCATED IN THE CONTAINMENT, ELEV. 283'0" ASCO MODEL NP8316E35E REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET No. 3 LICENSEE REFERENCE (S): 40, 649 FUNCTION (PLANT ID): NOT STATED (V12-7, -9, -11, -13; CVC-200A, B, C) LICENSEE SUBMITTAL: SCEW(S): 20 0F 25 [20] , EQUIPMENT ITEM NO. 4 SOLENOID VALVE LOCATED IN THE CCNTAINMENT, ELEV. 283'0" ASCO MODEL 2063812U REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. 4 ._ LICENSEE REFERENCE (S): 40, 649 FUNCTION (PLANT ID): NOT STATED (V12-7, -9, -11, -13; CVC-200A, B, C) LICENSEE SUBMITTAL: SCEW(S): 20 0F 25 [20] EQUIPMENT ITEM NO. 5 MOIORIZED VALVE ACTUATOR LOCATED IN THE CONTAINMENT, ELEV. 241'0" LIMITORQUE MODEL SMB00 WITH PEERLESS MOTOR, CLASS B INSULATION REQUIRED OPERATING TIME: 1 HOUR TER CHECKSHEET NO. 5 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): ACTUATES HOT LEG INJECTION VALVES (V-866A, B)- LICENSEE SUBMITTAL: SCEW(S): 6 0F 25 [20] h -mem.m..

TER-C5257-511 EQUIPMENT ITEM NO. 6 MOTORIZED VALVE ACTUAIOR LOCATED IN TIIE CONTAINMENT, ELEV. 245' LIMITORQUE MODEL SMB3 WITH RELIANCE MOTOR, CLASS H INSULATION; MOTOR BRAKE, CLASS B INSULATION REQUIRED OPERATING TIME: 5 MINUTES TER CHECKSHEET NO. i LICENSEE REFERENCE (S):- 637, 639 FUNCTION (PLANT ID): ACTUATES REACTOR CORE DELUGE VALVES (V-744A, B) LICENSEE SUBMITT!.L: SCEW(S): 9 OF 25 [20] EQUIPMENT ITEM NO. 7 MOTORZZED VALVE ACTUATOR LOCATLD IN THE REACTOR AUXILIARY BLDG. LI'.4ITORQUE MODEL SMB00 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 7 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): ACTUATES HOT LEG IRJECTION BORON INJECTION VALVE (V869) LICENSEE SUBMITTAL: SCEW(S): 7 0F 25 [20] FUNCTION (PLANT ID): ACTUATES RHR DISCHARGE TO SI SPRAY SYSTEM VALVES (V863A, B)

• LICENSEE SUBMITTAL: SCEW(S): 12 OF 25 [20]

FUNCTION (PLANT ID): ACTUATES REACTOR COOLANT PUMP SEA'L WATER RETURN VALVE (CVC-381) LICENSEE SUBMITTAL: SCEW(S): 23 0F 25 [20] EQUIPMENT ITEM NO. 8 MOTORIZED VALVE ACTUATOR LOCATED IN THE REACTOR AUXILIARY BLDG. LIMITORQUE MODEL SMB1 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 8 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): ACTUATES CV SUMP TO RHR SUCTION VALVES (V860A, B) LYCENSEE SUBMITTAL: SCEW(S): 10 0F 25 (20] FUNCTION (PLANT ID): ACTUATES CV SUMP TO RHR SUCTION VALVES (V861A, B) LICENSEE SUBMITTAL: SCEW(S): 11 OF 25 [20] EQUIPMENT ITEM NO. 9 FLOW TRANSMITTER LOCATED IN THE REACTOR AUXILIARY BLDG. FISCHER AND PORTER MODEL 10B2496PBBABBB REQUIRED OPERATING TIME: 30 DAYS TER CHECKSHEET NO. 9 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): MONITORS SAFETY INJECTION HEADER HOT LEG FLOW (FT-940) LICENSEE SUBMITTAL: SCEW(S): 1 0F 25 (20] FUNCTION (PLANT ID): MONITORS SAFETY IRJECTION HEADER HOT LEG FLOW (FT-943) LICENSEE SUBMITTAL: SCEW(S): 2 0F 25 (20] kdED.*

TER-C5257-511 EQUIPMENT ITEM NO. 10 PRESSURE TRANSMITTER LOCATED IN THE REACTOR AUXILIARY BLDG. FISCHER AND PORTER MODEL 50EP1041BCXA REQUIRED OPERATING TIME: 30 DAYS TER CHECKSHEET NO. 10 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): BORON INJECTION TANK HEADER PRESSURE (PT-934) LICENSEE SUBMITTAL: SGW(S ) : 3 0F 25 [20] FUNCTION (PLANT ID): SAFETY INJECTION TANK HEADER PRESSURE (PT-943) LICENSEE SUBMITTAL: SGW(S ) : 5 0F 25 [20] EQUIPMENT ITEM NO. 11 PRESSURE TRANSMITTER LOCATED IN THE REACTOR AUXILIABY BLDG. FISCHER AND PORTER MODEL 50EP1041 EQUIRED OPERATING TIME: 30 DAYS rER CHECKSHEET NO. 11 LIGNSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): SAFETY INJECTION HOT LEG HEADER PRESSURE (PT-940) LICENSEE SUBMITTAL: SGW(S ) : 4 0F 25 [20] EQUIPMENT ITEM NO.12 PRESSURE TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT MODEL 1153A REQUIRED OPERATING TIME: 30 MIN (TABLE 1.3.3) TER CHECKSHEET NO. 12 LICENSEE PEFERENCE(S): 1764, 4423 f FUNCTION i F' ANT ID): PRESSURIZER PRESSURE CONTROL Slt.iAL (PT-444) { FUNCTION (PLAT.T ID): PPISSURIZER PRESSUSE SIGNAL "0R SIS INITIATION (PT-455) FUNCTION (PLANT ID): FUNCTION NOT STATED (PT-44 5, -456, -457) LICENSEE SUBMITTAL: SCEW(S): 19 0F 25 [20] EQUIPMENT ITEM No. 13 LEVEL TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT MODEL 1153A REQUIRED OPERATING TIME: 30 MIN TER CHECKSHEET NO. 13 LICENSEE REFERENCE (S): 1764, 4423 FUNCTION (PLANT ID): NOT ST ATED ( LT-4 7 5, -4 7 6, -4 8 5, -4 86, -4 9 5, -4 9 6, -4 9 7) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR A NARROW RANGE LEVEL (LT-474) a FUNCTION (PLANT ID): MONITORS STEAM GENERATOR A WIDE RANGE LEVEL (LT-477) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR B NARROW RANGE LEVEL (LT-484) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR B WIDE RANGE LEVEL (LT-487) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR C NARROW RANGE LEVEL (LT-494) FUNCTION (PLANT ID): MONITORS STEAM GENERATOR C WIDE RANGE LEVEL (LT-491) FU NCT ION ( PLANT ID ) : MONITORr PRESSURIZER LEVEL AND ACTUATES SIS (LT-459,

                                           -4 60, - 51)

LICENSEE SUBMITTAL: SGW( S ) : 19 0F 25 [20] l g B-4

                     ~ WA WlW?.*

1

                                                         <TER-C5257-511 EQUIPMENT ITEM NO. 14 FLOW TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT HODEL 1153A REQUIRED OPERATING TINE: 1 HOUR TO 1 DAY TER CHECKSHEET NO. 14 LICENSEE REFERENCE (S): 1764, 4423 FUNCTION (PLANT ID): MONITORS MAIN STEAM FLOW LOOP A (FT-474, -475)

FUNCTION (PLANT ID): MONITORS MAIN STEAM FLOW LOOP B (FT-484, -485) FUNCTION (PLANT ID): MONITORS MAIN STEAM FLOW LOOP C (FT-494, -495) LICENSEE SUBMITTAL: SCEW(S): 19 0F 25 (20] EQUIPMENT ITEM No.15 (TMI ACTION PLAN ITLM II.F.2) PRESSURE TRANSMITTER LOCATED IN THE CONTAINMENT ROSEMOUNT MODEL 1153GA9 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 15 LICENSEE REFERENCE (S): 1764, 4423 , FUNCTION (PLANT ID): DETECTION OF INADEQUATE CORE COOLING (PT-500, -501) LICENSEE SUBMITTAL: SCEW(S): 6 0F 15 [15] EQUIPMENT ITEM NO.16 (TMI ACTION PLAN ITEM II.F.15) LEVEL TRANSMITTER LOCATED IN THE C0hTAINMENT GEMS MODEL XM52495 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 16 LICENSEE REFERENCE (S): 1887 FUNCTION (PLANT ID): CONTAINMENT SUMP WATER LEVEL (LT-801A, B, C, D) LICENSEE SUBMITTAL: SCEW(S): 12 of 15 [15] EQUIPMENT ITEM NO.17 LEVEL TRANSMITTER LOCATED IN THE CONTAINMENT GEMS MODEL XM36495 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 17 LICENSEE REFERENCE (S): 1887 FUNCTION (PLANT ID): CONTAINMENT SUMP WATER LEVEL (LT-802A, B, C, D) LICENSEE SUBMITTAL: SCEW(S): 13 of 15 [15] B-5 o r=sw:2.se

( TER-C5257-511 EQUIPMENT ITEM NO. 18 TEMPERATURE ELEMENT LOCATED IN THE CONTAINMENT, ELEV. 243'0" ROSEMOUNT MODEL 176KF REQUIRED OPERATING TIME: 1 HOUR TER CHECKSHEET NO. 18 LICENSEE REFERENCE (S): 687 FUNCTION (PLANT ID): MAIN STEAM LINE BREAK DETECTION, LOOP 1 (TE-412B, D) LICENSEE SUBMITTAL: SCEW(S): 14 0F 25 [20] FUNCTION (PLANT ID): MAIN STEAM LINE BREAK DETECTION, LOOP 2 (TE-422B, D) LICENSEE SL'BMITTAL: SCEW(S): 15 0F 25 [20] FUNCTION (PLANT ID): MAIN STEAM LINE BREAK DETECTION, LOOP 3 (TE-432B, D) LICENSEE SUBMITTAL: SCEW(S): 16 0F 25 [20] EQUIPMENT ITEM NO. 19 LEVEL SWITCH LOCATED IN THE CONTAINMENT, ELEV. 228'0" MADISON MODEL 5602 REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 19 LICENSEE REFERENCE (S): NOT CITED FUNCTION (PLANT ID): CONTAINMENT SUMP WATER LEVEL MEASUREMENT (LS-1925A, B) LICENSEE SUBMITTAL: SCEW(S): 8 OF 25 [20] EQUIPMENT ITEM NO. 20 (TMI ACTION PLAN ITEM II.D.3) ACCELEROMETER LOCATED IN THE CONTAINMENT ENDEVCO MODEL 2273AM20 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 20 LICENSEE REFERENCE (S): 1596 FUNCTION (PLANT ID): NOT STATED (A, B, C) LICENSEE SUBMITTAL: SCEW(S): 2 0F 15 [15] EQUIPMENT ITEM NO. 21 (TMI ACTION PLAN ITEM II.D.3) AMPLIFIER LOCATED IN THF. CONTAINMENT UNHOLTZ-DICKIE MODt.L 22CA2TR REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 21 LICENSEE REFERENCE (S): 1596 FUNCTION (PLANT ID): NOT STATED (A, B, C) LICENSEE SUBMITTAL: SCEW(S): 3 0F 15 [15] l l l l

                            /k L Franklin Research Center a tum.on oe Th. Fr.non in iu

TER-C5257-511 EQUIPMENT ITEM NO. 22 ELECTRIC MOIOR LOCATED IN THE REACTOR AUXILIARY BLDG. - WESTINGHOUSE MODEL 506UPZ REQUZRED OPERATING TIME: CONTINUOUS TER CHEGSHEET NO. 22 LICENSEE REFERENCE (S): 606, 3184 FUNCTION (PLANT ID): DRIVES RHR PUMP - SIS (RHR-A, B) .. LICENSEE SUBMITTAL: SCEW(S): 13 0F 25 [20]

                                                                 ~                                                                 -

EQUIPMENT ITEM No. 23 ELECTRIC MOTOR LOCATED IN THE CONTAINMENT, ELEV. 275'0" WESTINGHOUSE MODEL 685.5S REQUIRED OPERATING TIME: 3 HOURS TER CHEGSHEET NO. 23 LICENSEE REFERENCE (S): 639, 640 - FUNCTION (PLANT ID): DRIVES CONTAINMENT FAN COOLER (HVH-1, -2, -3, -4) LICENSEE SUBMITTAL: SCEW(S): 17 0F 25 [20] . E EQUIPMENT ITEM NO. 24 ELECTRICAL PENETRATION LOCATED IN.THE CONTAINMENT, ELEV. 234'-246' CROUSE-HINDS MODELS 1.2.2 (745), 1.2.2 (747), 1.2.4 (749), 1.2.5 (751) REQUIRED OPERATING TIME: CONTINUOUS TER CHEGSHEET NO. 24 - LICENSEE REFERENCE (S): 25, 2096 . FUNCTION (PLANT ID): ELECTRICAL DISTRIBUTION (B-1, -2, -5, -9; C-1, "fl 3,

                              -4, -6, -8, -9; D-1, -2, -3, -5, -8, -9)                                                                ,

LICENSEE SUBMITTAL: SCEW(S): 18 0F 25 (20] - EQUIPMENT ITEM NO. 25 ELECTRICAL CABLE LOCATED IN THE CONTAINMENT CONTINENTAL WIRE AND CABLE MODEL CC2115 _- . REQUIPID OPERATING TIME: CONTINUOUS - TER CHEGSHEET NO. 25 . _. 2818 LICENSEE REFERENCE (S): INSTRUMENTATION CABLE 4 FUNCTION (PLANT ID): LICENSEE SUBMITTAL: SCEW(S): 21 0F 25 [20] , EQUIPMENT ITEM NO. 26

                                                                                                                            ?

ELECTRICAL CABLE LOCATED IN THE CONTAINMENT KERITE MODEL HIGH TEMPERATURE, FIRE RESISTANT - '_ REQUIRED OPERATING TIME: CONTINUOUS TER CHEGSHEET NO. 26 LICENSEE REFERENCE (S): 27, 4281, 4282 ^ FUNCIION (PLANT ID): Q)NTROL AND LOW POWER CABLE - E LICENSEE SUBMITIAL: SCEW(S): 22 0F 25 [20] , B-7 ' cu reeese. . m mumm e-m meme ii e

l . TER-C5257-511 EQUIPMENT ITEM NO. 27 (TMI ACTION PLAN ITEM-ALL) ELECTRICAL CABLE LOCATED IN THE CONTAINMENT ROCKBESTOS, MODEL NOT STATED REQUIRED OPERATING TIME: NOT STATED . TER CHECKSHEET NO. 27 LICENSEE REFERENCE (S): 1391 FUNCTION (PLANT ID): ELECTRICAL DISTRIBUTION, TMI EQUIPMENT LIGNSEE SUBMITTAL: SCEW(S): 14 0F 15 [15] EQUIPMENT ITEM NO. 28 (TMI ACTION PLAN ITEM-ALL) ELECTRICAL CABLE LOCATED IN THE REACTOR AUXILIARY BLDG. ROCKBESTOS, MODEL NOT STATED REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 28 LIG NSEE REFERENCE (S): 1391 FUNCTION (PLANT ID): ELECTRICAL DISTRIBUTION, TMI EQUIPMENT LICENSEE SUBMITTAL: SCEW(S): 14 0F 15 [15] EQUIPMENT ITEM NO. 29 (TMI ACTION PLAN ITEM-ALL) ELECTRICAL CABLE LOCATED IN THE CONTAINMENT SAMUEL MOORE, THERMOCOUPLE EXTENSION REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 29 LICENSEE REFERENCE (S): 677 FUNCTION (PLANT ID): ELECTRICAL DISTRIBUTION, TMI EQUIPMENT LICENSEE SUBMITTAL: SCEW(S): 15 0F 15 [15] EQUIPMENT ITEM No. 30 ELECTRICAL CABLE SPLICE LOCATED IN THE CONTAINMENT, ELEV. 234'-246' RAYCHEM, MODEL NOT STATED REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET No. 30 LICENSEE REFERENCE (S): 815 FUNCTION (PLANT ID): SINGLE CONDUCTOR AND MULTICONDUCTOR CABLE SPLICING LICENSEE SUBMITTAL: SCEW(S): 24 0F 25 [20]

     . EQUIPMENT ITEM NO. 31
         , ELZCTRICAL CONNECTOR LOCATED IN THE CONTAINMENT, ELEV. 234'-246' AMP MODEL 535481, WIRE SIZE 16                            ,

REQUIRED OPERATING TIME: CONTINUOUS TER CHECKSHEET NO. 31 LICENSEE REFERENCE (S): 2068 FUNCTION (PLANT ID): CONDUCTOR BUTT SPLICE LICENSEE SUBMIITAL: SCEW(S): 25 0F 25 [20]

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f 3M/ ELECTRO PRODUCTS MODEL SCOTCH 70 (SILICON RUBBER) .E. ' - REQUIRED OPERATING TIME: CONTINUOUS .. .. '" : ' - 4 TER CHECKSHEET NO. 32 i .','g.  :. - LICENSEE REFERENCE (S): NOT CITED - f. , FUNCTION (PLANT ID): CABLE TERMINATION PROTECTION .' ~7. * . LICENSEE SUBMITTAL: SCEW(S): 25A 0F 25 [20] y

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TER-C5257-511 APPENDIX C - PLANT SAFETY-BELATED SYSTEMS AND DISPLAY INSTRUMENTATION C.1 LIST OF SAFETY-RELATED SYSTEMS In accordance with IE Bulletin 79-01B or NUREG-0588, the Licensee was required to (1) establish a list of systems and equipment required to mitigate the consequences of a loss-of-coolant accident (LOCA) and a high energy line break (HELB) and (2) identify components needed to perform the functions of safety-related display information, post-accident sampling and monitoring, 'and radiation monitoring. The list of safety-related systems provided by the Licensee was reviewed by the NRC staff against a staff-developed master list. The NRC staff had developed a generic master list based upon a review of plant safety analyses and emergency procedures. The systems list was established on the basis of the functions that must be performed for accident mitigation (without regard to location of equipment relative to hostile environments). The instrumenta-tion selected included that needed to monitor overall plant performance as well as to monitor the performance of systems on the list. Based upon information in the Licensee's submittal, the equipment location references, and in some cases conversations with the Licensee, the NRC staff verified that the systems included in the Licensee's submittal were those required to achieve or support: (1) emergency reactor shutdown, (2) containment isolation, (3) reactor core cooling, (4) containment heat removal, (5) core residual heat removal, and (6) prevention of significant release of radioactive material to the surrounding environment. With the exception of items deferred for later review (cold-shutdown equipment and TMI Lessons-Learned modifications), the staff concluded that the systems identified by the Licensee were acceptable. The list of systems identified by the Licensee and accepted by the NRC staff is reproduced in this appendix. A C-1 d$ Franklin Research Center A Dusean of The Frankan insaeute

TER-CS257-511 - Function System 1 _ Emergency Reactor Shutdown Reactor Protection _ Engineered Safeguards Actuation Chemical and Volume Control Reactor Coolant Containment Isolation Main and Auxiliary Steam Main and Auxiliary Feedwater ' Containment Ventilation Chemical and Volume Control _ Safety Injection h Residual Heat Removal i Cooling Water _ Intake Cooling Water - Reactor Core Cooling Safety Injection System Containment Heat Removal Containment Spray Containment Air Recirculation Core Residual Heat Removal Residual Heat Removal - Main Feedwater Auxiliary Feedwater K Main Steam

                                                                                                =_

Safety Injection Cooling Water

1. The NRC staff recognized that there are differences in nomenclature of ~

systems because of plant vintage and engineering design; consequently, - some systems performing identical or similar functions may have different T names. In those instances it was necessary to verify the function of the i syrtem(s) with the responsible IE regional reviewer and/or the licensee. ~ 4 C-2 U000 Franklin Research Center A Omneon of The Franhan insatute

TER-C5257-511 Function Systeml Prevention of Significant Release Containment Air Purification 2 of Radioactive Material to Environment Containment Combustible Gas Contro12 Post-Accident Sampling and Monitoring Supporting Systems Emergency Power HVAC C.2 SAFETY-RELATED INSTRUMENTATION In Section 3.1 of the NRC S3R [16], the NRC made the following statement:

     " Display instrumentation whien provides information for the reactor operators to aid them in the safe handling of the plant was not specifically identified by the licensee. A complete list of all display instrumentation mentioned in the LOCA and HELB emergency procedures must be provided. Equipment qualification information in the form of summary sheets should be provided for all components of the display instrumentation exposed to harsh environments. Instrumentation which is not considered to be safety related but which is mentioned in the emergency procedure should appear on the list. For these instruments, (1) justification should be provided for not considering the instrument safety related and (2) assurance should be provided that its subsequent failure will not mislead the operator or adversely affect the mitigation of the consequences of the accident. The environmental qualification of post-accident rampling and monitoring and radiation monitoring equipment        g is closely related to the review of the TMI Lessons-Learned modifications and will be performed in conjunction with that review."

In Reference 20, the Licensee provided the following response:

     "The reference to display instrumentation requirements within the SER appears to limit the current need to instrumentation within the harsh environment and/or as mentioned in the LOCA or HELB emergency procedures. Instrumentation within harsh environment would be limited to      ,

those transmitters, switches, and RTD's already reported on SCEWS.

2. Covered as part of TMI-2 Lessons Learned.

nklin Research Center A Ommon of The Frar*hn insatute

TER-C525 7-511 At present, CP&L is to develop new Emergency Instructions incorporat ing TMI emergency guidelines as part of a TMI action item requirement. These new instructions are scheduled for 1983 implementation. When reviewed and accepted for plant operational use, they will be reviewed for components and display instrumentation wit..in plant harsh environment. If new instrumentation is required to meet these emergency procedures or if additional instrumentation is referenced by these procedures, a list will be compiled and SCEW's provided to the NRC." Evaluation The Licensee states that instrumentation within the harsh environment is already reported on SCEWS. If new instrumentation is referenced in emergency procedures being rewritten for 1983 implementation, these instruments will be identified to the NRC. It is considered that the Licensee has responded to the concern identified in the SER. At the same time, a review of the SCEWS for these instruments reveals that the specified operating times for several key instruments are too short. For example, pressurizer pressure transmitters have required operating times of 1 hour to 1 day. A further review of the SCEWS does not reveal any RCS pressure transmitter which will be available for long-term monitoring of reactor coolant system pressure. Additionally, the Licensee states that steam generator level transmitters are required to operate for only 30 minutes. While these transmitters are not necessarily required for long-term monitoring, these operating times are not consistent with the general requirements for achieving long-term shutdown cooling modes and do not adequately reflect the potential need to remain in a hot-shutdown condition for an interim period before reaching a stable long-term cooling condition. In order to ensure that environmental qualification has been satisfac-torily addressed with regard to safety-related display instruments, the Licensee should (1) ensure that RCS pressure indication is provided which is qualified for long-term monitoring and (2) ensure that steam generator wide-range and pressurizer level monitoring iast'uments r are provided which will ' adequately perform their functions throughout the period when they would reasonably be expected to operate. l Ak i Franklin Research Center ao - or% r un mu. p, , _ _ . _ , - - - . - -.

TER-C5257-511 APPENDIX D - REVIEW OF LICENSEE'S RESPONSE TO NRC EEQ SER CONCERNING JUSTIFICATION FOR INTERIM OPERATION

1. BACKGROUND The NRC Safety Evaluation Report (SER) concerning equipment environmental qualification (EEQ) states [16]: ,

     " Subsection 4.2 identified deficiencies that must be resolved to establish the qualification of the equipment; the staff requires that the information lacking in this category be provided within 90 days of receipt of this SER. Within this period, the licensee should either pro-vide documentation of the missing qualification information which demon-strates that such equipment meets the DOR guidelines or NUREG-0588 or        -

commit to a corrective action (requalification, replacement, relocation, and so forth) consistent with the requirements to establish qualification by June 30, 1982. If the latter option is chosen, the licensee must provide justification for operation until such corrective action is complete." On January 19, 1982, FRC representatives met with NRC Division of Licensing personnel at NRC offices to discuss the potential for FRC to assist the staff in the technical revicw of licensees' statements regarding justifica-tion for interim plant operation submitted in response to outstanding qualifi-cation deficiencies in the NRC EEQ SERs. The results of the meeting were as follows: (1) FRC was requested to proceed immediately with the technical review of licensees' justification for interim operation, (2) the format was established, and (3) the criteria for the review were established. These criteria are presented in Section 2 of this appendix. On January 21, 1982, the NRC provided the following modification to Final Assignment 13 concerning this subject:

     "The FRC review will consist of:

o Review the licensee's justification of interim operation and provide FRC independent analysis which shows rhether or not licensee provided technically sound rationale as a basis for justification for continued plant operation. D-1 Mn i OqUU Franidin Research Center L A DMeson of The Frerehn "-

TER-C5257-511

• o On January 27, 1982, FRC shall provide a list of those power reactors that have provided technically sound justification for continued /

operation. FRC shall also provide a list of those power reactors which have not provided technically sound justification for continued _- operation. In addition to the lists, FRC may provide any additional r information which in FRC's judgment it, necessary to support the ' conclusions regarding justification for coatinued operation." On January 25, 1982, the NRC was provir 2d with the completed review of 3 the licensees' statements presented as a basis for justification for interim operation in response to the NRC EEQ SER.* On February 5, 1982, at the NRC's request, the NRC was provided with actual examples of licensees' responses to I the NRC EEQ SER that provide adequate rationale as a basis for justification for interim operation.** 2 GENERAL DISCUSSION In general, licensee-submitted justifications for interim operation are based on systems considerations, equipment operability evaluations, or failure-modes-and-effects analyses. Systems considerations often involve the availability of backup equipment capable of performing the particular safety function of concern. The backup equipment is either environmentally qualified, unqualified but not exposed to a harsh environment at the same time as the primary equipment, or located so = that it is unlikely that both the primary and backup equipment would be simultaneously exposed to a severe environment. In general, these systems discussions should consider (1) the possibility of a single-active failure . b

• C. J. Crane Letter to R. A. Clark, NRC.

Subject:

Transmittal of FRC Review of Licensees' Responses to NRC EEQ SER Concerning Justification for Interim Operation FRC, 25-Jan-82 7

• • C. J. Crane _

Letter to R. A. Clark, NRC.

Subject:

Transmittal of Actual Examples of Licensees' Responses to NRC EEQ SER Which Provide Adequate Rationale as a Basis for Justification of Interim Operation FRC, 5-Feb-82 _nklin Rese_ arch _. Center

TER-C5257-511 J disabling the backup equipment, (2) any major differences in the characteristics of the primary and backup equipment (unless it is obvious that the equipment is essentially identical), (3) the possibility of electrical .. failure of the primary equipment cwasing an adverse ef fect on other , safety-related equipment or power supplies, and (4) in the case of display instrumentation, the possibility of an operator being misled by the failed f j 7 primary equipment. Where equipment has not been demonstrated to be qualified, some justifications discuss administrative procedures or revised operating procedures in effect. Depending upon the specific equipment involved, each of the above considerations need not be discussed in every instance, but, in general, a complete systems discussion would consider the above points. Where equipment qualification evaluations were used, licensees generally .. (1) received additional information from manufacturers, (2) applied engineer-ing judgment, (3) performed material analysis, and/or (4) used partial test data in support of the original qualification documentation. Where these evaluations were performed, the licensees determined that, although full qualification was not documented, there was sufficient evidence to suggest that the equipment would perform its intended safety function, thereby justifying interim operation until qualified equipment is installed. Some licensees provided detailed failure-modes-and-effects analyses of electrical circuitry to demonstrate that, under all identified failura modes, the safety function of the equipment could still be accomplished. Other justifications involved a combination of qualification information and systems information. For example, if a licensee has qualification information (such as a generic test report or other partial qualification documentation) that tends to confirm the ability of the equipment to remain E operable for a specified period of time, justification for interim operation often was based upon a discussion of the required safety function being performed prior to the potential failure. This type of discussion often applies to equipment which performs a short-term trip or isolation function in the early stages of an accident. _ M D-3 nklin Resea rc.h.C.e.nter

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TER-C5257-511

3. PLANT-SPECIFIC REVIEW As a result of~the review, this plant was evaluated and the results documented on the " Summary of Review of Licensee's 90-Day Response" form reproduced below:

i

   " EQUIPMENT ENVIRONMENTAL QUALIFICATION (EEQ)

Review of Licensees' Resolution of Outstanding Issues From NRC Equipment Environmental Qualification Safety Evaluation Reports

SUMMARY

OF REVIEW OF LICENSEE 90-DAY RESPONSE Utility: Carolina Power & Light Co. Plant Name: H. B. Robinson Unit 2 NRC Docket No. 50-261 NRC TAC No. 42466 NRC Contract No. NRC-03-79-118 FRC Project No. C5257 FRC Assignment No. 13 FRC Task No. 511

References:

a. E. E. Utley and M. A. McDuffie Letter to S. A. Varga, NRC.

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2 - Response to May 21, 1981 letter and Safety Evaluation Report Carolina Power & Light Co., 31-Aug-81 NO-81-1432

b. Office of Nuclear Reactor Regulation .

Safety Evaluation Report for H. B. Robinson Unit No. 2 Environmental Qualification of Safety-Related Electrical Equipment l NRC , 21-May-81 l l D-4 000U Franklin Research Center A DMason of The Franhan kutnute

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                                                                                                          ?      -.

TER-C5257-511 2 M j The Licensee has submitted technical information in Reference a in  ; response to the NRC SER [b] on environmental qualification. FRC has reviewed I these documents [a, b]. As a result of this review, FRC concludes that the I Licensee has stated that the equipment items are environmentally qualified; or 3 has provided a technically sound rationale as a basis for justification for -- continued plant operation; or has provided a technically sound rationale or other additional information which in FRC's judgment provides a basis for - justification for continued operation; with the following exceptions:

                                                                                                                    =

Equipment Equipment Description / SCEW Sheet Basis for [ Item Function No. Status Code Deficiency

                                                                                                            ]-i None                                                                                                    _,
                                                                                                                  -a The Licensee's response to the SER addressed and provided resolution of                        -- i deficiencies identified in the SER and provided adequate rationale as a basis                                    -

for justification for interim. operation." l A a A a 2

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2 f TER-CS25 7-511 APPENDIX E - REQUEST FOR ADDITIONAL INFORMATION This appendix contains the Request for Additional Information (RAI) that -- was developed during the course of the review and issued to the NRC for forwarding to the Licensee. The RAI war revised throughout the review to reflect the Licensee's response (s) to the initial RAI. The reader is cautioned that the numbers in brackets refer to citations found in the list of references at the end of this appendix and not to the citations listed in Section 6, References, of the TER. 6

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                 .                            E-1                                 .

000 Franklin Research Center A OMace of The Franhan insatute

a L TER-C5257-511 $_ REQUEST FOR ADDITIONAL INFORMATION _: EQUIPMENT ENVIRONMENTAL QUALIFICATION (EEQ) - REVIEW OF LICENSEES' RESOLUTION OF OUTSTANDING ISSUES FROM NRC EQUIPMENT ENVIRONMEliTAL QUALIFICATION SAFETY  ?- EVALUATION REPORTS (SER) AND TMI ACTION PLAN INSTALLED EQUIPMENT _ Carolina Power & Light Company H. B. Robinson Steam Electric Plant Unit No. 2 * [ . m NRC Docket No. 50-261 November 24, 1981 NRC TAC No. 42466 Rev.1, February 1,1982 Rev. 2, April 7, 1982 _g _l

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c_ i E-2 .' 000 Franklin Research Center A DMoon of The Franhan Insetute b 7

t TER-C5257-511 BACKGROUND Franklin Research Center (FRC) of Philadelphia, Pa. is providing assis-tance to the U.S. Nuclear Regulatory Commission (NRC) for the equipment environmental qualification (EEQ) review of operating reactors. FRC will perform en EEQ review of the Licensee's 90-day response to outstrading issues from the NRC Equipment Environmental Qualification Safety Evaluation Report (SER) and the installed TMI AcLion Plan equipment. The review will be limited to safety-related equipment potentially exposed to a harsh environment.- The results will be presented in the form of a technical evaluation report for each plant. This request for additional information (RAI) is the result of an evaluation of the information provided by letters dated August 31, 1981 [1] and January 30, 1981 [2].* FRC previously requested TMI Action Plan information by telephone memoranda dated July 14, July 31, and September 9, 1981 [3,4,5]. In response, CP&L transmitted the following information on July 31, 1981 [6] and September 15, 1981 [7].

a. Normal Environments Inside Containment

b. Normal Environments Outside Containment

c. Analyses of High Energy Line Break Outside Containment

d. 45-day Response to IE Bulletin 79-01B

e. General Plant Procedure No. 6 (Edited)

f. Nuclear Qualification Test Procedure 548-8955 Revision A, January 7, 1981

g. Qualification Test Report AMP-110-11002, for Cable Splices.

On January 25, 1982, the NRC transmitted two reports concerning 4 information on environmental qualification [10, 10.1].51)**

• Numbers in brackets refer to citations found in the list of references.

 **Throughout the text, superscript numbers in parentheses indicate the revision in which the underlined material preceding the superscript was added.

nklin Research Center A Osamen of The Frenhan W

TE R-C525 7-511 In a letter dated March 1, 1982, CP&L stated the following with regard to Lts RAI response:(2)

                                             "For the reasons listed below, CP&L believes that a more cost e f fec tive review could be conducted by the NRC and FRC at CP&L's General Of fice in Raleigh, N.C.

1. The Technir.1 Specifications imposed by NRC's Order of October 24 1980 ~

require that CP&L maintain control of the Robinson central file. Sending the centcal file to FRC would violate that NRC Order.

2. The material requested is available for audit and review in CP&L's central file located at the Company's General Office in Raleigh, N.C.

Additionally, the central file contains supporting information used by CP&L in determining the qualification of individual pieces of equipment. The test reports are only a part of the processes involved, and a review of only the test reports by FRC would provide an incomplete and out-of-context picture.

3. There appears to have been no attempt by FRC to consolidate the requested information. It is quite possible that they have requested the sane document from several licensees. In the NRC's request of .

December 11, 1981, FRC acknowledges receipt of " Analyses of High Energy Line Break Outside Containment" from Robinson, yet requests a  : Postulated Pipe Failure Analysis Outside of Containment. The two analyses are one in the same. By not consolidating and comparing the requests, a needless duplication of effort and waste of resources - would occur."\41 A. FRC REVIEW OF THE LICENSEE'S 90-DAY RESPONSE TO THE NRC EEQ SER INFORMATION REQUESTED DATE RECEIVED BY FRC***

1. In re ference to the Licensee's 90-day =-

response [1] to the N RC SER [ 8 ] , a legible single copy of each of the following qualification documents is requested in order that the FRC evaluation may proceed;

a. Westinghouse Letter CPL-77-550 (CP&L Reference 2, Section 3.1 [1])

b. Crouse Hinds Connector Data, Elec t ric a l Penetrations (CP&L Reference 13, Sec tion _

3.1 (1]) -

                               ***This column will be completed by FRC as requested information is received.

E-4 20 Franklin Research Center A oi on or Th. Fr.n=an in.on,. l _ , _ . . . . .

l l TER-C5257-511 - DATE RECEIVED BY FRC***

c. WCAP-8587, Environmental Qualification 1-25-82 [10.1](1) i of Westinghouse NSSS Class IE Equipment (CP&L Reference 19, Section 3.1 [1])

d. Postulated Pipe Failure Analysis Outside 7-31-81 [6]

of Containment (CP&L Reference 21, Section 3.1 [1])

e. Rosemount Test Report 97215A, Model 1151 Received.2/12/82 on Transmitter (CP&L Reference 25, Section Task 49544>

3.1 [1])

f. Rosemount Test Report 127227 Rev. A, Model 1151 Transmitter (CP&L Reference _

26, Section 3.1 [1])

g. Rosemount Report 37821, Model 1153 Received.4/1/82 for Transmitter (CP&L Reference 41, Section Task 45244>

3.1 [1])

h. Limitorque Test Report FP-3271 (CP&L 1-25-82 [10](1)

Reference 42, Section 3.1 [1])

i. Kerite Company - Letter dated August 5, 1980 enclosures: LOCA Qualification of Kerite 1000 Volt FR/FR Control Cable LOCA Qualification of Kerite 1000 Volt HTK/FR Power Cable (CP&L Reference 49, Section 3.1 [1])

j. Kerite Company - Letter dated October 21, 1980 in response to CP&L letter, CO-02726, dated October 13, 1980 <

requesting qualification data on use of Scotch 70 Silicone Rubber Tape (CP&L Reference 50, Section 3.1 [1])

k. H. E. Robinson Steam Electric Plant Unit 2 TMI Project Modification Design Criteria (CP&L June 1, 1980) (CP&L Reference 53, Section 3.1 [1])

nklin Research Center A Oswason of The FrankAn kwende

TER-C5257-511 B. FRC REVIEW OF INSTALLED TMI ACTION PLAN ITEMS INFORMATION REQUESTED DATE RECEIVED BY FRC***

1. Reference 1 does not provide adequate detail with respect to identification of TMI Action Plan equipment installed after 1/1/81.

Identification of TMI Action Plan items installed after 1/1/81 is requested.

2. The qualification documents, e.g., the actual

                                                   ~

test reports and associated correspondence cited as evidence of qualification listed on the SCEW sheets, for identified TMI Action Plan equipment installed after 1/1/81 are requested. [The identification of those reports considered to be proprietary is requested so that proper control of documents can be maintained.]

3. A legible single copy of Wyle test report on ANP splices built per CP&L installation procedure M-521 is requested in order that the FRC evaluation may proceed.

4 Where the Licensee has a standard Owners' Group position with respect to a NUREG-0737 technical area or has requested extensions of implementation dates, this information is requested in order to incorporate it into the review. C. INSTRUCTIONS FOR TRANSMITTING INFORMATION RIQUESTED

1. The schedule for completion of the FRC assignment requires that the Licensec provide the requested information within 3 weeks of the date of the RAI.

2. The Licensee may transmit the requested information as follows:

o complete package directly to the NRC project manager or o copy of cover letter to NRC project manager and complete package to FRC. E-6 000 ranklin Research Center A OMoon of The Frannan insatute

I TER-C5257-511 REFERENCES \

1. E. E. Utley and M. A. McDuffie Letter to S. A. Varga, NRC.

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2 - Response to May 21, 1981 letter and f Safety Evaluation Report l Carolina Power & Light Co. , 31-Aug-81 NO-81-1432

2. B. J. Furr Letter to J. P. O'Reilly, NRC.

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2 Revision 3 to IE Bulletin 79-01B Ninety-Day Report. Carolina Power & Light, 30-Jan-81 Serial: NO-81-12

3. Telephone memorandum dated 7/14/81 C. J. Crane, J. A. Murphy (FRC) conversation with J. Sheppard, R. Schwager (CP&L)

Subject:

Request for additional information; Robinson 2

4. Telephone memorandum dated 7/31/81 C. J. Crane (FRC) conversation with J. J. Sheppard (CP&L) and J. Van Vliet (USNRC PM)

Subject:

Request for additional information, Brunswick 1 & 2, Robinson Unit 2

5. Telephone memorandum dated 9/9/81 D. J. Schmitz (FRC) conversation with R. A. Schwager (CP&L)

Subject:

Cable splices made per CP&L procedure M-521

6. E. E. Utley Letter to C. J. Crane, FRC.

Subject:

H. B. Robinson Steam Electric Plant Unit 2, Transmittal of TMI Action Plan Information Carolina Power and Light, July 31, 1981

7. E. E. Utley Letter to C. J. Crane, FRC.

Subject:

H. B. Robinson Steam Electric Plant Unit 2, Transmittal of TMI Action Plan Information Carolina Power and Light, September 15, 1981

8. Office of Nuclear Reactor Regulation Safety Evaluation Report for H. B. Robinson Unit No. 2 Environmental Qualification of Safety-Related Electrical Equipment NRC, 21-May-81

9. NUREG-0737, " Clarification of TMI Action Plan Requirements" NRC, November ic80

_nklin Rese_ arch .C_ enter J(

TER-CS257-511

10. S. A. Varga Letter to C. J. Crane, FRC.

Subject:

Transmittal of WCAP-8587, and Correction of Limitorque Test Report Number from Robinson 2 RFI USNRC, 25-Jan-82Lil 10.1 G. Butterworth and R. B. Miller Methodology for Qualifying Westinghouse WRD Supplied NSSS Safety Related Electrical Equipment Westinghouse, Feb-79 WCAP-8587, Rev. 2411

11. E. E. Utley Letter to D. G. Eisenhut, NRC.

Subject:

H. B. Robinson Steam Electric Plant, Unit No. 2 Request for Additional Information - Environmental Qualification _ Carolina Power & Light Co., 01 Mar. 1982\d l l E-8 O UO0ll Franklin Research Center A Chman of The Franadln insatute

If TER-C5257-511 APPENDIX F - EQUIPMENT WHICH IS EXEMPT OR NOT IN SCOPE OF THE REVIEW EQUIPMENT ITEM NO. 33 SOLENOID VALVE LOCATED IN THE CONTAINMENT ASCO MODEL NP831655E REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 1 LICENSEE REFERENCE (S): 649 FUNCTION (PLANT ID): CHARGING LINE LOOP A, COLD LEG (V-310A,B) LICENSEE SUBMITTAL: SCEW(S): 9-11 FUNCTXON (PLANT ID): AUXILIARY PRESSURIZER SPRAY (V-311) LICENSEE SUBMITTAL: SCEW(S): 10-11 FUNCTION (PLANT ID): REACTOR COOLANT LETDOWN (LCV-460A, B) LXCENSEE SUBMITTAL: SCEW(S): 11 0F 11 [20] EQUIPMENT ITEM NO. 34 SOLENOID VALVE LOCATED IN THE REACTOR AUXILIARY BLDG. ASCO MODEL LBX831614 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 2 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): REACTOR COOLANT LETDOWN ISOLATION (V-204A, B) LXCENSEE SUBMITTAL: SCEW(S): 7 0F 11 [20] EQUIPMENT ITEM NO. 35 S0LENOID VALVE LOCATED IN THE CONTAINMENT ASCO MODEL LBX831614 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 3 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): SEAL WATER BYPASS HEADER (V-307) LICENSEE SUBMITTAL: SCEW(S): 8 0F 11 [20] EQUIPMENT ITEM No. 36 MOTORIZED VALVE ACTUATOR LOCATED IN THE CONTAINMENT LIMITORQUE MODEL SMB2 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 9 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): ACCUMULATOR ISOLATION LOOP 1 RCS COLD LEG (V-865A, B, C) LICENSEE SUBMITTAL: SCEW(S): 6 0F 11 [20] F-1 4

TER-C5257-511 EQUIPMENT ITEM NO. 37 MOTORIZED VALVE ACTUATOR LOCATED IN THE CONTAINMENT LIMITORQUE MODEL SMB1 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 11 LICENSEE REFERENCE (S): 637, 639 FUNCTION (PLANT ID): RC LOOP 2 HOT LEG SUPPLY ISOLATION (V-750) LICENSEE SUBMITTAL: SCEW(S): 2 0F 11 [20] FUNCTION (PLANT ID): RC LOOP 2 HOT LEG SUPPLY ISOLATION (V-751) LICENSEE SUBMITTAL: SCEW(S): 3 OF 11 [20] EQUIPMENT ITEM No. 38 Mar 0RIZED VALVE ACTUATOR LOCATED IN THE REACTOR AUXILIARY BLDG. LIMITORQUE MODEL SMBO REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 12 LICENSEE REFERENCE (S): 662 FUNCTION (PLANT ID): RHR HEAT EXCHANGERS COOLING WATER (V-749A, B) LICENSEE SUBMITTAL: SCEW(S): 1 OF 11 [20] FUNCTION (PLANT ID): RWST/RHR PUMP SUCTION (V-862A, B) LIGNSEE SUBMITTAL: SCEW(S): 4 0F 11 [20] FUNCTION (PLANT ID): RWST OUTLET (V-864A, B) LICENSEE SUBMITTAL: SCEW(S): 5 0F 11 [20] EQUIPMENT ITEM NO. 39 (TMI ACTION PLAN ITEM II.E.3.1) CONTROL SWITCH LOCATED IN THE REACTOR AUXILIARY BLDG. GEMCO MODEL 404S2X4111 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 26 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): PRESSURIZER HEATER BREAKER TRIP (PLANT ID NOT STATED) LICENSEE SITBMITTAL: SCEW(S): 1 0F 15 [20] EQUIPhENT ITEM NO. 40 (TMI ACTION PLAN ITEM II.E.4.2) RESET WITCH LOCATED IN THE REACTOR AUXILIARY BLDG. GEMCO h0 DEL 404PI331PP1 REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 27 LICEhSEE REFEMENCE(S): 2850 FUNCTION (PL/NT ID): FUNCTION AND PLANT ID NOT STATED LICENSEE SUBKtTTAL: SCEW(S): 5 0F l's [20]

TER-C5257-511 EQUIPMENT ITEM NO. 41 (TMI ACTION PLAN ITEM II.E.4.2) SELECTOR SWITCH LOCATED IN THE REACTOR AUXILIARY BLDG. GEMCO MODEL 404S34122EE8 REQUIRED OPERATING TIME: NOT STATED TER CHEGSHEET NO. 28 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): FUNCTION AND PLANT ID NOT STATED LICENSEE SUBMITTAL: SCEW(S): 7 0F 15 [20] EQUIPMENT ITEM NO. 42 (TMI ACTION PLAN ITEM II.E.1.2) TRANSDUCER LOCATED ON THE TURBINE DECK CONTROLOTRON MODEL 240N4CS80HT REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 29 LIGNSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): NOT STATED (FT-425A, B , C) LICENSEE SUBMITTAL: SCEW(S): 9 OF 15 [20] EQUIPMENT ITEM NO. 43 (TMI ACTION PLAN ITEM II.E.1.2) TRANSDUCER LOCATED IN THE REACTOR AUXILIARY BLDG. CONTROLOTRON MODEL 240N4CS80HT REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET No. 30 LIGNSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): NOT STATED (FT-426A, B , C) Ll&NSEE SUBMITTAL: SGW( S ): 10 0F 15 [20] EQUIPMENT ITEM NO. 44 (TMI ACTION PLAN ITEM II.E.1.2) FLOW COMPUTER LOCATED ON THE TURBINE DErK CONTROLOTRON MODEL 241N REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 31 LICENSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): FUNCTION AND PLANT ID NOT STATED LIGNSEE SUBMITTAL: SCEW(S): 11 0F 15 [20] EQUIPMENT ITEM NO. 45 (TMI ACTION PLAN ITEM II.D.3) RELAY LOCATED IN THE REACTOR AUXILIARY BLDG. WESTINGHOUSE MODEL NBFD22S REQUIRED OPERATING TIME: NOT STATED TER CHECKSHEET NO. 34 LIGNSEE REFERENCE (S): 2850 FUNCTION (PLANT ID): FUNCTION AND PLANT ID JOT STATED LIGNSEE SUBMITTAL: SCEW(S): 4 0F 15 [20] F-3 KUU Franklin Research Center 4 com.on or Tw. Fr.,woin %,.eue. - _ _ _ _ _ _ .}}