ML20083J165
| ML20083J165 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 01/06/1984 |
| From: | CINCINNATI GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20083J157 | List: |
| References | |
| NUDOCS 8401160224 | |
| Download: ML20083J165 (961) | |
Text
{{#Wiki_filter:- O l ENVIRONMENTAL QUALIFICATION l
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REPORT FOR CLASS IE -
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/ EQUIPMENT VOLUME 1 O
! WM. H. ZIMMER ' NUCLEAR POWER STATION l CfHE CINCINNATI GAS & ELECTRIC COMPANY OOOha ' D ADO \ A PDR
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i s { WM. H. ZI)eiER NUCLEAR POWER STATION - UNIT 1. ,, NUREG 0588 REV. l' ENVIRONMENTAL QUALIFICATION REPORT., ?- d i h
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NED'REMONSIBLE ENGINEER REVIEWED BY: J cd [- /3 - 82 NED DIRECTOR OF. ENGINEERING PROJECTS (EQUIPMENT QUALIFICATION ) REVIENED BY: , // t!It-
- Al'-::6yrt - h/yfG' "d MANAGER, NUCLEAR ENGINEERING DEPARTMENT i.
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WM. H. ZIMMER NUCLEAR POWER STATION ENVIRONMENTAL QUALIFICATION SUBMITTAL REVISION 2
- DECEMBER 29, 1983
( j\ x The following sections of the July 16, 1982 Environmental Qualification - submittal have been revised as follows: SECTION CHANGE PER REV. 2 TABLE OF CONTENTS ............................. Replace Complete Section 1.C INTRODUCTION ............................. Replace Complete Section 2.0 ENVIRONMENTAL SERVICE CONDITIONS ......... Replace Complete Section 3.0 EQUIPMENT LIST ........................... Replace Complete Section 4.0 DOCUMENTATION REVIEW ..................... Replace Complete Section 5.0 COMPARISDN WITH NUREG 058R REV. 1 ........ Replace Complete Section 6.0 RESULTS OF E.Q. REVIEW ................... Replace Complete Section 7.0 ON-GOING ACTIVITIES ...................... Replace Complete Section 8.0 RESPONSE TO SAFETY EVALUATION ............ Add New Section to Report REPORT CONCERNS O V APPENDIX A .................................... Replace Complete Section APPENDIX 8 .................................... Replace Complete Section APPENDIX C .................................... Replace Complete Section APPENDIX D .................................... Replace Complete Section APPENDIX E .................................... Replace Complete Section APPCNDIX F .................................... Replace Comnlete Section APPENDIX G .................................... Add New Appendix to Report APPENDIX H .................................... Add New Appendix to Report l APPENDIX I .................................... Add New Appendix to Report i PREPARED BY: /2/29MJ NED RESPONSMLE ENGINEER DAIE l ! REVIEWED BY: -
/ ~.3 ~ N l I,) NED DQWCIDH OF ENGINELHING PROJECIS DATE
' V (f001PMENT QUALIFICATION) REVIEWED BY: [ Ad /' b-MANAGER, NUCLEAR ENGINEERING DAIE DEPARTMENT
TABLE OF CONTENTS
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x / VOLUME I PAGE NO.
1.0 INTRODUCTION
.........x......................................................... 1 2.0 : ENVIRONMENTAL SERVICE CONDITIONS............................................... 3 2.1 TEMPERATURE, PRESSURE, RELATIVE HUMIDIT) AND RADIATION.................................................................. 3 2.1.1 NORMAL TEMPERATURE, PRESSURE AND RELATIVE HUMIDITY.................. 3 2.1.2 ACCIDENT TEMPERATURE, PRESSURE AND RELATIVE HUMIDITY...............e 3 2.1.2.1. LOSS OF COOLANT ACCIDENT................................... 3 2.1.2.2. HIGH ENERGY LINE BREAK ACCIDENTS .......................... 3 2.1.3 RADIATION INSIDE AND OUTSIDE CONTAINMENT ........................... 4 2.1.4 RADIATION EFFECTS ON SOLID STATE EQUIPMENT IN MILD ENVIRONMENTS................................................... 5 2.2 SUB"ERGENCE .............................................................. 5 2.2.1 DRYWELL ............................................................ 5 2.2.2 SUPPRESSION POOL ................................................... 5 2.2.3 REACTOR BUILDING ................................................... 5 2.2.4 STEAM IUNNEL ....................................................... 6 2.3 CONTAINMENT-SPRAYS ........................................................ 6 2.3.1 DRYWELL SPRAYS ..................................................... 6 2.3.2 WETWELL SPRAYS ..................................................... 7 2.4 HARSH ENVIRONMENTS......................................................... 7 t A) x' 3 0 . EQ U I P M E N T L I S T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 3.1 METHODOLOGY USED IN FORMATION OF EDEL ..................................... 23 3.2 MAINTENANCE OF THE EQEL ................................................... 24 3.3 DISPLAY INSTRUMENTS ....................................................... 24 3.4 REG. GUIDE 1.97 AND NUREG 0737 EQUIPMENT .................................. 25 4.0 DOCUMENTATION REVIEW .......................................................... 36 5.0 COMPARISON WITH NUREG 0588 REV. 1 ............................................. 37 6.0 RESULTS OF E.Q. REVIEW ........................................................ 55 6.1 QUALIFIED ................................................................. 55 6.2 EXEMPT .................................................................... 56 6.3 RETEST .................................................................... 56 6.4 REPLACE ................................................................... 56 6.5 ANALYSIS .................................................................. 57 6.6 RELOCATE .................................................................. 57 - 6.7 UNDER REVIEW .............................................................. 57 7.0 ON-GOING ACTIVITIES ........................................................... 58 7.1 TESTING PROGRAM ........................................................... 58 7.2 REPLACEMENT PROGRAM ....................................................... 58 7.3 CONDUIT SEALS ............................................................. 58 7.4 ANALYSIS PROGRAM .......................................................... 58 g-s3 7.5 JUST IFICA TION FOR IN TERIM OPERATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 (,,)
- 7. 6 MAIN T EN ANCE & SURVE ILL ANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 I
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TABLE OF CONTENTS (Continued) O
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8.0' RESPONSE TO SAFETY EVALUATION REPORT CONCERNS ................................. 60 8.1 SER SECTION 3.11.3.le R.G. 1.97 EQUIPMENT ................................. 60 8.2 SER SECTION 3.11.3.1 NUREG 0737 EQUIPMENT .......................,......... 60 8.3 SER SEC TION 3.11.3.1 MECHANICAL EQUIPMENT . . . . . . . . <. . . . . . . . . . . . . . . . . . . . . . . . 60 8.4 SER SECTION 3.11.3.3.3 SUBMERGENCE IN DRYWELL ............................. 60 8.5 SER SEC TION 3.11. 3.4 CONDUIT SEALS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 8.6 SER SECT ION 3.11. 3.4 CHECKL ISTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 8.7 SER SECTION 3.11s.3.5 SOLID STATE EQUIPMENT ................................ 60 8.8 SER SECTION 3.11.4.1 UPDATE OF ELECTRICAL EQUIPMENT ACTION PLANS..................................................... 60 VOLUME I (Cont.) APPENDIX A SARGENT & LUNDY DESIGN CRITERIA A51-9 APPENDIX B EQUIPMENT QUALIFICATION EQUIPMENT LIST APPENDIX C EXEMPTION DATA SHEETS
-APPENDIX D ACTION PLANS f"'IVOLUMEII v
APPENDIX E COMPONENT EVALUATION DATA SHEETS APPENDIX F DOCUMENTATION REFERENCE SHEETS APPENDIX G REG. GUIDE 1.97 ADDITIONS TO ENVIRONMENTAL QUALIFICATIONS PROGRAM APPENDIX H NUREG 0737 ADDITIONS TO ENVIRONMENTAL QUALIFICATION PROGRAM APPENDIX I SOLID STATE ELECTRICAL EQUIPMENT IN MILD ENVIRONMENTS p v
INTRODUCTION The regulatory requirements regarding the Environmental Qualification requirements for safety related equipment have evolved throughout the construction of the Zimmer 7tation. CG&E's contract with General Electric covering the Nuclear Steam Supply System required that equipment be demonstrated to operate as required under the postulated LOCA conditions (temperature, pressure, humidity, radiation) to the applicable standards at the time of the contract. Since the contract was signed on August 29, 1969, IEEE Std. 323-1971 did not apply. IEEE Std.279-1968 and General Design Criteria 4 of 10CFR50 Appendix A were the applicable requirements of the time. CG&E later committed in the FSAR to justify qualification to IEEE Std. 323-1971. Qualification to IEEE Std. 323-1971 was specified in specifications for Balance of Plant electrical equipment. A letter from Mr. J. Stolz of the NRC to Mr. E. A. Borgmann of the Cincinnati Gas & Electric Company dated November 9,1979 requested that CG&E supply additional information regarding the status of environmental qualification of safety related instrumentation and electrical equip-ment. The NRC issued NUREG 0588 " Interim Staff Position on Equipment Quali-fication of Safety-Related Electrical Equipment" to CG&E for comment on January 9, 1980. On February 5, 1980, the NRC staff requested that Utilities perform a review of their environmental qualification program to identify the degree to which the program complied with the criteria of NUREG-0588. This request initiated a review of the existing environmental qualification parameters. CG&E elected to recalculate all radiation parameters based on the radiation source terms and methods required by NUREG-0588. The recalculation was completed in September 1981, and resulted in radiation doses higher than those previously used in the review. On May 23, 1980 the Commission issued Order and Memorandum 80 CLI-21 requiring plants under construction review environmental qualification to the requirements of NUREG-0588. Based on the date of the Zimmer's Construction Permit, CG&E is required to meet the Category 11 require-ments of NUREG-0588' for existing equipment and Category I (IEEE Std. 323-1974) for all additional electrical equipment. CG&E submitted the requested information to the NRC on January 7,1981. l2 This report addressed the qualification status of safety-related electrical equipment located in potentially harsh environments. The environmental requirements of IEEE Std. 323-1971 and the parameters identified in Section 3.11 of the FSAR were used as the basis of the review. On October 30', 1981, a meetina was held between the NRC reviewers and CG&E. CG&E committed to re-review the qualification of safety-related electrical equipment located in harsh environments to the Category II requirements of NUREG-0588 and to the latest calculated environmental
- '3 conditions. The results of this re-review were documented using the NRC 2 suggested format.
A revised report was submitted on July 16, 1982 that identified the qualification program established by CG&E to address the NUREG-0588 Category II qualification requirements for safety-related electrical equipment located in potentially " harsh" environments. The report superseded all previous reports covering the environmental qualification of safety-related equipment. Rev ision 1 of the July 16, 1092 submittal wac prepared to address the request for additional information and to reflect activities completed 2 between July 1982 and January 1983. Revision 1 was submitted January 31, 1983. An audit of the environmental cualification program was performed by the NRC and their consultant (EG5G) on June 1-3, 1983. This audit was conducted at the Zimmer site and encompassed the review of fifteen Class 1E devices which were located in harsh environments. The audit consisted of reviewing the qualification package and the field installation for each device identified. The results of this audit were 2 transmitted to CG&E in the form of a Safety Evaluation Report. This document wss prepared by the Of fice of Nuclear Reactor Regulation, Equipment Qualification Branch and was transmitted via a letter from Mr. B. J. Youngblood (NRC) to Mr. J. Williams, Jr. (CG&E) dated July 6,1983. The Cincinnati Gas & Electric Company submitted a schedule for the completion of environmental qualification activities for the Zimmer station via letter LOZ-83-0110, dated August 15, 1983. The schedule provided in this letter was discussed in a telecon between Messrs. L. Kintner (NRC), G. A. Minnes (CG&E) and W. F. Bradley (CG&E) on August 31, 1983. The results of this telecon were documented in a 9 letter from Mr. B. J. Youngblood (NRC) to Mr. J. Williams, Jr. (CG&E) dated September 8, 1983. The response schedule was also revised on 2 September 8, 1983 to reflect the chances agreed upon in the above telecon. The response schedule committed CG&E to respond to concerns identified in the SER in the form of three (3) revisions to the Environmental ~0ualification Report for Class 1E Equipment. These revisions are to be submit ted on January 2,1984, April 2,1984 and three (3) months prior to fuel load. An Environmental Qualification Report for Mechanical Equipment has been prepared in response to section 3.11.3.1 of the SER. Volume 1 of'the 2 Mechanical Report which covers the information requested by the NRC is being submitted with this report. A preliminary Justification for Interim Operation Report was prepared and orovided to the NRC equipment qualification reviewers for comment in 2 September 1982. This report will be updated three (3) months prior to fuel load in accordance with the response schedule. Revision 2 of the July 16, 1982 submittal ha9 been prepared as the first phase of addressing the st af f's concern as noted in the SER. Specific information regarding concerns noted in the SER may be found in section ,
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8 of this report. Revisions have been made to address the concerns, and to reflect activities completed between January 1983 and December 1983. 2.0 ENVIRONMENTAL SERVICE CONDITIONS 2.1 TEMPERATURE, PRESSURE, RELATIVE HUMIDITY, AND RADIATION _ The. normal and accfdent service conditions resulting from postulated I ) Loss of. Coolant and High Energy Line Break Accidents are defined in
'Zimmer Design Criteria A51-9, which is included as Appendix A of this report. References identified in this Design Criteria are available for review in the Environmental Qualification Central File.
2.1.1 Normal Temperature, Pressure and Relative Humidity The _ normal- temperature, pressure and relative humidity conditions are defined from the HVAC Design Criteria for each HVAC system. 2.1.2 Accident Temperature, Pressure and Relative Humidity The Environmental. Conditions resulting from the worst case postulated LOCA's insida containment and HEL8's outside containment are listed in Design Criteria A51-9. 2.1.2.1 Loss of Coolant Accident The most severe nuclear effects and the areatest releats of radioactive material to the Primary Containment result from a complete circum-ferential break of one of the Recirculation Loop Pipelines. The temperature and pressure profiles for the Reactor Building, Steam Tunnel and Auxiliary Building resulting from the Design Basis LOCA in con-
. junction with a Loss of Offsite Power were calculated and are documented in Sargent & Lundy documents 3C6-0681-002, 3C6-0481-005 and 3C5-0481-004 m respectively, as referenced in Design Criteria A51 9 and available in C the Central File for review as noted in Section 2.1.
2.1.2.2. High Eneray Line Break Accidents The LOCA identified in section 2.1.2.1 is the most severe High Energy Line Break af fecting equipment inside Containment. Pressure and temperature transient analyses for Hiah Energy Line Breaks outside Primary Containment were performed. Breaks in the following high energy lines were analyzed:
- 1) Main Steam Line Break with simultaneous Feedwater Line Break in the horizontal portion of the steam tunnel
- 2) Main Steam Line Break with simultaneous Feedwater Break in the vertical portion of the steam tunnel
- 3) Reactor Core Isolation Cooling Line
- 4) Reactor Water Cleanup Lines (3 break locations)
The Sargent E Lundy " WARLOCK" computer program was used in these analyses. The pressure and temperature conditions resulting from these breaks in the areas of the breaks, in other areas of the Reactor Building and of the Auxiliary Building were determined conservatively for all six cases with certain well judged assumptions. These analyses are documented in Sargent & Lundy documents MAD-40764 and 3C6-1173-001 b] and Appendix D of the Zimmer FSAR as referenced in Design Criteria A51-9. The temperature and pressure conditiona identified in Desian Criteria A519 for each zene represents the worst case condition.
Th3 Cincinnnti G:s & Electric Company has completed an analysis to datermins the environment resulting from a pastulated Scram Discharge Volume break in accordance with NUREG 0803. The results of this analysis are documented in Sargent & Lundy calculation 3C6-0483-003. The results of- this calculation show that the environ.nent is l'ess severe 2 1 than that produced by HELB or LOCA conditions as defined in 3&L Design Criteria A51-9. The equipment and components necessary for safe shutdown and long term cooling following a SDV break are the same as those necessary for a LOCA or HELB. Therefore, the effects of NUREG 0803 have been enveloped in our review. 2.1.3 Radiation Inside and Outside Containment Calculations were perfort onsistent with the requirements of NUREG 0588 and Section II.B.2 of NUdEG 0737 to determine the dose v.alues for each environmental zone. Each zone dependent equipment qualification dose is based on the sum of the radiation exposure in that zone due to 40 years of normal operation and the radiation exposure in that zone resulting from the design basis LOCA, plus a 10% margin. It is judged that, for the purposes of radiation qualification, the desian basis LOCA is the bounding case. The zone dependent 40 year operating dose is determined from the peak operating dose rate in that zone. If applicable, a duty cycle, or fraction of the plant lifetime during which the dose rate applies, is accounted for by an appropriately determined availability factor. Otherwise, the dose rate is assumed to be constant over the 40 year plant life.
, The zone dependent postaccident dose is determined by summing the
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separate doses resulting from piping carrying postaccident core ecolant, filters, airborne radioactivity, and other doses as appropriate (e.g., the dose through a drywell penetration). Each separate dose is integrated over a period of one year to yield the total integrated dose. The specific doses which are summed to yield the total postaccident dose in each zone are described in the calculation for that zone. The piping, filters, and other sources of radiation which produce theae doses are determined from reviews of general arrangement drawings, structural drawings, physical piping drawings, and the final safety analysis report. The specific postaccident dose from piping, filters, etc. are calculated using the methodolody of NUREG-0588 as applied to a BWR5/ MARK II system. A detailed description of the calculation methods used to generate these doses is provided as the preface of the Sargent & Lundy Report, Project No. 6020-16 which contains the calculation referenced in Design Criteria A51-9 for each zone. This report is available for review in the Central File. 2.1.4 Radiation Effects on Solid State Equipment in Mild Environments The review of safety-related solid state equipment in mild environments has been completed and Table 2.1-1 has been updated accordingly. During the course of the review, it was determined that several of the mild 2 environmental zones (Table 2.1-2) did not experience significant 'Q d increases in radiation exposure durina an accident. criteria was used to make this determination: The following
- 1) Bate particles would not be able to penetrate the plastic or m tel container housing thu semi-conductor material and therefore the beta contribution to the accident dose can be eliminated.
( 2) Total normal and accident dose is less than 103 RAD. (This number is felt _to be conservative based on-April 25, 1983 letter from Dr. M. V. Davis of Georgia Institute of Tech-nology, Fiquee 2.1-1 and position 5 of the AIF position paper on Radiation Considerations for Equipment Qualification Figure 2.1-2). 2 Documentation packages have been prepared for all safety-related solid state equipment located in 105 to 104 RAD environmental zones. This includes equipment that has been exempted by location specific dose calculations performed by Sargent & Lundy Engineers. It should be noted that the Hays 252 Differential Pressure Transmitter and the Rosemount 442A Temperature Transmitter are being replaced due to seismic quali-fication deficiencies. The replacement unite will be qualified to the appropriate radiation levels. In addition, radiation testing is planned for the Transmation cevices and the battery chargers furnished by Power Conversion Products are being reviewed. These packages will be updated as additional information becomes available. 2.2 SUBMERGENCE DUE TO FLOODING 2.2.1 Drywell The submergence of components located above the top of the downcomer vents due to flooding in the drywell is not a concern due to the design em of the Mark II containment. ! )
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A large pipe break inside the primary containment will only flood the drywell to the top of the downcomers and increase the suppression pool water level. To date, our review indicates that the only equipment located below the top of the downcomer vents in the drywell consists of 2 electrical cable, with the exception of one (1) essential junction box (JBWR01) which contains a terminal block. This junction box will be relocated above the maximum flood level prior to fuel load. The electrical installation specification (H-2173) will be modified to prevent the installation of essential electrical equipment below the top of the downcomer vents. The effects of submergence has been evaluated for all cable located inside primary containment. 2.2.2 Suporession Pool The only safety-related electrical components located in the suppression pool are Gordon Temperature Elements. The vulnerable electrical portion _ of these devices are located above the maximirn expected water level of 512.5 feet due to suppression pool swell. Conduit Seals will be added 2 to these devices to insure qualification due to humidity. 2.2.3 Reactor Building The areas of the plant which contain safety-related equipment are separated from one another by flood-proof walls and doors. Each [] safety-related equipment room is provided with an independent drainage sy stem. Flooding of one of the emergency equipment rooms caused by a pipe or component failure cannot affect the functioning of the equipment in other emergency equipment rooms. 2.2.4 Steam Tunnel The break of a main steam or reactor feedwater line anywhere inside the steam tunnel will cause a steam / water mixture to be released into this
~s area. The turbine building por. ton of the steam tunnel is open to the
(' ' ' , turbine building thereby providing a large reservoir for potential accumulation of water. There are no essential components located low enough in the turbine buildiaq to be susceptible to flooding. The reactor building portion of the steam tunnel is isolated from the adjacent ECCS pump cubicles by massive st ructural walls and bulkhead doors. It has been conservatively assumed that the total mass release would condense and accumulate on the floor of the steam tunnel to a level of approximately 1.8 feet. The essential components are located high in the steam tunnel away from this potential flood level. 2.3 CONTAINMENT SPRAYS 2.3.1 Drywell Sprays The drywell spray subsystem is a totally manual mode of the Residual Heat Removal System (RHR). Administrative controls prohibit activation of the spray system within ten (10) minutes after the Loss of Coolant Accident (LOCA) occurrence because the core cooling systems are designed to be fully automatic throuch this period. The operators are therefore procedurally controlled to prevent terminating ECCS flow to the core for the first ten (10) minutes in order to assure adequate core cooling for all break sizes. There fo re , simultaneous activation of ECCS and the spray system during the first ten (10) minutes of the event will not occur. 77 The conditions for which the operator must initiate the drywell spray
! ,) are shown in Emergency Procedure Guideline number OP.EPG.02 revision 4. l2 The condit. ions shown in this procedure are as follows:
- 1) 2.1.3 IF... Suppression pool pressure reaches the drywell spray limit, figure 2.2 THEN... Secure RR pumps, VP cooling fans and initiate l2 drywell sprays in accordance with OP.RH.01.
- 2) 2.2.2 IF... Drywell temperature reaches 340*F, THEN... Secure RR pumps, VP cooling fans and initiate l2 drywell sprays in accordance with OP.RH.01.
The lowest drywell pressure for which the operators must initiate the drywell spray is 26.1 psig (reference fioure 2.2 of OP.EPG.02) . The highest drywell pressure after ten (10) minutes is 22.7 psio (reference FSAR tables 6.2-3). The highest drywell te9perature after ten (10) minutes is approximately 240*F ( reference FSAR figure 6.1-14) . It should be noted that these values were calculated assumina one (1) RHR heat exchanger without containment spray. Based on the above infor-mation it is highly unlikely that the drywell spray will ever be initiated. Even thouah we feel that the drywell spray will not be used, we have f'; addressed the effects of containment sprays on equipment located in the L' drywell (zone C-1). 2.3.2 W5twell' Sprays The wetwell . spray subsystem :is a fully automatic mode of the Residual Heat _ Removal System ' (RHR) . The. automatic initiation logic for this p system is shown in FSAR subsection 6.2.1.3.4.4. The logic for this V- system is designed to initiate the wetwell spray twelve '(12) minutes after the' occurance of the t0CA if the' wetwell pressure is greater than or equal to thirty-five (35) psig. The operator may initiate the wetwell spray manually after ten (10) minutes. The condition for which the operator must initiate the wetwell. spray -is'shown ir. Emergency Procedure Guideline number OP.EPG.02 revision 4. The condition shown in this procedure is as follows: l2
- 1) 2.1.2 BEFORE...... Suppression pool pressure reaches the suppression pool spray limit, figures 2.1, INITIATE... Suppression pool sprays in accordance with OP.RH.01.
-The lowest suppression pool pressure for which the operator must initiate the wetwell spray is 13.5 psig (reference figure 2.1 of OP.EPG.02). The highest suppression pool pressure after ten (10) l
^ minutes.is 22.7_psig (reference FSAR table 6.2-3). It should be noted
. that- these values were calculated assuming one (1) RHR heat exchanger without containment spray. ' Based on the above information it appears that even though-the requirements for automatic initiation of the wetwell spray are not met the system will be manually initiated by the operator. ,r g The 'ef fect of wetwell sprays on safety related electrical equipment -(/ located in the wetwell.(zone C-2) has been addressed in our program.
2.4 HARSH ENVIRONMENTS The- Primary Containment, Reactor Building and some portiore of the
' Auxiliary Building are exposed to Harsh Environments resulting from the postulated LOCA or HELB accidents.
A Harsh Environment has-been defined in our Nuclear En.cineering Procedure NEP-3.8 as follows: e l2 Area of plant _where postulated LOCA or HELB accidents create-significant. increases in temperature, radiation, relative humidity, or pressure from normal values as documented in Design Criteria A51-9. The following zones are considered Harsh Environments in this report: C-1 R-4A,B,C,D,E,F T-1 C-2 R-SA,B,C,D A-3C,0
.R-1A,B,C R-6A,R,C A-5A,8 R-2A,8 R-7 A-6A,B,C,D,E
-R-3A,B R-8 O
.1-1 TAB Revised 12/21 SAFETY RELATED EQllIPMENT CONTAINING SOLID STATE ELECTRONICS IN MllD ENVIRONMENTS MANF. MODEL & DESCRIPTION ZONE & DOSE STA rilS ' TEST DOSE & WEPORT COMMENTS (WORST CASE)
- Bailey 701 Basic Controller A-1 5x102 RAD EX 745 Alarm linit A-1 5x102 RAD EX 750 Square Root Extractor A-1 5x102 RAD EX 752 Input Summer A-1 5x102 RAD EX 753 Mtyl* plier / Divider A-1 5x102 RAD EX Basler DG Voltage Regulator D-1B 8.72x102 RAD EX DG IJF/0V Assembly D-1B 8.72x102 RAD EX DG Auto Synch Relay D-1B 8.72x102 RAD EX S
DG BKR Equalizer Relay D-1B 8.72x102 RAD EX DG Speck Sensing Assembly D-1B 8.72x102 RAD EX DG Field Conditioning Relay D-1B R.72x102 RAD ' EX _ CAD 5x104 RAD - Wyle Lab Batteries ARR 130 Baltery Chargers A-3A 7.15x103 RAD 0 Report 44138-1 9/21/78 Eberlina CLI-l Communicalion Line Isolator A-7B 2.3x102 RAD EX DAM-1 Data Aquisition Module A-7B 2.3x102 RAD EX DAM 4-6 Data Aquisition Module A-78 2.3x102 RAD EX GE Neutron Monitoring System A-1 5x102 RAD EX 9T66Y Power Supply A-3A 8.53x102 RAD EX S&L Location Specific Dose Calculation ZI-EQ-28 Dated 9/29/83 129B2802Gli Ind. Trip Unit IA-1 5x102 RAD EX ___ 238X660C007 Loa. Rad. Monitor A-1 5x102 RAD FX
a~ I TABLE -.1-1 Revised 12/21/ s . SAFETY RELATED EQllIPMENT CONTAINING , _ , SOLID STATE ELECTRONICS IN MILD ENVIRONMENTS MANF. MODEL & DESCRIPTION ZONE & DOSE STATils TEST DOSE & REPORT COMMENTS (WORST CASE)
- Hays 252 Differential Press. Trans. A-7A 6.80x103 RAD R Replace ECR 925 Rev. 1 Due to Seismic Problems ITE/ Power 9hield Trip Unit A-3A 7.15x103 RAD Q 1x105 RAD-Brown Boveri G0llLD File #190 (Letter 8/12/83)
Kepco PCX 72 Power Supply A-7A 6.88x103 RAD Q 1x107 RAD - MCC Powers Report 734-79.001 Rev. 3 Dated 2/4/81 Pa. 89 L&N Speed-0-Max Mark III Racorder A-1 5x102 RAD EX Love 48 Current Relay A-7A 6.80x103 RAD Q 1x107 RAD - MCC Powers Controls Report 734-79.001 Rev. 3 h Dated 2/4/81, Pg. 31 54 Proportional Controller A-7A 6.88x103 RAD 0 lx107 RAD - MCC Powers Report 734-79.001 Rev. 3 Dated 2/4/81, Pg. 8 56 Current Relay A-7A 6.88x]D3 RAD Q 1x107 RAD - MCC Powers Report 734-79.001 Rev. 3 Dated 2/4/81, Po. 20 MDA 7060 Fan Ammonia Detector A-7A 6.88x103 RAD Q 6xlOS RAD - MDA Scienti-Scientific]' fic Report EQR-82.0ll Rev. O, Dated 8/20/82 Power 3Sil Batt ery Charger A-3A 7.15x103 RAD llR Conversion Products S Dattery Charger A-3A 7.15x103 RAD UR Riley 36 PTGF-EBG Temp. Alarm Unit A-1 5x102 RAD EX 86 PTGF-EGR Temp. Alarm Unit A-1 5x102 RAD EX 86 VTFF-EGB Temp. Alarm tinit A-1 5x102 RAD EX
'Nmm.#'
TABLE 2.1-1 Revised 12/21/83 SAFETY RELATED EQUIPMENT CONTAINING SOLID STATE ELECTRONICS IN MILD ENVIRONMENTS MANF. MODEL & DESCRIPTION ZONE & DOSr STATHS TEST DOSE & REPORT COWtENTS (WORST CASL)
- Rosemount 1151 Diff. Pressure Relay A-7A 6.RRx103 RAD Q 2x106 RAD - Rosemount Report 97215A Dated 9/21/72 442A Temperature Trans. A-7A 6.88x103 RAD R Replace ECR 962 TEC SRV Acoustic Mon. System A-1 5x102 RAD EX Topaz Inverter A-3A 8.53x102 RAD EX S&L Location Specific Electronic Dose Calculation Zl-EQ-28, Dated 9/29/03 Filter inverter A-3A 8.53x102 RAD EX cil Location Specific c) hose Calculation Zl-EO-28, Dated 9/29/03 Trans- 230lT E to I Convertor A-1 5x102 RAD EX mation 600 Series Themocouple to 1 A-1 5x102 RAD EX Convector 610 Series Temperature Relay A-3A 7.15x103 RAD TEST 620 Series Thermocouple to I with A-1 5x102 RAD EX Alarm 650 Series RfD to I with Alarm D-1B 8.72x102 RAD EX S-220A Dif ferent ial Press. Relay A-7A 6.88x103 RAn IESI S-520A Sional Convertor A-3A 7.15x103 RAD TLST Vitro Essential Relaf Panels A-3A 8.59x102 R t.D EX SAL Location Specific Dose Calculations ll-EQ-24, Zl-EQ-25, ZI-EQ-26, Dated 9/29/85
y TABLE 2.1-1 Revised 12/21/83 SAFETY RELATED EQUIPMENT CONTAINING SOLIO STATE ELECTRONICS IN MILD ENVIRONMENTS MANF. MODEL & DESCRIPTION 70NE & DOSE STATUS TEST DOSE & REPORT COMMENTS (WORST CASE)
- Wallace & 50-125 Chlorine Detector A-7A 6.88x10) RAD 0 1x104 RAD - MCC Powers Tiernan '
Report 734-79.001 Rev. 3 Dated 2/4/81, Pa. 232, 243 Westronics D4N Chart Recorder A-1 5x102 RAD EX Woodward 2301/8270-180 Load Sensor D-18 8.72x102 RAD EX
- 9. G. Gov.
2301/8270-189 Freq. Sensor D-1B 8.72x102 RAD EX D. G. Gov. 2301/8270-201 Power Supply D 1B 8.72x102 RAD EX
- 1. 2301/8270-768 Amplifier D-1B 8.72x102 RAD EX T D. G. Gov.
- LEGEND Q -Qualified EX -Exempt 8 -Replace UR -Under Review TEST -Test
O O O TABLE 2.1 Revised 12/21/83 EXEMPTED ENVIRONMENTAL ZONES
'l ZONE 40 YEAR DOSE l ACCIDENT BETA DOSE ACCIDENT GAMMA DOSE TOTAL GAMMA DOSE l
A 1.75x102 RAD 2.035x102RAD 5.73x101 RAD L '2.323x102 RAD A-38 3.50x102 RAD 2.68x102 RAD 3.21x102 RAD. 6.71x102 RAD , A-78 1.75x102 RAD 1.237x101 RAD 4.722x10 .1 RAD 2.222x102 RAD. 4 D-1B 3.50x102 RAD 2.68x102RAD 5.25x102 RAD 8.75x102 RAD S-1 2.98x102 RAD -2.68x102 RAD 2.00x102 RAD 4.98x102 RAD S-2 2.98x102 RAD 2.68x102 RAD 2.00x102 RAD 4.98x102 RAD i 1 4
s
. Georgia Institute of Technology e-R" -
SCHOOL OF NUCLEAR ENGINEERING AND HEALTH PHYSICS ATLANTA, GEORGIA 30332 NEELY NUCLEAR ACSEAACH (404:894-3600 CENTEA April 25, 1983' Mr. c. A. Parker Zimmer Nuclear Power Station U. S. Route 52 Noscow, Ohio 45153
Dear Mr. Parker:
This letter is in response to your request for a threshold level for radiation dar. age to solid state circuitry of any type. In the past I have not known of any observed damage belcu 3"cc-l.000 Rad howevar; in the inturest of conservatism and laching detailed knowledge of the circuitry I would r eco:amena that you use a level of 1C00 dad as your design thrauhold. O U I .ill f ur ther recor.u tend that you maasure the actual tarcsnolu ainca it maybe much highar tl.an ti.e above aantionea values especially if there is an enclosure v;hich uill prevant any dose fron incident beta particles. , Very trul{ "ours,
# R
/
-)
Monte V. Davis, Professor MVD:lrm Figure 2.1-1 4 A Umt of the Uravers.ty System of Georgia An Equal Educanon and Employment Opportumty insteten _. , . - - . _ . _.__ - - , , . . _ _ , - . _ , - ~ _ .
%s A NUCLEAR INDUSTRY POSITION PAPER ON RADIATION CON 9IDERATION3 FCR EQUIPMENT QUALIFICATION 4
Prepared based on inputs received at an NSAC sponsored workshop attended by those in the attached list, and reviewed and approved by members of the AIF EQ Subcommittee, Utility owner's Group, and AIF Licensing Steering Group. Mr. I. Haas - Long Island Lighting Co. - Chairman Mr. S. Kasturi - EDS Nuclear - Moderator Mr. F. Akstulewicz - USNEC Mr. SL Ostrow - EBASCO Mr. E. Warman - Stone & Webster Mr. L. Bonzon - Sandia Laboratories Mr. JN Smith - General Electric s Mr. J. Brtis - Sargent & Lundy
.( $ Mr. W. Parkinson
\~ Mr. S. Ingeneri
- Oakridae National Labs.
2
- Stone i Webster Inc.
Mr. C. Pelletier - SAI Mr. P Littlefield - YAEC Mr. P. Karatzas - Boston Edison Issue Record No. Description Date
- 1. Comment issue by workshop participants 10/Ob/81
- 2. Comment issue to AIF. E.O. Committee 11/13/81 l 3. Membership Comments resolved AIF-EQ Subco=mittee 01/20/82
- 4. Comments from IDCOR/AIF Representative incorporated 03/05/82
- 5. AIF representative comments incorporated 04/21/82
- 6. Forwarded to the USNRC by AIF letter from Mr.' Richard M. Eckert to Mr. Richard H. Vollmer. 08/24/82 1
- 7s Figure 2.1- 2
~ V) i
p 4
\, /
1.0 INTRODUCTION
Numerous NRC documents (e.g.: I.E. Bulletin 79-01B, NUREG-0588, NUREG-0737) delineate the requirements for radiation considerations in equipment qualification. Pursuant to the commission order CLI-80-21, the staff has underway the development of a rule addressing the various aspectJ of equipment qualification, including radiation considerations. The NRC documents in ref erencer 1 thru 12 above have numerous inter-document and intra-document inconsistencies reflecting.the evolutionary process in establishing these requirements. This position paper sets forth our position on the radiation considerations for equipment qualification. 2.0 POSITION Licensing source tern assumptions, specifically the characteristics and magnitude of the released fission products, are consistent with the state-of-the-art and adequate to assure _ plant and public safety. While we feel that such source terms may be overly conservative, changes to these assuertions should be preceded by 6dditional analytic and experimental data which more firmly establish fission product evolution, transport and
/'
distributing processes. Further, no changes should be made to the existing Design Basis Accident (DBA) source term framework (_)T. until the supporting data and a clear understanding of tre replacement framework are available. However, we feel that the instantaneous release assumption and practices presently employed to establish doses to safety related equipment will require modification. Beta dose to equipment, particularly internal components sensitive to radiation is often insignificant compared with the concommittant gamma dose, when more realistic modeling that accounts for the shielding is applied. Radiation threshold dose levels for various generic types of materials and components should be established below which equipment can be considered exempt from demonstration of its capabilities by testing / analysis. The rationale behind these industry positions is provided in Sections 3.0, 4.0 and 5.0 below.
3.0 BACKGROUND
The procedure of qualifying a piece of equipeent to a given - radiation exposure may be considered as having two steps. First determining the radiation dose (gamma, beta, etc.) to it from all sourcess second, demonstrating qualification by a combination of testing, analysis, etc. In order to accomplish the former, the NRC specifies radiation source terms to be used in dose calcu?otions, and certain specific requirements in establishing doses to equipment. m Figure 2.1-2
. r 's
~ ' ./}
Determination cf radiation source terms and dose to equipment, requires consideration of the following, among others: 1.
. Time dependance and magnituda of the source terms released from the core.
2. Deffnition of the pathways, and time-dependent - locations applicable to the diffetent groups of radio'nuclides following their release srom the core including partitien factors into airborne, waterborne (pressurized and depressurized), removal / transport factors, such as plateout cond ens ~at ion, suppression, pool scrubbing, and wash-out and wash-off coefficients. 3. Realistic calculated models for performing dose calculations locations. for different types of radiation in different
- 4. Assessment of shielding effects.
4.0 REGULATORY HISTORY Guidance for determining equipment qualification doses continues to evolve within the NRC. The following presents a brief outline of its history. NUREG-0578,5 NUPEG-0588,2 and IE Bu11eton 79-01B1 are some of the documents that are applicable to equipment ( fs qualification. Source terms stated in TID-148446 whose g'
^- '} Furpose was judging tht suitability of a proposed reacter site and not equipment qualification, are used in these docu=ents.
NUREG-0737 modified these requirements by specif ying that leakage f rom systems outside of containment, and noble gases in depressurized cooling water, need not be considered. The NRC also commissioned a s a review of WASH-1400gudy, NUREG/CR-12376, which was basically
, " Reactor Safety Study", to establish best-estimate source terms for use in establishing doses to equipment for equipment qualification purposes. The results of this study, however, have not been endorsed by the NRC and were considered to be overly conservative.
Recently, as a result of the nuclear industry's position on the behavior of cesium and iodine af ter a LOCA, and the assertien (partially based on TMI experience) that the iodine environmental impact has been overestimated in the past, the NRC has issued NUREG-077110 and NUREG-077211, which review the bases and regulatory impacts of source ter= assumptions. The NRC has released a draf t, dated February '82, of prcposed Negulatory Guide 1.89, Rev. 1,4 " Environmental Qualification of Electric Equipment Important to Safety for Light-Water-Cco1+d ~ Nuclear power Plants". This draf t revision of the regulatory guide proposes revising the source terms by: (1) adding 50% cesium activity to the fraction of the core inventory released: (2) including a time delay for LOCA's where the break can be isolated: 'and, (3) establishing more conservative source term based on WASH 1400 for selected post accident monitoring 12 instrumentation. A t i Figure 2.1-2 V i l E,
- In view of these, and other, examples of regulatory inconsistencies, we prepose an approach to the resolution of the many specific technical differences, i.e.r source term assumptions, dose calculations, etc. for equipment qualification purposes.
5.0 INDUSTRY POSITIONS This section describes our position on specific areas where technical differences exist between the NRC and the industry. 5.1 Position #1: Fission Product Release From Fuel We do not support the use of an instantaneous release assumption for source terms for dose rate calculations.
5.1.1 Discussion
The current NRC assumption (Refs. 2 and 4, for example) of instantaneous release of radionuclides from the core coincident with the start of an accident is unrealistic as it is not based on concideration of any physical mechanisms. There is ample evidence based on NRC and industry sponsored research (Ref. 9, for example) to _f 3 support the following statements: r J (/ 1. The core cannot begin to melt, and, thus, release the bulk of its contained radionuclide inventory, for a time period of at least, on the order of, 10 minutes, under the worst case accident scenario.
- 2. If core meltdown was assumed it would not result in the release of all of the radionuclides at one time but would rather release the radionuclides in a manner consistent with their volatility, core temperature and transport rates out of the reactor pressure vessel.
Release assumptions should therefore reflect the known sequence of iodine spiking gap, release followed by melt down, vaporization and oxidation f ractions.
- 3. Dif ferent radionuelides have dif f erent release rates.
In addition, the chemical form of the fission products released frcm fuel is of equal importance to the percent that is released. In particular, it is incensistent to assume a release of 50% of the core I activity of iodine and 50% of the core activity of cesium without considering the predominant chemical
- form of iodine and the subsequent barriers to fission -
product transport. Incorporation of more realistic assumptions based on i time of release from the core, counled with consideration of transport time out of the core, would have an ameliorating effect on qualificatien of equipment to radiation environments in that: The
, ; /~s
() v Figure 2.1-2 _ . ~ . _ . ~ ._ . _
doses to equipment' required to function for only short times af ter an accident minimum 1 hour' time margin requirements)(disregarding present wo'ld be reduced by a u significant amount. This will have significant effect on qualification of some equipment that'would not otherwise need to be demonstrated as qualified with respect to radiation, and would reduce.any cost of testing / retesting. 5.1.2 Recommendation It is, th,erefore, recommended (1)- That a more realistic, though still conservative and enveloping, models of time dependent release of radionuclides from'the core be incorporated into regulations,'and (2) That the one-hour minimum time margin be deleted-for cases where it can be demonstrated that a piece of eqt'ipment-is aht needed to function only for a certaan
- t time period following an accident, and that its physical integrity or functional capability is of no consequences of to the: safety of the plant or uitigation an accident after'it function. has performed its bafety
'5.2 Position 02: Fission Product Distribution
/" 3 Present NRC assumptions regarding fission product
_(used distribution
\s / in the-development'of licens1ng source teres for equipeent qualification) within the various volumes of the containment system and its removal are highly consersative.
the assumption of 50% iodine released into containmentIn particular, atmosphere addition, is-an over_ estimate in light of recer.c data. In the effectiveness of. engineered safety features, and plateout-in removal of airborne iodine (especia11y'non-organic iodine) may have been signif2cantly underestimated. Further, the distribution of fission products released atmosphere and their removal by engineered saf into containment ety features have been inappropriately carried over f rem calculational assu=pt2ons used in determination of of f-site doses for siting.
.While most evidence suggests that the deter =inistic licensing source term in R.G. 1.3 and 1.7, which has been used in the past for equipment qualification,- is overly conservative, sufficient data on fission product transport exist'to change the assumptions. and
~ distribution does not yet Ho we ve r , sufficient data does exist to change the the regulatory Lother release periods. guides and should be used as necessary to supportinstantaneo the- fission product area theSince extensive research is ongoing in resultsbases of thisforresearch should provide, equipment' if necessary, the qualification techntcal source term. changang the
.m 0 Figure 2.1-2
- / 4,
%)
5.2.2 Reco=mendation That the NRC defer any changes to the assumptions regarding fission product characteristics and distribution (excepting the time dependent release aspects discussed above) used as - part of the licensing source term until the current fission pr od uc t/ t ra nsport experiments are concluded and reviewea and a clear understanding of the replacement framework is d,e velop ed . 5.3 Position #3: Beta Doses Beta do e to equipment, particularly internal components sensitive to radiation, is of ten insignificant cor. pared with the concommittant gamma dose, when more realistic modeling is applied to account for the shielding effects of the equipment enclosure. 5.3.1 Discussion The NRC generally endorses the calculation of beta doses within the containment using an infinite cloud model (see Refs. 2 and 4, for example), and using that value for equipment qualification. This simplistic model may yield reasonably accurate values for the beta dose in air at the containment centerline. In fact, industry calculated (~'} results generally agree rather well with those of the NRC. (,,/ . This approach overesti=ates the dose to an actual piece of equipment. For equipmenc qualificatter, it is inapprcpriate to use the sum of free-air beta and gamma contributions as stated in these NRC references. The proper equipment qualification dose is a good deal lower. than the sum of the f ree-air beta and gamma contributions. Due to the quite short range of beta particles in typical materials comprising a piece of equipment, it can be shown thats the geometry appropriate for beta dose calculation is usually, at most, a semi-infinite, and often a finite cloud even for quite small pieces of equipment. such as ' cable. This is due to self-shielding effects of the equipment, and the effects of enclosed spaces around the equipment. The majority of the equipment has sufficiently thick coverings around any radiation sensitive components ( or materials so as to reduce the beta contribution to the total dose to a level far below that (less than 10%) of the gamma contribution. l Proper attention to the above considerations will, in most cases, render tne beta dose insignificant when compared to
- the magnitude of the concomitant gamma dose.
5.3.2 Recommendation That the NRC allow the use of the semi-infinite and finite cloud models where applicable and Justified. I
\s /
l Figure 2.1-2 l a b' 5.4 Position e5: Radiation Threshold Levels A radiation threshold dose level should be established below which equipment can be considered exempt f rom demonstration of its capabilities by testing / analysis. 5 . 4 .1 ' Discussion Plastics and elastomers are used in power plant equipment in the form of gaskets, insulation, jackets, 0-Rings, seals, hoses, diaphrages, supports, and filler materials. Review of available data (Ref. 16 through 21) on various comr.only used plastics and elastomers used in the construction of the safety related electrical and instrumentation equipment shows that they have a threstold* damage radiation dose level of 10E5 Rads or above. The exceptions are polytetra flouroethelyne or Teflon (1 x ICES Rads) and -polysulphide rubber (8 x 10E5 Rads), and some solid state electronic devices (less than 10E4 Rads). Lubricants and greases used in safety related electrical equipment have a threshold damage integrated radiation dose level of 10E6 Rads or higher (References 16 thrcu=h 20). A cormen design engineering practice used in the industry is to require exclusion of raterials snown to be carticula:ly se;eeptible to radiation by equipment cessen specitications
' and assure the same through the vend 6: drawincic0curent review process. ,, 5.4.2 Recommendation k_)r That equipment located in areas where tetal integrated gamma dose levels over the life of the plant er equipment including the post accident doses do not exceed 10E5 RACS (conservatively estimated to be one order of magnitude less than the~ threshold of detecteble ef f ects) should be exempt f rom requirements to demonstrate its radiation aging capabilities by type testing and/or analysis. For solid state electronic devices, the threshold level should be 510E3 RADS gamma.
In the context used herein, threshold damage radiation dose level 'is defined as that amount of integrated ga=ma dose which when absorbed by the material at a prescribed dose rate, causes degradation as measured by loss of 25% engineering properties of interest. Re vied of available data in various equipment qualification documents f rom various test facilities indicate that if the dose rate (s) at which this integrated dose is applied is within the range of 0.1 to 1 Megarads/Hr, no significant dose rate dependent effects may be present. It is, however, noted that dose rate effects are not well understood . and defined for all materials and that further generic study is required to totablish the proper range of dose rates. Figure 2.1-2 q LJ
'\
V) f
6.0 CONCLUSION
- 1. More realistic, though still conservative and enveloping, models of the time dependent release of radionuclides from the core should be incorporated into the regulat. ions.
- 2. Licensing source term assumptions, regarding the magnitude and chamical nature of fission products, presently used are consistent with the present state-of-the-art and adequate to assure plant and public safety. In most cases imC's source term assumptions as specified in NUREG-0588 are overly conservative. Further changes to existing DBA source terms should be deferred until the results of the various additional generic studies either presently underway or expected to be underway shortly, become available and provide valid justification f or the changes proposed.
- 3. Available experimental data demonstrates that the present NRC models for iodine removal capability of the spray system seriously underestimates the removal coefficient.
If, however, no credit is to be taken for its iodine removal capability, then caustic addition to the spray system may no longer be warranted.
/'} 4. For purpose of equipment qualification, the NRC should
(_/ recognize and endorse the cencept of a threshold damace rad aat ton dose level.
7.0 REFERENCES
- 1. I.E. Bulletin 79-013 " Environmental Qualification of Class 1E Equipment " January 14, 1980.
- 2. NUREG-0588, " Interim Staff Position on Environmental Qualification of safety-Related Electrical Equipment,"
Dec em be r, 1979 and Rev. 1, July, 1981.
- 3. 10 CFR 50.49, " Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants,"
Draft, June 17, 1981.
- 4. Regulatory Guide 1.89, " Environmental Qualification or Electrical Equipment Important to Safety for Light-Water-Cooled Nuclear Power Plants," proposed Rev. 1,
. Draft dated Feb '82
- 5. NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report .
and Short-Tern Recommendations," July, 1979.
- 6. TID-14844,." Calculation of Distance Factors for Power and Test R,eactor Sit es, " USAEC, March 23, 1962.
- 7. NUREG-0737, Section II-B.2, " Clarification of THI Action Plan Requirements," October, 1980.
13 V . Figure 2.1-2
^
7m l i V B. NUREG/CR-1237 (SAND 79-214 3), "Best Estimate LOCA Radiation ~ Signature, " January, 1980. 9.
-WASH-1400 (NUREG-75/014), " Reactor Safety Study - An
-Assessment Power Plantrof, "Accident October, Risks 1975. in U.S. Commercial Nuclear 10.
NUREG-0771,
- Regulatory Irpact of Nuclear Reactor Accident Source Term Assumptions,' (for comment) June, 1981.
11. NUREG-0772, " Technical Bases for Estimating Fission Product Behavior During LWR Accidents," June 1981. 12. Regulatory Guide 1.97 ." Instrumentation for Light-Water-Cooled huclear Power Plants to Assess Plant and Environs Conditions During and Following an Acc1 dent," Rev. 2, Deceube r, 1983. 13.
"A* Nuclear Industry Position Regarding the One Hour Minimum Operating Time Margin Requirement." Transnitted to NRC with AIF letter dated 8/24/82 to Mr. R2 chard M. Vollmer.
14. Letter from W.R. Stratton, A.P. Malinaustas, and D.O. Campbell to NRC chairman J. Ahearne, dated August 14, 19G0.
- 15. " Realistic Estimates of the Consequences of Nuclear Accidents," M. Levenson and P. Rahn, ERPI, August, 1980.
16.
"The Parkinson, Use of Plsstics and Elastomers in Nuclear Radiation,"
() s i W.W. Design Volume 17, O.1971, Sissman, ORNL, Nuclear Engineering and pg. 247-280. 17.
"A Review of Equipment Aging Theory and Technology," EPRI Report NP-1558-00, September, 1960.
18.
" Radiation Damage to Elastomers, Plastics and Organic Liquid, " C.G.
Collins and V.P. Calkins, GE Atomic Products Division Aircraf t Nuclear Prcpulsion Department. 19.
" Designers Guide to Radiation Effects on Materials for Use on Jupiter FLY-BY and ORBITER " IEEE Transaction Volume NS-26, August, 1979.
- 20. 1.E. Bulletin 79-01B, Attachment 4, DOR Guidelines, Appendix C.
21. M. Bruce. M. Davis, " Radiation Effects on Organic Materials in Nuclear Plants, " EPRI-NP-2129, Ncvember, 1981. q Figure 2.1-2 Q
3.0 EQUIPMENT LIST The Environmental Qualification Equipment List (E0EL) provided in Appendix B represents the safety-relat,ed electrical equipment lcoated in potentially harsh environments that is required to be environmentally /, 4 qualified. V 3.1 METHODOLOGY USED IN FORMAT 10N OF E0EL The following steps were followed to develop the E0EL for electrical equipment in harsh environments:
- 1) All safety-related elect rical devices identified from Zimmer Instrument Index, Valve List and Equipment List were listed by device tag number.
- 2) All electrical purchase orders were reviewed to identify the cables, terminal blocks, and splice kits used in the construc-tion of the plant. These items were then added to the list.
- 3) The location, manufacturer and model number of each device was identified.
- 4) The list was then sorted to include only devices located in harsh environments.
- 5) The systems containing equipment in this list were identified.
This list represents all systems containing safety-related equipment in harsh envirosiments.
- 6) The systems were reviewed to identify the required safety (g) function for each system for each of the postulated accidents.
The results are included in Table 3.1-1.
- 7) The Standby Liquid Control, Process Radiation, Neutron Detection, Reactor Building Ventilation, Turbine Building Ventilation, and the Reactor Core Isolation Coolino Systems contains safety related equipment. The harsh environment safety related electrical equipment of these systems perform no safety function for the mitigation of postuwted LOCA and HELB accidents except for the portion of RCIC equipmcnt required to mitigate a RCIC Line Break. This equipment has been exempted from qualification and is designated as NUREG 0588 Category EX in the E0EL. Failure mode ef fects analysee are provided as part of the justification for exemption from environmental qualification. Exemption data sheets are in Appendix F of this report.
- 8) Equipment of other systems located in harsh environments not required to* mitigate a LOCA or HELB accident are also exempted in the same manner as equipment identified in paragraph 7 above.
- 9) In addition to the device tag number, manufacturer, model number and locat ion, the specification, drawing, environmental zone, flood level requirements, active or passive safety p function and the Component Evaluation Data Sheet number are V included in the index.
- 10) As requested by the NRC in their November 29, 1982 request for additional information, a comparison between FSAR Table 3.2-1 and Table 3.1-1 was made. The results of the comparison are provided as Table 3.1-2 r
G' 3.2 MAINTENANCE OF RE E0EL As modifications are made to the plant, the E0EL is updated to reflect the changes. The EQEL is not updated until the equipment is actually installed in the Plant. The EQEL therefore represents the equipment currently installed in the plant and does not include changes that are currently in the design slage. 3.3 DISPLAY INSTRUMENTATION A review of the Zimmer Emergency Operatino Procedures (EOP) for postulated LOCA and HELB accidents was performed to ensure that all electrical equipment located in harsh environments required by safety-related display instrumentation is included in the harsh environments E0EL. The followino procedures were also reviewed since they are referenced in the LOCA and HELB E0P's:
- 1) Emergency Guideline Contingencies
- 2) Emergency Procedure Guidelines
- 3) Reactor Scram E0P V 4) Loss of Offsite Power E0P A list of all display instrumentation (note for this review, display instrumentation includes position indicating lights, annunciators, alarms, meters and recorders) was prepared. The Elcetrical Schematics, Wiring Diagrams, P&ID's and C&ID's were then used to determine the specific identification tag number for the display instrumentation, interposing equipment and field instrument.
In accordance with NRC Generic Leter No. 82-09, dated April 20, 1982, all non-essential field elements feeding non-essential display instrumentation were removed from the list. In addition, all equipment not located in a harsh environment was deleted from this list. The remainder of the list is shown in Table 3.2-1. This list represents all safety-related equipment located in harsh environments, providing signals to display instrumentation located in the Control Room. - Comparison of Table 3.2-1 with the EQEL for harsh environments shows that all equipment, with the exception of fifteen tag numbers marked with an asterick, is included in the harsh environment EQEL provided as Appendix B. Additional investigations show that these fifteen devices are being added to the plant and are not yet installed. As noted in Section 2.3, this equipment will be added to the program when 7_ it is physically installed. U
3.4 REGUtATORY GUIDE 1.97 A710 NllREG 0737 MODIF1 CATIONS Environmental Qualification of additional equipment required to meet Reg. Guide 1.97 and NUREG 0737 requirements is being addressed in the 73 followinq manner:
)
- Appendix G contains a listing of all Req. Guide 1.97 Cateoory 1 and Category 2 equipment which will be installed in a harsh environment. This listing contains the following: 1.97 Variable, 1.97 Category, equipment ID number, description manufacturer, model number, location, status, Engineering Change Request (ECR) end data sheet number. As the implemen-ting ECR's are closed nut, alI new equipment identified in Appendix G will be added to the EQEL as described in Sectica 3.2.
- Appendix H contains a listing of all essential electrical equipment required by NUREG 0737 which will be installed in a harsh environment. This listing contains the following: 0737 Item Number, equipment ID number, description, manufacturer, model number, location, status, ECR and comment. This listing is as complete as possible, but since some of this equipment is still in the design stage a complete listing of all pertinent information is not possible at titis time. Appropriate comments have been made for those items which have been incorporated in Req. Guide 1.97 requirements. As the implementing ECR's are closed out , all new equipment identified in Appendix H will be added to the E0EL as described in Section 3.2 As this equipment is added to the E0EL it will be evaluated to the f requirements of NUREG 0588 as applicable to the Zimmer station.
V
\
v TABLE 3 SYSTEMS CONTAINING CIASS IE ELECTRICAL. Rev i me<1 r.QUIPMTNT IOCATEt1 IN IlARSil ENgmMi'NTS I/25/81 EMERCENCY REACTCR CONT. CORE RESIDUAL CORTAINMENT ISO. l'REVENTTION OF S&T. CE R EACTOlt CORE ltEAT ItEAT AND INTEGRITY RADIATION SYSTFM CODE CODE ACCIDENT SilOTDeWN COOLING R T PtOVAI P l : h >VAI. CONTkOL RE!.F.ASE AUXILIARY POWER AP I A X X X X X X IIEl.B X X X X X CONTAINMENT HONITORING A X CM IlEl.B DC VOI.TAGE SUPPLY CA X X X X X X DC IIEl.B X X X X , X FERDIABILITY CONIROL llG I CA X T49 llEl.B IIICll PRESSURE CORE SPRAY IDCA X llP E22 IIELB X 1:0YWI.LL PNEUMATIC IDCA X X IN HEl B X MSIV l.EAKAGE CONTROL LC I CA X E32 l lIEl.Il a - h 1 LEAK DETECTION gp g33 IDCA X 111.1.16 X l.OW 1RESSURE CORE SPRAY rp g2; IEA X flEl.h X NUCLEAR HotLER gg g23 IMA X X X X llEl.n X X X X NEll1RtC MONITORINC NR C51 1.DCA N/A N/A N/A N/A N/A N/A
!!El R N/A N/A N/A N/A N/A N/A PRESSURE SUPPRFSSION ^ 3 PC B21 IIEl.H X PROCESS RADIATION HONITORIFC IAH A N/A N/A N/A N/A PR DI) N/A N/A IWI it N/A N/A N/A N/A N/A N/A g8 e.
TABl.E 3 SYSTEMS CONTAINING CLASS IE ELECTRICAL Revised EQUIPMENT 1.0CATED IN IIARSil ENVIRONMENTS 1/25/P1 4 EMERGENCY REACTOR CONT. CORE RESIDUAL CONTAINMENT ISO. PREVENTTION OF S&L CE REACTOR CORE I! EAT liF47 AND INTrrRITY SYSil:M RA!)lATION . CODE CODE ACCIDENT SilUTDOWN OK) LING REMOVAL, RMR)VAI. C(Wikot REl. EASE CONTROL ROD DRIVE !!YDRAULl(S RD C11
^ '
I ILELB X X REACTOR Bullt!NG AND CONTAINMENT DRAINS TO RADWASTE RE A X IIELB FIE D l' RAINS RF LOCA X llELB RESIDUAL llEAT REMOVAL I A X Ril E!2 X llELB X X X REACTG CORE ISOLATION COOLING RI ESI ^ ItELB X REACT G PROTFCTION RP IMA X
'C71 IIELB X REACTCO RECIRCUI.ATION RR B33 ,
J i REACTOR WATER CLEAN-UP RT C33 STANDBY LIQUID CONTROL ^ ^ "^ ^ ^ SC C41 IIELB N/A N/A "IA N/A N/A N/A N/A STANDHY CAS TREATMENT yc WA X llELB FRIMARY CONTAINMENT VlNTil ATION yp IKA X llELB PRIMAkV CONTAINMENT & SUPPRKSSION Pool. PtfRCE SYSTEM yq IEA X llEl.B REALTtG BUILDINC VENTII.ATION VR A NA NA A NA N/A l lIEl.B N/A N/A N/A N/A N/A N/A I
'* mes OE
w F O N!! OOE I I S A TTA / T N!Al E. N d) EhE eg VAR nj ER i $ R vp F aj Rg . O SY I 1 1 TR f. NCO ^ A EF k !/ NT l' N NN N
, I I O A C T
r D t N 0A C L A U I D A I TV ^ A SA u / Xx XX E EI }i Rf l N R E R O C S . IA L( TTV A A N' NAOI !/ X XX C E. OE} T N I ?1 CI I RN R TO CR R C EI O N LV T E I. ^ /A EN CR t XX X XX E AO u N E ECO I i l R C S SR Y N SA I CR W 3 A. I NOI f ETX ^ A!/ E. C N CC! T I I RA U N RC EE! A N 'J MRl S T! C E NT I A T AC N TO E NL D ^ B. B. ^i l A B. O CT N I C C 'l I E l Mlw I t L E l l NEl I M SE A MM EP E Tl ED St i CO YQ C SF L E
& D T y R 5 S O V V W 9 C
R E T A W _ G G N N N I. E N I. 1 O 1 0 T I 0 0 S T 0 C 1 S A I C D . I T E T N S N L 0 E M l V P C G N I U Q G N I F I D. D R l Y L E l S I T U D U A B N A B W E _ T R E e N _. S O C . - I T I B E C V h R R A R U O E E T C R S 6 IJD1 ke
} g 1/25/8b';
TABLE 3.1-2
. COMPARISONBETWEENFSARTABLEj.2-1 -
WITil JULY 16, 1982 E.Q. SUBMITTAL TABLE 3.1-1 FSAR TABLE SYSTEM CODE INCLUSION IN JULY 16, 1982 3.2-1 (S&L,GE) REMARKS E.Q. SUBMITTAL I. Reactor System B13 Not Included Essential Mechanical and Structural Components No Essential Electrical Components II. Nuclear Boiler NB, B21 Included System III. Recirculation RR, B33 Included System IV. CRD llydraulic RD, C11 ' Included System
- V. Standby Liquid Control System SC, C41 Included VI. Neutron Monitoring System NR, C51 Included VII. Reactor Protection System RP, C71 Included VIII. Process Radiation Monitors PR, D13 Included
y(7 (} G l/25/8b,?) V TABLE 3.1-2 COMPARISON BETWEEN FSAR TABLE 3.2 . NITil JULY 16. 1982 E.Q. SUBMITTAL TABLE 3.1-1 FSAR TABLE SYSTEM CODE INCLUSION IN JULY 16, 1982 3.2-1 (S&L,GE) REMARKS E.Q. SUBMITTAL IX. Rasidual IIcat Removal System Ril, E12 Included X. Low Pressure Core Spray System LP, E21 Included XI. liigh Pressure Core Spray System IIP, E22 Included XII. Reactor Core Iso-lation Cooling RI, E51 Included System XIII. Fuel Service Not Required to Mitigate LOCA Equipment F13 Not Included or llELB Accidents er i e " 9" u p ent Not Included H B Ac d t XV. In-Vessel Service Equipment Not Included Not Required to Mitigate LOCA or HELB Accidents I ] ::VI. Refinling Not Required to Mitigate LOCA Equipment Not Included or HELB Accidents No Electrical Equipment
( 1/25/8h TABLE 3.1-2 COMPARISON BETWEEN FSAR TABLE 3.2-1 ,
*WITH JULY 16, 1982 E.Q. SUBMITTAL TABLE 3.1-1 e
FSAR TABLE SYSTEM CODE INCLUSION IN JULY 16, 1982 3.2-1 (S&L,GE) REMARKS E.Q. SUBMITTAL XVII. Storage Not Required to Mitigate LOCA Equipment Not Included or HELB Accidents No Electrical Equipment DM XVIII. Radwaste WE No Essential Electrical Equipment. System _ WX Not Included Essential RE & RF Isolation Drain, WZ Valves Included XIX. Reactor Water Clean-up System RT, G33 Included XX. Fuel Pool Cooling and Clean-up System FC Not Included Non-Essential XXI. Control Room Pancis PM, 1I13 Not Included Mild Environnent XXII. Local Panels PL , 1122 Included Electrical Components Identified in Submittal XXIII. Off Cas System OG Not Include
- Non-Essential XXIV. Service Water System WS, Included
( })- lllT 1/25/8llhK TABLE 3.1-2
- COMPARISON BETWEEN FSAR TABLE 3.2-1 ,
MITH JULY 16, 1982 E.Q. SUBMITTAL TABLE 3.1-1 P FSAR TABLE SYSTEM CODE INCLUSION IN JULY 16, 1982 3.2-1 (S&L,GE) REMARKS E.Q. SUBMITTAL XXV. Instrument and Service Air System IN Included (Drywell Pneumatic) XXVI. Diesel Generator Systems DG. Not Included Mild Environment XXVII. Flammability Control System HG, T49 Included XXVIII. Standby Gas Not included in Table 3.1-1 Added in Revised Tabic 3.1-1 , Treatment System VG, But Equipment was in Submittal Inadvertantly omitted in July 16, 1982 Table 3.1-1 XXIX. Primary Contain-ment Ventilation VP Included System XXX. Power Conversion System B21 Included Essential Electrical Equipment Included XXXI. Cycled Condensate Storage and Trans- CY Not Included No Essestial Electrical Equipment fer System XXXII. Onsite A-C Power System (Aux Power) AP Included 4
- 1/25/8h TABLE 3.1-2 COMPARISON BETWEEN FSAR TABLE 3.22-1 ,
WITil JULY 16, 1982 E.Q. SUBMITTAL TABLE 3.1-1 FSAR TABLE SYSTEM CODE INCLUSION IN JULY 16, 1982 3.2-1 REMARKS (S&L.CE) E.Q. SUBMITTAL XXXIII. Emergency D-C. Power System DC Included XXXIV. Miscellaneous Components Included ECCS Water Leg Pump Motors Included in llP,LP, and Ril Systems XXXJ. Reactor Building Closed Cooling WR - Included Water System XXXVI. Equipment and Floor Drainage RE
- System RF Included XXXVII. Miscellanious Ventilation VR Included System
_ "T XXXVIII. Area Radiation Monitoring AR, D21 Not Included Non-Essential System XXXIX. Leak Detection System LD, E31 Included XL. Fire Protection System FP Not Included Non-Essential 9 e
[$ v TABLE 3.1-2
~ COMPARISON BETWEEN FSAR TABLE 3.2-1 .
DITH JULY 16, 1982 E.Q. SUBMITTAL TABLE 3.1-1 FSAR TABLE SYSTEM CODE INCLUSION IN JULY 16, 1982 3.2-1 (S&L,CE) :tEMARKS E.Q. SUBMITTAL XLI. Civil Stuctures Not Included Structures Not Included Because They Are Not Electrical Equipment XLII. Containment Related accum Breaker Valves Electrical Items Included Accessories and Electrical Penetra-tions Included in PC and AP Systems XLIII. Other Radiological Equipment Not Included Non-Essential XLIV. MSIV Leakage Control System LC, E32 Included XLV. Instrumerit and Included As Part of Each Safety Control Equipment Included Realted System Identified I e
r-mr-TABLE 3.2-1 E0P ' REVIEW EQUIPMENT LIST ILT-CM008 1TE-CM068 1TE-LD042 1B21-N020A-D
,_ 1LT-CM009 1E22-N002A,B 1TE-LD043 1B21-N023A-D
( ; ILT-CM022 1E22-N005- 1TE-LD044 IB21-N024A-E,G
\ ILT-CM023 1E22.-N008* ITE-LD045 IB21-N026A-D ILT-CM112A,B* 1E22-N009 1TE-LD046 1B21-N031A-D 1PT-CM010 1E22-N010* ITE-LD047 IB21-N036A-D 1PT-CM021 1E22-N013 ITE-LD048 1B21-N037A-D IPT-CMOS1 1E31-N001A-F 1TE-LD949 1B21-N038A,B IPT-CM082 1E31-N002A-F 1TE-LD050 IB21-N044A,B IPT-CM088A B* 1E31-N003A-F ITE-LD051 1B21-N045A-D 1PT-CM089A B* 1E31-N004A,B ITE-LD052 1B21-N047A-D ITE-CM045 1E31-N005A,B ITE-LD053 1B21-N048A-D ITE-CM046 1E31-N006A,B ITE-LD054 1B21-N051A,B 1TE-CM047 1E31-N008A-D ITE-LD055 ILIS-NB016*
ITE-CM048 1E31-N009A-D ITE-LD056 ILIS.NB017* ITE-CM049 1E31-N010A-D ITE-LD057 ILIS-NB018* ITE-CM050 1E31-N011A-D ITE-LD058 ILIS-NB019* ITE-CM051 1E31-N017A-D ITE-LD059 ILIS-NB020* ITE-CM053 1E31-N018A-D 1TE-LD086 1D13-N003A-D ITE-CM054 1E31-N022A-D ITE-LD087 1D13-N019A-D ITE-CM055 1E31-N024A,B ITE-LD088 1E12-N009A-C ITE-CM056 1E31-N027A-D ITE-LD089 1E12-N015A-C iTE-CM057 1E31-N028A-D ITE-LD090 1E12-N022A-C ITE-CM058 1E31-N029A-D 1TE-LD093 1E12-N028 1TE-CM059 1E31-N030A-D ITE-LD094 1E12-N029A,B ITE-CM060 1E31-N031A-D ITE-LD096 1PSH-RH005A,B ITE-CM061 ITE-LD038 1E21-N001 1 psi-RH006A,B g's ITE-CM062 1TE-LD039 1E21-N006 1PT-RH009A-C* (j' 1TE-CM064 1TE-LD040 1E21-N009 1C71-N002A-D ITE-CM066 ITE-LD041 1PT-LP002* 1C71-N004 Limit Switches on the Following Valves , ICM 003 1CM 023 IB21-F013A-H,K,L,P R.S 1E12-F016A,B 1CM 004 1CM 024 1B21-F016 1E12-F017A,B ICM 005 1E22-F001 1B21-F019 1E12-F023 1CM 006 1E22-F004 1B21-F022A-D 1E12-F024A,B ICM 007 -1E22-F012 1B21-F028A-D 1E12-F027A,B 1CM 008 1E22-F015 1B21-F065A,B 1E12-F040 1CM 009 1E22-F023 1B21-F067A-D 1E12-F041A-C 1CM 010 IIND08A,B IREu048 1E12-F042A-C 1CM Oll IIN 012 1RE 049 lE12-F047A,B ICM 012 11N 013 1RF 001 1E12-F048A,B 1CM 013 IIN 061 1RF 002 1E12-F049 1CM 014 IIN 170 1E12-F003A,B IE12-F053A,B 1CM 019 11N 171 1E12-F004A-C 1E12-F064A-C ICM 020 *1E21-F001 1E12-F006A,B 1E12-F068A,B 1CM 021 1E21-F005 1E12-F008 1E51-F008 1CR 022 1E21-F011 1E12-F009 1E51-F063 1E51-F064 IB33-F019 1G33-F001 1\P-012A,B 1E51-F076 1B33-F020 1G33-F004 IVP-045A,B LE51-F080 1B33-F355A-D 1G33-F040 (')' N- IE51-FB6 - IB33-F356A-D IVP-006A,B . 4.0 DOCUMENTATION REVIEW A review of environmental qualification documentation to the Category II requirements _ of NUREG 0588 Rev. 1 was conducted for all devices 7- identified in the Environmental qualification Equipment List (EDEL) in l2 Appendix 8. This review was performed by CG&E in accordance with Nuclear. Engineering Procedure NEP-3.8, " Review of Environmental Qualification Documentation."' This review included: Collection of all Qualification Documentation
- Review of documentation to the Category 11 requirements of NUREG 0588 Rev. 1 Preparation of the Component Evaluation Data Sheets for each device
- Preparation of the Documentation Reference Sheets Preparation of detailed action plans for each device requiring additonal action to establish qualification
- Preparation of Central File Documentation Packages for all devices.
A detailed comparison of NUREG 0588 Category Il requirements and CG&E's technical postion used to perform this review is included in Section 5 of this submittal. (3 G 9 O
5.0 COMPARISON WITH NUREG 0588 REV. 1 This section contains a detailed comparison of the Category 1} requirements of NUREG 0588 Rev.1 with CG&E's technical position used in
, -the review of existing documentation for all future qualification
/ act iv ities.
+
O lO t ! 1 i
' ' ' ~ - ,- . , , _ '
'?-
COMPARISON WITH NUREC 0588 REV. 1 NUREG 0588 REQUIREMENTS CATEGORY II CC&E TECrlICAL POSITION
~
.; z - -
- 1. EsTABListoirarf or 7tfE QUALITICATION 1.1 TEMPERATURE AND PRESSURE CONDITIONS PARAMETZAS FOR DESIGW BAS 15 EVENTS INSIDE CONTAINMENT-LOSS-OF-COOLANT 3.1 Temperature and Pressure conditions Inside ACCIDENT (LOCA)
Containment - Loss-of-Coolant Accident (LOCA) (1) The tisse-dependent temperature and pressure, (1) Time-dependent tenperature and established for the desita of the containment pressure profiles defined in
, structure and found acceptable by the staff' may be used far. environmental qualification the FSAR'for the Design Basis of eq.;ipment. LOCA defined and accepted in (2) Acceptable methods for calculating and
- the FSAR have been included in establishing the containment pressure the Zicmer Design Criteria A51-9 and temperature envelopes to which ' ' ,
and ,;.N. used in our prograt. equipment should be qualified are See Section 2.1.2.1 of the sumarized below. Acceptable methods for calculating mass and energy release , g rates are summarized in Appendix A. . *
-(2) -The method of calculating con-Pressurized Vater Reactors (PVRs) , .tainment pressure and temperature has been reviewed and accepted
( nry Centain=ent - Calculste IDCA con-tainment envaronment using CONTEMPT-LT through the FSAR. [m} U or equivalent industry codes. Additional guidance is provided in Standard Review Plan (SRP) Sectisa 6.2.1.1.A NUREG-75/087. Ice Condenser containment - Calculate 1DCA containment envarossent using IBTIC
- ,
- or equivalent industry codes.
Additional guidance is provided in SRP. ~
.. Section 6.2.1.,1.3, NUREG-75/087. s Bollina Wter Reactors (BVRs)
Mark I. II and III containment - Calculate IDCA envaronment using methods of CI3SAR Appendia 3B or equivalent industry codes. Additional suidance is provided in SRP Section 6.2.1.1.C. NUREG-75/087. . (3) In lieu of using the plant-specific contair.orat temperature and pressure . (3) Plant specific parameters defined design profiles fo'r BVR and ice in the FSAR and subsequently in De-
- condenser types of plants, the generic sign Criteria A51-9 are used for envelope abovn in Appcadia C may be used for qualification testing. review and retesting.
(4) e test profil'es included in Appendix A (4) gce Section 1.l(3), to IEEE Std. 323-1974 should not be con-sidered an acceptable alternative in lieu of using plant-specific contain- 'j (m * ' . 4 ment temperature and pressure design profiles unless plant-=pecific
!V :*
- analysis is provided to verify the I adequacy of those profiles.
.. .r
COMPARISON WITH NUREG 0588 REV. 1 v NUREG 0588 REQUIRDIENTS
'CATECORY'II CG6E TECHNICAL POSITION 1.f Teeperature sad pressure tendittens Inside Centstament - esin 5tese Ltse treak (r'.5 LB )
1.2 Temperature and Pressure Conditions Inside Containment - Main Steam Line Break (MSLB) t .(1) here qualification has not been com-
*/ . pleted, the envireimmental parameters
. used for equipseat qualification should .
(1) Time-dependent temperature and be salculated using a plaat-opecific Pressure profiles defined in the endet based en the staff-approved FSAR for the Design Basis LOCA , Q *,i'**g 3 di'***"d i* **** I . defined and accepted in the FSAR, have been included in the Zin:mer (2)* Other models that s're acceptable for Design Criteria A51-9 and are used calculatist containment parameters are listed in Secties 1.1(2). in our program. See Section 2.1.2.1 of the submittal. (3) la lieu of using the plaat-specific contaimment tewperature and pressure design profiles for swa and ice (2) See Section 1.2(1) condenser plaats, the generic envalepe , i, sheve in Appendiz C may be used. '- (3) See Section 1.2(1) (4) The test profiles included in Appendix A . to IIIE Std. 313-1974 should not be coa. (4) See Section 1.2(1) sidered as acceptable alternative in
. 11em of usias plant-specific contat am-st ,
tamperature aa.d pressure design profiles unless plant-specific analysis is pro- . vided to verify the adequacy cf these profiles. . . (5) Were qualificattoa has been completed (5) The Zic=e7 Design Basis Accident but ealy locA conditions were considered, them it must be demonstrated that the (LOCA) is a complete circumfer-1cca qualification conditions exceed or ential break of one of the Re-
..are equivalent ta the naximum calculated circulation Loop Pipelines. This E5LB conditions. The.following tech-atque is acceptables .
postulated accident has been de-termined to be the worst case (a) Calculata the peak ttsperature from PIPE break inside containment and as usu asing e del bued on the staffs approved assumptions dia-therefore is used for LOCA and l t 3""%i8 it**'l *f Appead'23. HELB inside containment. See hetion 2.1.2.2. (b) Show that the peak surface tamperature of the component to be (a) See Section 1.2(5) qualified does not exceed the IcCA qualification temperature by the method discussed f.a item 2 of (b) See Section 1.2(5) Appendiz 1. ; l i (c) See Section 1.2(5) (c) If the calculated surface temperstare exceeds the qualification temperature, the staff requ. ires that (1) additional i justificatica te prsydad to demonstrata l that the equipment can saistata ita l siquired functional operability if its
- aarface tamperature reaches the calculated value er (ii) requalification testing be l .
perfoned with appropriata margiaa. i ( O ~ or (112) qualified physical protec-r
. ~
.- '39-c l .
COMPARISON WITH NUREG 0588 REV. 1 [n') V
- NUREG 0588 REQUIREMENTS '
CATECORY II CC&E TECHNICAL POSITION _
. ties be provided to assure that the parface tamperature will not c.sceed the actual qualificaties temperature.
1.s rfreets of chemical spr*7 1.3 Chemical Sprays are not used. Demin-m effecta .f caustie sprav sh uld b, eralized water is used for Drywell and
.ddressed for the eqaipment qualification. Wetwell Containment Sprays. Effects The concentration of caustica used for of Demineralized water spray are con-qualification should be equivalent to er more severe than those used in the plant sidered. See Section 2.3 of the sub-
<eataf m==at spray system. If the chemical mittal.
composition of the cadatic spray can be affected by equipment malfunctieaa, the most severe causcic spray environansat that resulta , free a sissle failure in the spray system . ' should be assumed. See SRP Section 6.5.2 Oratzo-7s/cs7), paragraph II ite= (e) for caustic spray solution guidelines. .
- 1.4 Radiation conditions Inside and outsid* 1.4 Calculations have been conservatively performed to detumine the expected 7 m radiation environment for qualification radiation dose during the normal 40 of eqaspoent should be based on the normally years of operation and that associated
[V] espected radiation environment over the equipeent qualified life, plus that asso. - with the Design Basis LOCA described cisted with the most severe design basis in Section 1.1. These calculations accident. (DnA) during or followins which that equipment must remain functional. It should were performed consistant with Appendix be assumed that the DBA related environmental D of this NUREG. See Section 2.1.3 of conditions occur at the end of the equip.ent the submittal for more information, gealified life. , The sample calculation'a in Appendix D and the following positions provide an accept-able approach for establishing radiation limits for qualification. additional radiation margins identified in Sectica 6.3.1.5 of IIII Std. 323-1974 for qualificatloa type testing are act required if these methods are used. (1) The source term to be used in determining (1) The calculatbns described above were the radiation environment associated vsta based on these source terms. the design basis thCA abould be taken as as instantaneous release from the fuel * '
- to t .a atmosphere af.100 percent ef the l
, amble gases. 50 percent of the iodines,
. and 1 percent of the remaining fission products. for all other aca-ICCA design
*. l e.
C0liPARISON WITil NUREG 0588 REV.1 (/7> V NUREG 0588 REQtJIRE11ENTS CATEGORY II CC&E TECIINICAL POSITION ! basis accident conditions, a source term involving sa instantaneous relesse free the fuel to the atmospbers of 10 percent of the neble gases (except Er-85 for which a release of 30 percent should be assumed) and to percent of the iodines is acceptable. (2) h calculation of the radiation (2) The time dependent transport of re-eavironment associated with design basis accidets should take into leased fission products within the account the time-ciependent transport of various regions of containment and released fission products within various auxiliary structures were modeled usions of cottainment and an=111sry structuras. in the dose calculations. (3) The initial distributies of setivity (3) At t=0, the major fraction of the b == a cha i ti ra t nal a. source term was initially distributed , assumption. Eence, for compartmested in the drywell. containments, such as in a IkR, a large pertion of the source should be assumed ,a to be initially contained in the dryvell. .- _ _ _ _ - . - - - . _ _ _ _ . _ . _ The assumption of unif orm distribution of activity throughout the containment at time zero is not appropriate. N (4) Effects of E57 systans, auch as (4) No credit was taken for removal of [Q ' contaf-nt sprays and containment ventilation and filtration sysm, airborne activity bY containment which set to remove airborne activity sprays, ventilation and filtration and redistribute activity within con-saina.nt, should be calculated using systems. This approach is considered - the same assumptions used in the cal, more conservative, culation of offsite dose. See SRP Section 15.6.5 (NURIG-75/087) and the related sections referenced in the
- Appendices to that section.
(5) .Netars1: deposition (i.e., piste-out) (5) A conservative, rather than a mechanistic ser airborne activity shes14 be determined model for iodine plate-out was used.
- ssing a mechaaistic model and best No testimates' for the model parameters. credit was taken for removal of iodine eThe assumption of 50 percent inst.an- from surf aces by steam condensate flow or taaeous plate-out of the iodine released from the core should not be washoff by containment spray, made. Removal of iodine from surfaces by steam condenance flow or washoff by the containment spray may be
, assumed if such effects can be justi-fled as! quantified by analysis or .
apertswas. * - (6) Tec unshielded equipment located in the (6) For equipment located inside containment. r.'*t ' N 'b. g$$ to tUe e the gamma dose was conservatively calcu-deee rate et the centerreint of the lated as the sum of this immersion dose contain nt plus the contribution fr*" location dependent searces such as the at the centerline plus the dose from the sino water and plate-out, valess it can plated-out DUClides plus the Contact be hew by analy.as th.e location and
/q i dose on contained sources.
V t
.3
COMPARISON WITH E REG 0588 REV. 1 t . NUREG 0588 REQUIREMENTS I CATECORY II CG&E TECHNICAL POSITION shieldies of the equipment reduces the dose and dose rate. Q) for anshielded equipment, the beta doses at the surface of the equipen.a should (7) The Beta dose was conservatively cal-be tse sins of the airborne and plate-out culated as the sum of the dose due to searces. The airborne beta dose should nticlides plated-out on the surface be uzen as the beta dose calculated for a point at the containment center. plus the dose due to airborne nuclides, (8) Shielded components need be qualified (8) The Beta dose was conservatively requir d
.ho revi d an a lys that the sensitive portions of r test .
calculated assuming that no shield was ' the component or equapsent are not . thicker than the equivalent of 10 mils esposed to beta radiation or that the of steel. effects of beta radiation heating and ionization Lave ne deleterious effects
,es component performance.
(3) cables arnaged in cable trays in t.be 5'y",'] be a n un d te te (9) The dose to cables arranged in cable trays
,g ralculated for a pot.nt at the center of was conservatively calculated using the the containment plus the sassas ray dose same model as the dose to unthielded equip-calculated in accordance with Section 1.4(6). ment located inside the containment.
' This reduction in beta dose is allowed f because of the localized shieldicg by et.her cables plus the cable tray itself.
f (10) Painta and coatings should be assumed - to be exposed to both beta and gam * (10) The dose to paints and coatings was con-rays in assessing their resistance to servatively calculatedas thesum of the dose radiation. Place-out activity should at be assumed to remain on the equipment the centerline of the containment pitis
'* the dose due to contained sources plus the
.re.o *$ Ic ",1 ,a s sp y ussh- dose due to plated-out nuclides. No eff or steam condensate flow, can es justified and quantified by analysis credit was taken for removal mechanisims or esperiment. such as spray washoff or steam condersate flow, (11) ce.poneau of the emergency core coal-y . ins te I (11) The dose to the components of theECCS g, g st;,d;ut81d',co"*
and electrical equipment) should be t located outside containment was conser-qualified to withaund the radiation Vatively calculated as the sum of the
' radiation penetrating from the contain-tai sfpIstheUeu"re%=ta ment, plus the immersion dose from airborne surp fluid uains assumptions consistent with the requirements stated in nuclides plus the contact dose on piping Appeneix I to 10 tT2 Part 50. containing the sump fluid.
n '. (12) Equips.ent that may be orposed ta radia-
" (12) Environments postulated to receive doses Nt be o s de d a b7es t rom Breater than 10" rads have been considered radiation quclification. unless analysis supported by test data is to be Harsh Environments. Review of mild
'provided te verify that these levels environment equipment will address radia-
.111 nat degrade the operability of the tion qualification for equipment receiving e
m%qu.iIc*. eat below accepuble values. r **,
.. .. . __. . doses less than 10. . rads.
COMPARISON WITH NUREG 0588 REV. 1 hg NUREG 0588. REQUIREMENTS CATEGORY II' 'CG&E TECHNICAL POSITION (13) ne suff will accept s' given co=ponent b (13) Equipment.is considered qualified if ow. untie c#o .In mIsUe,e it can be shown that the component has qualified to integrated beta and ga.ma
~
*been qualified to integrated beta and doses whicF are equal to or higher than gamma doses equal to or greater than
[ti$ar*in aIt Is'sc t th t the total normal and accident radiation incli.ded in Appendiz D (wbsch uses de doses identified in Design Criteria A51-9. source term given in ites (1) above). and that the component incorporates appropriate factors pertinent to the plant design and operating character-istics, as given in these general guidelines. (14) When a conservattva analysis has not (14) Conserative Analysis has Ueen performed
. been provided by the applicant for staff review. the staff will use the radiation..a. as identified in Section 1.4.
aavaronment guidelines contained .i.a Appendiz D suitably corrected for t.be differences in reactor power level. . type, containment si.=e. and other _ _,. _ _ _ _ _ _ _ _ , _ _ _ spyropriate factors. 1.3 Invironnectal Canditions for outside 1.5 C*""'* '
, (1) Conditions resulting from postulated (1) Equip.ent located outside contair.=ent High Energy Line Breaks outside con-that could be subjected to high-enerry tainment have been calculated as iden-yipe breaks should be qualified to the conditiens resulting from the accident tified in Section 2.1.2.1 of this for the duration required. The teca* Submittal.
- siques to calculate the environmental persneters described in Sections 1.1 through 1.4 (Category II) above should be applied.
(2) Equip =ent located in general plant aress (2) This will be considered as mild en-outside containment where equipment is
' set subjected to a design basis accident Vironment. Equipment will be quali- .
fled to the mild environment require-environment should be qualified to the normal and abnormal range of enetron- ments. I ' sental conditions postulated to occur at the equipment location. (3) Iquip. cat not served by Class IE environ- (3) Credit was not taken for non-Class ,
==nt2 6 support syste... or served b7 Class 11 support syntess that may be 1E environmental support systems in secured during plant operation or shut. the calculations identified in l
i
' dows, should be qualified to the limattng eartronmental conditions that are postulateW Sections 1.5(1) above. Qualification for that location. assuming a loss of the to be established to these parameters.
envire mental support systes. Or . . . . . . . . . . . . . . . . th e re may b e . designa where a loss of the enetron-erntal support system mar espose some y equiper at ta enetronments that exceed I the qualified limita. Tor these destgns. l (
- i
. +'
l *
-=
COMPARISON WITH NUREG 0588 REV. 1 g/ NUREG 0588 REQUIREMENTS CATEGORY II CGSE TECHNICAL POSITION appropriate asettorier devices should be peevides to slert the operstor that abeermal renditions exist and to permit sa essesseest of the conditions t. hat occurree is order to determine if cor-rective action, such as replacing any affected equapsent, La warsaatad. 2a ccA m icAT2ex e m es 2. QUALIFICATION METHODS
~
2.1 Selection of Methods . - 2.1 (1) Qualification methods should confors to the requirements defined in IIII (1) Qualification methods will conform std. 323-1sn. to the requirements defined in IEEE-STD-323-1971 for equipment purchased (2) ne choice of the seasde selected prior to May 23, 1980. Equipment is largely a matter of technical judgment and availability of infor- t purchased prior to May 23,1980 re-nation that supports the cenclusions quiring re-evaluation will be quali-ru ched. taperience has shows that fied using analysis or analysis qualification er equipment subjected to . an accident envuor.sent without test __ supported by partial test data. Equip-rY1, ment purchased after May 23, 19c0 and Iunct on N r $111t e equipment which requires substantial the staff will not accept analysia 12
- Lieu of test dat.a unless (a) testing requalification will be qualified to of the cosponent is impractical due to (j) /
size limitations, and (b) partial type tess dau is provided to Category I unless otherwise justified. support the asa17tical assumptions (2) See 2.l(1), and conclusions reached. (3) ne environ. ental qualification of (3) Appropriate documentation addressing'this equipeent exposed to DBA environ- g gg
. sesta shoald conform to the fellowing positions. n e bases should be provided for the time interval reevired for operability ..
! et this equipment. D e operability l and f ailure enteria should be specified and the safety margins defined. , () Iquip=ent that =ust function (a) Operability of the equipnent for
# the time required in the environ-
" dtest
.c$ *' [ioult be I Utf f $ '
to demonstrate its operabi1* mental Conditions resulting from icy for the ti== required in the the accident is established b79 environmental conditions resulting i f ree that accide.at. test or by test with, analysis by g A rehenius . calculations. ; l (g) Any equip.ent (safety-related or (b) Any equipment that could fail in a ! se uiety-related) taat need **c manner detrimental to plant safety function in order to sitigate any is classified as safety-related. accrdent, but t. hat must not f*il 18
' a manner desnmental to plant safet7 Failure mode effects analysis will er tItu $pa be provided for all safety-related Ne ,*n 1t to via.
l ----: .tand any accident environ.ent for electrical equipment located in
= the time during which it =ust s't harsh environments that quali-l
) 1811- fication has not been established.
( , I l l
COMPARISON WITH NUREG 0588 REV. 1 A NUREG 0588 REQUIREMENTS CATEGORY II CG&E TECIC:ICAL POSITION (c) Equipinest that need not function
.. La order to sitigste any accident (c) Only Safety related (Class IE) and whose failure is any moda sa equipment is be!ng addressed.
any accident environment is met - , h detrimenul te plant safety need
-3 ealy be qualified for its son-accident service enviroamaat.
Although actual type testing is.
- preferred, other methods when justified may be feund acceptable.
The bases should be provided for concludict that such equipment is set required to functief in order ta mitigate any accident, and that its failure is say mode in any accident environment is not detri-mental to plant safety. , (4) ror =4viron=esul qualification of (4) Conditions resulting from LOCA and HELB equipment subject to events other thaa e DBA, which result in aboormal a. conditions have been calculated as noted environmental conditiona, actual type in sections 1.1 and 1.2. noncrmal en-tasting is preferred. Ioweve r. analysis or operating history, or
- vironments resulting from other events say applicable combio.atton thereof, are addressed in the normal ranges.
coupled with partial type test data may be found acceptable, subject to the applicability and detail of information provided. I 2.2 Qualifiestion by Test (1) The fatture criteria should be established 'l) Prior to testing. Acceptance Criteria are established for all current and future testing programs. ,For (2) Test resulta should demonstrate that tests that are completed without established the equipment can perform its required acceptance criteria, the tast results are petaINebwith ' ib its reviewed against the system design require-installed life. ments. (3) The items described in tection 5.2 of (2) IIEZ Std. 323-1971 supplemented by items Test results will deconstrate that the equip-(4) through (12) below constitute ment can perform its required function for acceptable ruidelines for establisting t.se procedures. all service conditions postulated during its installed life.
' (4), Wen establishing t.he simulated environcental profile for qualifying (3) The requirements of section 5.2 of IEEE-323-U [p cIr tha ib$e p* 1971 were used as guidelines in our review of be used that envelopes the environmental existing documentation. The requirements of c, editions resulta g from may design basis event during pay mode of plant . IEEE-323-1974 are being addressed in all '.
operation (e.g., a profile that current and future qualification programs, envelopes the conditions produced by the See items (4) through (12) below. main steamline break and loss-of-coolant
****d***
- 4) See Section 1.2(5).
(5) zquip. cat should be located above fleed le,el or protected assinat sub.ergence by locating the equapsent in qualifi (5) See Section 2.2 of the submittal, wetartight enclosures. Were equipment - Q .bli .
, . 8
COMPARISON WITH NUREG 0588 REV. 1 0 NUREG 0588 REQUIREMENTS CATEGORY'II CG&E TECHNIC /4 POSITION is located 1a Idt'rtight'eaclesures,
~
~
qualificaties by tast er analysis should
- be ased to demonstrate the adequacy of such protection. Where equipaest could
'be submerged, it should be identified sad demeestrated to be qualified by tast for the durstion required.
(6)" The temperature te which e @ pment is (6)
* 'd Thermocouples to be used for temperature M*d 9"' '
, ,,,, hould d es measurement. The preferred thermocouple by therseceuple reedisse ea er as close location is as close as practical but not as practical to m surface of m ca -
Ponent being qualifie4. in contact with the surface of the test
,g g ,, ,,,, article. If there were no thermocouples se thers couples leested near m located near the equipment during testing, equipment dueins
- tests, hast traufer analysis should he used the method used to determine temperature ta cetermine the tesperature at the will be justified.
component. (Arceptable heat transfer ag analysis methods are provided in Append 12 3.)
-(7) Performance characteristics of (7) Monitoring points are dependent on oper-equ1P = nt should be verified befers, af ter, and periodically during ational requirements (e.g. an item that t, sting threuthout its rante of is required to function only after an required operacility, event need not be monitored during the (s) canstic spray should be incorporated Wend . In general, performance charac-during simulated event testins ** t3e terisites of equipment to be monitored
.aximum pressure and at the t==perature conditions aat would occur when m before, periodically during and af ter casite spray systems actuate. testing throughout its range of required (s) The eperability ststus of equipment operability. In those cases where moni-should be o.aitored continuously during toring Vas not aCCCmplished during testing, testing. yer 1_ong-term testing, how- pggg ym g ggg ,
ever, monitbring at discrete intervals she u be justified if used. (8) See Sections 2.3 of the submittal. (to) zzpected extremes in power supply (9) See Section 2.2(7). voltage range and frequency aheald be applied during simulated event environ . masul testing. (10) E,xpected extre=es are being applied in all (11) Dust environments should be addressed future and testing currently in progress.
- when establishing qualification service Justification to be provided for extreues co attion.. , considered in previous tests that have been I (12) fehalt-60 is as acceptable samme radia- considered acceptable.
taoi source for' environmental
, q 11ficaties. (11) Dust will be considered when establishing equipment qualification on a case by case basis. Those types of equipment which could be adversely affected by dust will be reviewed and a preventative maintenance program established.
4 (12) Cobalt 60 is being used as a gamma radiation j source for environmental qualification. If f other radiation sources are used, they will be justified. i
.. l
-X
COMPARISON WITH NUREG 0588 REV. 1 /g h NUREG 0588 REQUIREMZNTS CATEGORY 11 CG&E TECHNICAL POSITION ' 2.3 yn t s""**" 2.3 TEST SEOUENCE: (1) Justificattom of the adequacy of the test s.quence selected saould b* (1) Justification to be provided for P "'id "
- sequence of equipment tested and (2) The te st should simulate as closely as Procured prior to May 23, 1980.
pr cticable the postulated environment. Current and future testing will be performed to the test sequence (3) ne test precedures should conform to the gutdelines destribed in Section 5 defined in IEEE 323-1974 or it will
. of IIII r,td. 323-1971. be justified.
(4) The staff considers that, for vital (2) Testing will simulate as closely as electrical equipment such as penetrations, possible the worst case environment connectors, cables, salves and motors, and transmitters located instde contattaent that the device is Postulated to ex-or erposed t3 hostile steam environmenta a- perience. outside containment, separate effects aNe q ic .SS. $ t$ts: . (3) Testing used to establish qualification of such equipment should be conaucted in _ _ _ __that was performed prior to May 23, 1980 a manner that subjects the sans piece of equipment to radiation and the hostile will conform to the guidelines of stera environment sequentially. Section 5 of IEEE 323-1971 or will be justified. All current and future
*4
. other cualificatten Methods testing will be performed to the same as category I (except eat IIII Category I requirements of NUREG Std. 323-1971 and ancilla:T standards 0588 and to IEEE 323-1974.
endorsed at the time the CP IIR was issued may be used). men i (4) Safety related electrical equipment Qualification by analysts or operating located inside primary containment experience tzplemented, u descrsbed in such as penetrations, cables, valve IIII Std. 3:J-1974 and other ancillary motors and connections have been standards, may be found acceptable. The tested sequentially. Zimmer does adequacy of these methods will be evalu-ated 4a the basis of the quality and detail not utilize transmitters inside of the information subastted in support of primary containment, the assumptions made and the specific func-thod ae o t suita e7er 2 men ere 2.4 'OTHER QUALIFICATION METHODS: testing is precluded by physical size of the equipment beins qualified. It is required Results from testing are used as the basis that, vben these neunds are esplayed, se . of qualification for all electrical devices partial type tests on vital ecaposenta of ue located in potentially harsh environments. equipment be provided in support of these me thods.
~
., Analysis is used to supplement testing in -
3- WNS i cases where qualification deficiencies are (1) Quantified maratna should be applied to minor in nature and can bejustified withanalysis. the design parameters discussed in 3 MARGINS: Section 1 to assare t.ha t tne postulated i sectdent condition have been e_ eloped (1) Margins consiatant with the guidelines ductas testing. These margins saould b* applied in addition to any margins (con- i g of IEEE 323-1974 are being applied to servatssa) applied during the derive- the accident conditions of current 6fut'ure
- tion of us spectried plant para ete.s.
( g) testing to insure that the conditions are enveloped during testing. For testing completed prior to May 23, 1980, margins are reviewed on a case by case basis.
. - - - ~ . - .
,,- COMPARISON WITH NUREG 0588 REV. 1 f.
b NUREG 0588 REQUIREMENTS CATEGORY II CG&E TECHNICAL POSITTON
~4. *
- idIN6 ' ' * .
- 4. AGING:
(1)* Qualification programs that are con *
' The Zir.mer Preventive Maintenance and f st 82 IN2 for '*"!v" Surveillance Program is currently being y operstor s) and *IEEE Std. 334-1971 (for prepared. This program will addIess motors) should consider the effects of sting. For this equipment, the manufacturer recommendations, results Category I positions of Section 4 of environmental qualification testing are applicable.
- and analysis,and operating experience.
(2) For other equipment,' the qualification All current and future testing programs programs should address aging only are addressing , aging as required per to the estent that equipment that 'i' IEEE 323-1974. The Equipment Qualification is composed, in part, of materials documentation will be revised as the pro-susceptible to aging effects should be identified, and a schedule for . gram is Complete. periodically replacing the equipment .-- --- - - - - - and/or materials should be established. During individual case revieve.
-. This program is consistent with the re-quirements of NRC Generic Letter 82-09 Nec f og b a c un e or and will be completed prior to fuel load.
en selected equipment if operating (v[) experience or testing indicates that the equipment may exhibit
, deleterious aging mechanisms. -
- 5. QUAEITIcArrow DOCUMENTATION
. 5. QUALIFICATION DOCUMENTATION:
(1) The staff endorses the requirements stated in IEEE Std. 323-1974 that, "The
. qualification documentation shall verify An Environmental Qualification Documentation that each type of electrical equips.nt Eile has been set up in the Nuclear Engin-is qualified for its application and eering Department per Nuclear Engineering meets its specified perfoamance Procedure NEP-3.8. This file contains
~requi r'emen t s . The basis of qualification documentation packages for all safety shall be erplained to show the reistion" sh ofg,all iacets of roof edcd t related electrical equipment located in
,, q ,, , th c p . eq p. harsh environments and supporting environ-ment. Data used to demonstrate the ment calculations. Mild environment and qualification of the equipment shall be
' ' ' mechanical equipment will be added upon
$as ne1 i a .3eblefors .the completion of the tasks. This file (2) The guide 11:es for documentation in .is available for NRC review. '.
IEEE Std. 223-1974 when fully imple-mented are acceptable. The documenta-tion abould include sufficient informa-tion to address the required information identified in Appendix E. A certificate of confer == ace by itself is not acceptable
, unless it is accompanied by test data and inforsation on the qualification program.
... s- -
"',g, , k .,4 .c N
~m-
- n. . .
COMPARISON WITil NUREC 3588 REV. 1 a . . . k . NUREG 0588 REQUIRDIENTS - CATEGORY II' ^- CC&E TECHNICAL POSITION
^
APPENDIX A 1 -+ APPENDIX A Methods for Calculating Mass and Energy Release. . See Section 1.1(2) APPENDIX- B ' APPENDIX B Model for Environmental Qualifigation for Loss-of-Coolant-Accident and -See-Section e 1.l(1) Main-Steam-Line-Break Insidh PWR and
- BWR Dry Type'of Containment, c .
'=~ APPENDIX C. . - APPENDIX C Qualification Profiles for BWR and Ice ' Condenser Containments. Plant specific environ:nental profiles are used. APPENDIX D APPENDIX D Sa=ple Calculation and Type Methodology for Radiation Qualification Dose. See Section 1.4 A, e a a
'W
.m
.s
,-w v
, .- , ~, - --- ,- -g. . - ..e. s - , , .,--.s. , ,m , -w , e,, .n-.. w-,,,
s. COMPARISON WITH NUREG 0588 REV. 1
' (_,) . '
I
~
-NUREG 0588-REQUIREMENTS CATEGORY II CG&E TECHNICAL POSITION APPENDYXE APPENDIX E Standard Question'on. Environmental
. Qualification of Class lE Equipment. '
, 1.. Identify all Class IE equipment, 1. Class IE equipment located in harsh and provide the following: environments has been identified in l_ a. -Type (functional designation) the Equipment Qualification Equipment i
.b. Manufacturer '-
List .(EQEL) as identified in -Section 3.1 f; . ., ,
.c. Manufacturar's type ""-b** "" of the submittal . The EQEL contains
~
~
r .model number '
-the component type, manufacturer, and d.. The equipment should include -
model number for all entries.
- - ~
~ ~ ~ - - ' '~
( the:following, gs applicable: (1) ,Switchgear
?T 3 (2) Motor control centers J. -(3) Valve operators (4). Motors (5) ~ Logic' equipment (6)- Cable
- (7) Diesel, generator control equipment (8) S'ensors'(pressure,
pressure differential,. '
temperature and neutron)
.(9): Limit switches <
(10) Heaters . (11) Fans
.(12) Control boards 1.
(13) Instrument racks'and panels
~(14)- Connectors (15) Electrical penetrations -
, (16) Splices.
'(17) Terminal blocks s-
)
h
.,, - -- .. _ .- ,, . , . . _ . . . _ . . . _ - . . . - . . _ . - . . _ - _ _ - - - . - . _ . _ _ . _ . . _ . . _ . - - _ _ . _ - ~ . .
COMPARISON WITH NUREG 0588 REV. 1 7] G' NUF2G 0588 REQUIREMENTS CATECORY II CG&E TECHNICAL POSITION _
- 2. Categorize the equipment identi- 2. Ihe equipment identified in Item 1 fled in Item 1 above into one of above was given a NUREG 0588 category _
the following categories: consistant with these categories and the addition of an exemption (EX)
- a. Equipment that will experi- category for equipment-that has been ence the environmental exempt from qualification.
conditions of design basis accidents for which it must function to mitigate said~ a:cidents, and that will be4 qualified _rn demonstrate operability in the accident environment for the time -- - - - - --- - -- required for accident mitiga-tion with safety margin to f- . failure.
- b. Equipment that will experi-ence environmental conditions of design basis accidents through which it must not fail in a manner detrimen:a1 to.
plant safety or accident mitagation, and that will be qualified 'to demonstrate the
, capability to withstand any accident environment for the time during which it must not fail with safety margin to failure.. -
- c. Equipment that will experi-ence' environmental conditions of design basis accidents '
through which it need not function for mitagation of said accidents, and whose failure (in any mode) is deemed not detrimental to
~
plant safety or accident mitigation, and need not be
^_
qualified for any accident (_3) environment, but will bc qualified for its non-accident service environment.
COMPARISON k'ITH NUREG 0588 REV.1 7 .
'w)
NUREG 0588 REQUIREMENTS CATEGORY II cctr TrenvTcv nngr7Tnu
- d. Equipment that will not experience environmental conditions of design basis
't accidents and that will be qualified to demonstrate operability under the expected extremes of its non-accident . service environment. This equipment would normally be located outside the reactor containment. 4
- 3. For each type,of equipment in the 1 Component Evaluation Data sheets in Appendix E categories of equipment listed in _. identify requirements a,b,6c for each applica-Item 2 above, provide separately _ tion of the equipment identified in item 1 above.
the equipment design specification requirements, including: Justification is provided in Exemption Data Sheets for all equipment that is labeled EX
- a. The system safety function in the 0588 Category. Failure mode effects requirements. analysis are included with these sheets to show that failure of the device will not
- b. An environmental envelope as a affect other required safety related equipment.
function of ti=e that includes These sheets are included as Appendix C. all extreme parameters, both maximum and minimum values, Justification for equipment classified as 2B expected.co occur during plant is not required since this designation was shucdown, normal operation, obtained from the various design documents abnor=al operation, and any used to generate the EQEL as noted in section design basis event (including 3.1 of this submittal. LOCA and MSLB), including post-event conditions.
- c. Time required to fulfill its
, safety function when subjected to any of the extremes of the ,
environmen,t envelope specified above.
- d. Technical' bases should be provided to justify the placement of each type equip-ment in the categories 2.b e and 2.c listed above.
f %. V COMPARISON WITH NUREG 0588 REV. 1
.%.)
t'] NUREG 0588 REQUIREMENTS CATEGORY II CC&E TECHNICAL POSITION 4 Provid the qualification test plan, 4. This information is available in the E.Q. test setup, test procedures, and Central File. acceptance criteria for at least , one of each group of equipment of Item 1.d as appropriate to the category identified in Item 2 above. If any method other than type test-ing was used for qualification (operatir.; experience, analysis, ~'
-ccmbined qualification, or ongoing qualification), describe the method in sufficient detail to permit evaluation of its adequacy.
fM{. For each category of equipment 5. This information is available on the Component i, ) identified in-Item 2 above, state Evaluation Data sheets in Appendix E of this the actual qualification envelope report. simulated during testing (defining the duration of the hostile environ-ment and the margin in excess of the design requirements).- If any method other than type testing was used for qualification, identify the method and define the equivalent
" qualification envelope" so derived.
-6. A summary of test results that 6. The Central File package includes all of demonstrates the adequacy of the the documentation required to demonstrate
. qualification program. If analysis qualification of those items considered is used for qualification, justifi- qualified.
cation of all analysis assumptions must be provided. - 9 L.)
COMPARISON WITH NUREG 0588 REV. 1 2:c
~
NUREG 0588 REQUIREMENTS CATEGORY 11 CG&E TECHNICAL POSITION
- 7. -Identification of the qualification 7. The Central File package is identified on documents which contain. detailed the bottom of each Component Evaluation
, supporting information, including Data Sheet in Appendix E of the submittal. 4 test data, for Items 4, 5 and~6. All Class lE equipment located in harsh In: addition, in accordance.with environments will be qualified or a the requirements of Appendix B of , Justification for Interim Operation for that 10 CFR 50, the staff requires a
~
item will be provided prior to fuel load, statement verifying that (1) all "
, Class 1E equipment has been -
1 . qualified for an~ operating license (OL) or will be qualified for a f
. construction permit-(CP) to the
~g program described above, and (2)
,_) the: detailed qualification infor-mation and test results are (or will be) available for an NRC audit.
^
4 - e
- . _ - - - - - ~ . _ - . - . _ _ . - - _ . .
6.0 RESULTS OF ENVIRONMENTAL QUALIFICATION REVIEW The environmental cualification review of all safety-related electrical equipment located in potentially " harsh" environments is complete.
-, Component Evaluation Data 9heets for each device are provided as
( Appendix E of this report. The status of qualification is summarized as follows: QUALIFIED 46% EXEMPT 5.5% RETEST 16% REPLACE 2 26% RELOCATE 5% ANALYSIS REQUIRED 0.5% UNDER REVIEW 1% Sections 6.1 - 6.7 identify the devices of each of the above categories. l2 Specific action plans for each device are provided in Appendix D. 6.1 00ALIFIED Review of the available qualification documentation has established qualification for the following equipment: ANACONDA LOW VOLTAGE POWER CABLE ANACONDA CONTROL CA8LE ASCO HVA 90-405 SOLENGID VALVES BOSTON WIRE INSTRUMENTATION CABLE CONAX CANNISTER PENETRATIONS CONAX KULKA TERMINAL BLOCKS (~3 G. E. LEAKAGE CONTROL HEATER (_ / G. E. SK ECCS MOTORS GORDON TEMPERATURE ELEMENTS KERITE MEDIUM VOLTAGE POWER CABLE KERITE SPLICE KIT LIMITORQUE VALVE ACTUATORS (MAJCRITY QUALIFIED; 2 ONE REPLACE) OKONITE LOW VOLTAGE POWER CABLE OKONITE CONTROL CABLE OKONITE SPLICE KIT RAYCHEM INSTRUMENT CABLE RAYCHEM SPLICE KIT ROBERTSHAW PRESSURE INDICATING SWITCH ROCKBESTOS CONTROL CABLE ROCKBESTOS INSTRUMENTATION CABLE ROSEMOUNT 1152 PRESSURE TRANSMITTERS SAMUEL MOORE INSTRUMENTATION CABLE TARGET ROCK SOLENGID VALVES - WESTINGHOUSE CLASS H MOTORS Qualification .has been established for these devices to the Zimmer parameters and require no further action with the exception of qualified conduit seals. Conduit seals to be added to Gordon Temperature Ele-ments, Rosemount 1152 Pressure Transmitters and Target Rock Solenoid 2 Valves. q ' I 6.2 EXEMPT As identified in section 3.1-7, all safety related electrical equipment. of the Standby Liquid Control, Process Radiation, Neutron Detection, Reactor and Turbine Building Ventilation Systems and some equipment of
- (*')- the Reactor Core Isolation Cooling System have been exempted from qualification. In addition, as noted in Section 3.1-8, several devices of other systems have also been exempted because they perform no safety functi'on to mitlaate a LOCA or HELB accident. Identification.and justification for exempting this equipment is provided in Appendix C of this. report. Included with the exemption data sheets is a failure mode effects analysis for each item that shows that failure in any mode will not affect other safety related equipment required to mitigate the
. postulated LOCA or HELB accidents. In several cases the FMEA is not included with this submittal but will be included in our Justification For Interim Operation Report. With the exception of these FMEA's, no
.further action is required for these items. +
6.3 RETEST CG&E has elected to retest the followinq equipment to ensure that it will perform its required safety function during the postulated conditions.
- - BARKSDALE PRESSURE SWITCH ,
BARTON PRESSURE SWIICH G.E. TERMINAL BLOCK MAGNETROL LEVEL SWITCH MARATHON TERMINAL BLOCK LICON LIMIT SWITCH 2 MAGLOCK LIMIT SWITCH O evCo SCHUTTE & K0ERTING reMetaarust eleMe~r FLOW ELEMENT & TRANSMITTER ITT GENERAL CONTROLS DAMPER ACTUATOR 6.4 REPLACE CG&E has determined that replacement of the following devices is the most effective way to establish qualification.- ALLISON 1052 TEMPERATURE ELEMENT AND TRANSMITTER ASCO SOLEN 0ID VALVES (PARTIAL) AIK0MATIC SOLENDID VALVES BAILEY 555 & 556 TRANSMITTERS BARTON 385 DIFFERENTIAL PRESSURE TRANSMITTER BARTON 760 TRANSMITTER SWITCH BUCHANAN TERMINAL BLOCK CROSBY SRV SOLEN 0 IDS ' DELPHI H 022 MONITOR 2 HA7S 252 PRESSURE TRANSMITTER LIMITOROUE VALVE ACTUATORS (MAJORITY QUALIFIED; ONE REPLACE) MERC0!D LEVEL & TERMPERATURE SWITCHES NAMCO LIMIT SWITCHES ROSEMOUNT 1151 TRANSMITTERS ROSEMOUNT TEMPERATURE ELEMENT SIEMENS l.EAKAGE CONTROL BLOWER MOTOR Q C STATIC-0-RING PRESSURE SWITCH WESTINGHOUSE CLASS F M0 TORS
6.5 ANALYSIS Additional Analysis is required to establish qualification for the
. following devices:
J! .: UNITED ELECIRIC TEMPERATURE SWITCH
-; Test data is ' available for these devices. -The Component Evaluation Data Sheets classify this equipment as " Conditionally Qualified". Analyses are required to address aging, operability duration, higher radiation requirements, pressure and traceability concerns.
'6.6 RELOCATE Due to levels of high radiation, the SGTS panels will be relocated to a less severe environment.
AGASTAT TIME DELAY RELAYS G.E. SB-1 CONTROL SWITCH G.E. 180 TEMPERATURE INDICATOR G.E. HFA RELAYS 2 G.E. HMA RELAYS LOVE CUREENT RELAY LOVE PROPORTIONAL CONTROLLER
- POWERS CONTROL CABINET MISC. COMPONENTS 6.7 UNDER REVIEW Several devices are currently under review to determine the status of qualification. These items include:
.() CTI INDEECO HYDROGEN RECOMBINER SGTS HEATER
'ITE GOULD MOTOR CONTROL CENTER 2
, ROSEMOUNT S35 MILIV0LT CONVERTER SPENCER HYDROGEN RECOMBINER BLOWER 4 e
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7.0 ON-GOING ACTIVITIES Activities are currently underway by CG&E to establish and maintain qualification and to justify interim operation. - Detailed Action Plans are. provided in Appendix D'to identify the action being taken to hs establish qualification for each device. 7.1 . TESTING CG&E has entered a testing program with Research Dynamics Incorporated (RDI) and the University of Cincinnati to perform qualification tests in accordance-with IEEE 323-1974 to the equipment requiring testing as identified in Section 6.3. CG&E plans to use this facility for the majority of current and future qualification programs. 2 CG&E continues to monitor other on-going test programs in the industry. Testing identified in Section 6.3 or Justification for Interim Operation will be completed prior to fuel load. 7.2 REPLACEMENT Engineering Change Request (ECR's) are being prepared to replace the equipment identified in Section 6.4 of this report. Procurement'of the qualified or qualifiable devices is underway. Replacements will be installed to the schedule identified in the Action Plans. Replacements will ha comnleted nr lust i fient i nn for interim Oppretion will be provided prior to fuel load. Every' effort is being made to install fully qualified equipment prior to fuel load which is scheduled for February 1986. p 7.3 ELECTRICAL CONDUIT SEALING b CG&E is currently performing an evaluation of all safety related equipment at the Zimmer Station to determine if electrical conduit 2 sealing is required. Qualified electrical conduit seals will be installed on equipment where this evaluation determines conduit sealing is needed. This program will be completed prior to fuel load. 7.4 ANALYSIS l2 CG&E is currently performinq material analysis in cases where analysis can be used to justify minor qualification deficiencies. This analysis and all other justifications for outstanding items are part of the documentation packages in the Central File. 7.5 JUSTIFICATION FOR INTERIM GPERATION l2
- CG&E has completed a preliminary report covering the Justification foe .
Interim Operation (JIO) of the Zimmer Station with the current level of qualification. . The draft report was provided to the NRC reviewers in September,1982 for comments. The report will be revised based on NRC comments and qualification activities completed between September 1982 and fuel load. O
=
7.6 MAINTENANCE AND SilRVEILLANCE l2 A maintenance and surveillance program is .being prepared for all safety related equipment at.the Zimmer Station. As noted in Section 4 of the Comparison with NtJREG 0588, the preventative maintenance will address V the . manufacturer's ' recommendations, .results of erw ironmental qualification testing and analysis, technical. specifications, as well as operating ~ experience. This program will be completed prior to fuel load. ( d 1. l LO z 4 4 I e 4 e 4 i;
,. _ . . . - ,-, . . . - - . . - . . ~ - , , - - , - , . - - , - , , - - - - - , , , - - - - - - , - - - - - - - , , - - - - - - - - - -
8.0 RESPONSE TO SAFETY EVALUATION REPORT CONCERNS CG&E's response to the SER items identified in the response schedule are as follows: 8.1 SER SECTION 3.11.3.lc R.G. 1.97 EQUIPMENT [v') Category 1 and 2 equipment-required per Reg. Caide 1.o . located in harsh environments has beea -identified in Appendix G of this report. Additional information pertaining to this subject is contained in section 3.4. 8.2 SER SECTION 3.11.3.1 NUREG 0737 EQUIPMENT All essential electrical equipment, located in harsh environments has been identified in Appendix H of this report. Additional information pertaining to this subject is contained in section 3.4. 8.3 SER SECTION 3.11.3.1 MECHANICAL EQUIPMENT As noted in section 1, an Environmental Qualification Report for Mechanical Equipment has been prepared. Volume 1 of the Mechanical Report covers the information requested and is being submitted with this report. 8.4 SER SECTION 3.11.3.3.3 SUBMERGENCE IN DRYWELL Information regarding this topic can be found in section 2.2.1 of this report. 7 8.5 SER SECTIGN 3.11.3.4 CONDUIT SEALS
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In fo rmat ion regarding the program, which is currently under way, 2 regarding conduit seals may be found in section 7.3 of this report. 8.6 SER SECTION 3.11.3.4 CHECKLISTS Checklists are being incorporated into the qualification packaaes for all qualified equipment in the Central File. Checklists will be incorporated into the qualification packages as the equipment is qualified. A copy of the checklist is attached as figure 8.1. 8.7 SER SECTION 3.11.3.5 SOLID STATE EQUIPMENT Information regarding the qualification of solid state equipment may be found in section 2.1.4 of tais report. Data sheets, Action Plans and Document References have been prepared and are included as Appendix 1. 8.8 SER SECTION 3.11.4.1 UPDATE OF ELECTRICAL EQUIP"ENT 2CTION PLANS The Electrical ~ Equipment Action Plans found in Appendix D of this raport have been updated to reflect the changes in qualification status of equipment between January 1983 and December 1983. r3 O
-- s WM. H. ZIMMER NUCLEAR POWER STATION - UNIT 1 -(^/ ENVIRONMENIAL' QUALIFICATION REPORT EVALUATION FORM FOR NRC NUREG 05E8 CATEGORY II POSITION
- 1) Equipment Manufacturer:
- 2) Equipment Model No:
- 3) Equipment Tag Numbers-See Tab II YES NO N/A COMMENT
- 4) '- Is the report traceable to the plant .I I i 1 equipment? (Identified in tab II) l l l l l l l 1 5)
Did the report specify an acceptance -l _ l l l criteria for equipment performance? l l l l ' l l l l
- 6) Was a base line test done to establish I l l l the reference basis? l l l l l 1 1 -l
- 7) Did the maximum and/or accident temper- l l l l ature and pressure used in the test envelopel l l I those for _the plant zones? l l l l l l l l
_' i - 8)
, Were thermal agin'g parameters chosen and l l l l J used in the tests supported by adequate l l l l documentation or references? l l l l l l l- l
- 9) Was radiation aging addressed? (Test or l l l l analysis. If analysis, was adequate doc- l l l l umentation provided?) l l l l l l- l l
- 10) Did the -radiation dose profile, i.e., integ-l l l l rated dose for normal operations and acci- l l l 1 dent for the plant, fall within the envelopel l l l used in ' qualifications? I l l l
~
l l l l
' 11) Was mechanical and/or-electrical cycling l l l l addressed? l l l l l l l l
- 12) Were effects of Relative Humidity l l l l considered? l l l l .
l I I i
- 13) Did the DBA qualification include chemical l l l I spray? l l l l l l l 1
- 14) Were the margins used in test parameters l l l l 1 defined? l l l l Figure 8.1 .
_ . - _ . _ , ___. ~ ___ . _ _ - - - _ - ._ - _ . - - - , -
y 11 EVALUATION FORM
=(
^l FOR NRC NUREG 0588 CATEGORY JI POSITIONS Page 2 of 3 YES NO N/A CO>DIENT
'15); Did.the margins conform to those required l I l l by'IEEE-323-74 and any applicable daughter l I l l standsids for this equipment? l l l l l l 1 1
- 16) _ Did the specification provide the required l l l l operating time for the ~ equipment in the l l l
'DBA or other specificed harsh environment?-l _ l l l 1 l l l l
- 17) Did the test operating time under the harsh'l. l l- l environment ~ equal or exceed that in the equip- l l l
, ment specification? l l l l I l- 1 I
- 18) . Were the effects of Submergance addressed? l l l l-l l l l
- 19) Was the accuracy demonstrated during testing l l .l l 7
equal to or better.than that specified? ,l l l l l ~l I i
- 20) Were the mounting and installation interfaces l l l used in the test configuration similar to l l l l those used in-the plant?' l l l l' l -l l I h 21) Was the test measuring' equipment-(TME) l -l ! l calibration addressed in the report?
l 1 l l l l l 1
- 22) Did it specify that the calibration of the l l l l
.THE is traceable to NBS or other' secondary l l l. I standards?. l l l l l 1 l l 23)' Was'the same test specimen subject to l l l l the entire test. sequence? I l l l (Including aging tests? - NUREG 0588) 1 1 I I l l l l
- 24) Was the qualified ' life (QL) explicity stated? l l l 1 l l l
- 25) Did the aging tests / analysis results support l l l l the Qualified-Life conclusion and is l l l l adequate documentation provided to support l l l l this conclusion? l l ! l ~
l l l l
- 26) 'Were there any major discrepancies between l l l l baseline tests versus those during the l l l l various tests? ~ l l l l l l l l l l l l
- 27) If so, was it satisfactorily explained in l l l l in the report? l l l l Iigure 8.1
-t i.
EVALUATION. FORM FOR NRC NUREG 0588 CATEGORY II POSITIONS Page 3 of 3
.28) The Maintenance Requirements / Intervals:
i.
- 29) 'The-Replacement Requirements / Intervals: '
- 30) Additional Comments / Recommendations:
+ r w~- D q_ ',fPrepared by: Date:
~
Resiewed by: Date: Approved by: Date: 4 i t 5 l () Figure 8.1
4 ' - - s, 4 't : t to i
- SARGENT & LUNDY EN G1N EE RS CHICAGO s A51-9 Revision 4 May 12, 1983 Page i WM. H. ZIMMER NUCLEAR POWER STATION - UNIT 1 THE CINCINNATI GAS & ELECTRIC COMPANY A51-9 DESIGN CRITERIA FOR ENVIRONMENTAL DESIGN CONDITIONS FOR STATION EQUIPMENT O
Nuclear Safety Related e f .
._, - , - . ~ _ _ _ _ _ . . . _
O O 0p v . d . THE CINCINNATI GAS & ELECTRIC COMPANY ' WM. H. ZIMMER NUCLEAR POWER STATION - UNIT 1 PROJECT NUMBER 4130-00 A51-9
- DESIGN CRITERIA FCR ENVIRONMENTAL DESIGN CONDITIONS FOR STATION EQUIPMENT ISSUE
SUMMARY
Revision Reason For Prepared Number Date Reviewed Approved $ Issue By By By m$
- 1 Oct. 12, 1981 tions "td .
b All Pages Nov. 17, 1981 u$ tions 3 3 8 I Corrected Error and ( Pages 1,11,1,7; March 24, 1982 Updated Calculation _hky b SalspAl# ,y'gYj /
*aE .
, Attachment Pages 7 8 " " g 4 and 60 only ' Reinstated PSAR < All Paces _May 12, 1983 r fo Z ts _ Nb fuu r i d h.
- Cl & C2, added iN l/
Zone A-7B and corrected Figures,
'2 ( 4_
i l yb p. e.
*h
*' ' SARGENT & LUNDY cuoturcas CMtCAGO A51-9 q Revision 4 V May 12, 1983 TABLE OF CONTENTS Page 1.0- SCOPE 5
2.0 REFERENCES
5 3.0 DEFINITIONS 5 4.0 DESIGN REQUIREMENTS - FOR PURCHASE OF INITIAL EQUIPMENT 6 5.0 DESIGN REQUIREMENT - FOR PURCHASE OF NEW CLASS lE, 7 SAFETY-RELATED EQUIPMENT AND RETESTING OF EQUIPMEh"I 6.0 QUALIFICATION REQUIREMENTS 7 ENVIRONMENTAL ZONE
SUMMARY
TABLE (REV. 4) I h Zone A-1 1 4
~
Zone A-2 1 Zone A-3 1 Zone A-4 2 Zone A-5 2 Zone A-6 3 Zone A-7 4 Zone C-1 5 l4 Zone C-2 5 Zone D-1 5 Zone R-1 6 l4 Zone R-2 6 Zone R-3 7 Zone R-4 7 Zone R-5 9 Zone R-6 10
-r Zone R-7 11 l4
, Page 1 of 7
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v v e s SARGENT & LUNDY
.- EN GIN E ERS a
cuicano A51-9 Revision 4 Q's L May 12, 1983 TABLE OF CONTENTS (Cont' d) Pace Zone R-8 11 Zone S 11 Zone T-1 12 Figure 1 - Plan El. 546'-0" 13 Figure 2 - Plan El. 521'-0", 525'-7", 527'-0" & 536' 14 Figure 3 - Plan El. 510'-6a 15 Figure 4 - Plan El. 496'-0" & 503'-6" 16 Figure 5 Plan El. 473'-5" & 475'-6" 17 Figure 6 - Plan.El. 570'-6" & El. 567'-5" 18 Figure 7 - Plan El, 593'-6" 19 Figure 8 - Plan El. 627'-9" 20 Figure 9 - Zones S-1 & S-2 21 Figure 10 - Auxiliary Building Zones A3C and A3D '22 Summer Temperature Transient Figure 11 - Auxiliary Building Zones A3C and A3D 23 Winter Temperature Transient Figure 12 - Augiliary Building Zone ASA Summer 24 j Temperature Transient Figure 13 - Auxiliary Building Zone ASA Winter 25 Temperature Transient Figure 14 - Auxiliary Building Zone A5B Summer 26 Temperature Transient Figure 15 - Auxiliary Building Zone ASB Winter 27 Temperature Transient Figure 16 - Auxiliary Building Zone A6A Summer 28 Temperature Transient () Figure 17 - Auxiliary Building Zone A6A Winter Temperature Transient 29 4 Page 2 of 7 L _ _-.- . __ ._- __ _ - - - _ __
4 e s SARGENT & LUNDY E N GIN E E RS
- a. c.acaso A51-9
^
t' \ Revision 4
\/ May 12, 1983 TABLE OF CONTENTS (Cont'd)
Page Figure 18 - Auxiliary Building Zone A6B Summer 30 Temperature Transient Figure 19 - Auxiliary Building Zone A6B Winter 31 Temperature Transient Figure 20 - Auxiliary Building Zone A6C Summer 32 Temperature Transient Figure 21 - Auxiliary Building Zone A6C Winter 33 Temperature Transient Figure ~22 - Auxiliary Building Zone A6D Summer 34 Temperature Transient Figure 23 - Auxiliary Building Zone A6D Winter 35 Temperature Transient Figare 24 - Auxiliary Building Zone A7A & A7B 36 (,,) Summer Temperature Transient Fig 0re 25 - Auxiliary Building Zone A7A & A7B 37 Winter Temperature Transient Figure 26 - Pressure / Temperature Response for 38 High Energy Line Break (HELB) in Horizontal (Auxiliary Building) Main Steam Tunnel Figure 27 Pressure / Temperature Response for 39 High Energy Line Break (HELB) in Vertical (Reactor Building) Main Steam Tunnel Figure 28 - Primary Contairtment Zones C1 and C2 40 Temperature Response Figure 29 - Primary Containment Zones C1 and C2 41 Pressure Response l Figure 30 - Reactor Building Zones Rl-R7 Summer 42 ! Temperature Transient 4' Figure 31 - Reactor Building Zones Rl-R7 Winter 43 l Temperature Transient. O
- Page 3 of 7 l
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' o SARGENT & LUNDY E N GIN E E R S cmenco A51-9
(). Revision 4 May 12, 1983 TABLE OF CONTENTS (Cont'd) Page Figure 32 - Reactor Building Zones Rl-R7 Summer 44 Humidity Transient Figure 33 - Reactor Building Zones Rl-R7 Winter 45 Humidity Transient Figure 34 - Reactor Building Zone R-1, HELB 46 Temperature Transient Figure 35 - Reactor Building Zone R1, HELB 47 Pressure Transient Figure 36 - Reactor Building Zone R4, HELB 48 Temperature Transient Figure 37 - Reactor Building Zone R4, HELB 49 Pressure Transient Figure 38 - Reactor Building Zone R5, HELB 50 Temperature Transient Figure 39 - Reactor Building Zone RS, HELB 51 Pressure Transient Figure 40 - Reactor Building Zones R6 and R7, 52 HELB Temperature Transient Figure 41 - Reactor Building Zones R6 and R7, 53 HELB Pressure Transient Figure 42 - Main Steam Tunnel Zone T-1, Summer 54 Temperature Transient Figure 4 3 - Main Steam Tunnel Zone T-1, Winter 55 Temperature Transient Figure 44 - Main Steam Tunnel Zone T-1, Summer 56 Relative Humidity Transient Figure 45 - Main Steam Tunnel Zone T-1, Winter 57 [ Relative Humidity Transient i LIST OF REFERENCES 58-61 4 l l ( ). l Page 4 of 7 b - * - - , . , , - - - , , . . , _ , , . . %_. , ,_ , ,, , ,,_ ,_,,,,, , _, , , , _ , _ , , _ _ _ _ _ _
v .- SARGENT & LUNDY ! E N GIN E E R S
.. ca.caso Rev. 4 May 12, 1983
(} WM. H. ZIMMER NUCLEAR POWER STATION - UNIT 1 ~ DESIGN CRITERIA FOR ENVIRONMENT DESIGN CONDITIONS FOR STATION EQUIPMENT A51-9 1.0 SCOPE This design criteria specifies the environmental design conditions for station equipment and the qualification requirements for safety-related equipment.
2.0 REFERENCES
- a. U. S. Nuclear Regulatory Commission, " Clarification of TMI Action Plan Requirements," NUREG-0737, November 1980, section IT.R.2.
- b. U. S Nuclear Regulatory Commission, " Interim Staff Position on Environmental Qaalification of Safety-O- Related Electrical Equipment," NUREG-0588, December 1979.
- c. U. S. Nuclear Regulatory Commission, " Control of Com-bustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," Regulatory Guide 1.7, Revision 2, November 1978.
- d. Wm. H. Zimmer Nuclear Power Station, Unit 1 - Final Safety Analysis Report, Docket No. 50-358, ZPS-FSAR.
3.0 DEFINITIONS
- a. Class 1E The safety classification of the electrical equipment and systems-that are essential to emergency reactor shutdown, containment and reactor heat removal, or are otherwise essential in preventing significant release of radioactive material to the environment.
- b. Normal Operating Ambient Conditions Plant environmental conditions during reactor startup, operation at power, normal hot standby, and cooldown to cold-shutdown conditions.
- c. Abnormal Operating Ambient Conditions
. Plant environmental conditions during loss-of-coolant i accident, high-energy line break or loss of offsite power.
Page 5 of 7
SARGENT & LUNDY A51-9 E N GIN E ER S e CH3CAGO Rev. 4 ( 3 .' May 12, 1983
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4.0 DESIGN REQUIREMENTS - FOR PURCHASE OF INITIAL EQUIPMENT i 4.1 Normal Operating Ambient Conditions All equipment shall be designed to operate under the following normal conditions: 4.1.1 Inside Primary Containment Temperatura (*F) 150 Pressure (psig) -0.5 to 2.0 Relative Humidity (%) 20 - 90 Atmosphere 95% N2, 5% O2 Duration Continuous 4.1.2 Outside Primary Containment Equipment Except valves (l) Valves Temperature (*F) 40-104 40-122 Pressure (W.G.) -1.0" to
+0.25" (same)
Relative Humidity (%) 20-90 (sanie ) Atmosphere Air (same) (~#) Duration Continuous (same) (1) Selected equipment shall be designed for a temperature range of 40-122*F as determined during detail design. 4.2 Abnormal Operating Ambient Conditions All safety-related equipment shall be designed to operate under tne following accident and post-accident conditions: 4.2.1 Inside Primary Containment Temperature (*F) 340 320 250 200 Pressure (psig) 45 Nax. 45 Max. 25 Max. 20 Max. Relative Humidity (%) 100 100 100 100 Atmosphere Steam Steam Steam Steam Duration First 3 Next 3 Next 18 Next 99 Hrs. Hrs. Hrs. Days 4.2.2 Outside Primary Containment Temperature (*F) 150 Pressure (W.G.) 7" Max. Relative-Humidity (%) 100 s Atmosphere Air (_) Duration 100 Days Page 6 of 7
l
?' SARGENT & LUNDY ' :' . cuoisccas c"***
A51-9 pey. 4 May 12, 1983 . l l I 5.0 DESIGN REQUIREMENT - FOR PURCIIASE OF NEW CLASS lE, SAFETY-RELATED EQUIPMENT AND RETESTING OF EQUIPMENT i (Based on NUREG-0588 of December 1979) See attached " Environmental Zone Summary Table (Rev. 4)," 4 pages 1 through 60, dated March 24, 1982, for pressure temperature, humidity and radiation values to be used for purchase of new Class lE equipment or retesting of equip-ment. 6.0 QUALIFICATION REQUIREMENTS All safety-related equipment shall have a certified factory test report to verify that the equipment (or prototype equipment) has been tested operationally under environmental conditions-equivalent to those specified under 4.0 or 5.0. 4 These tests must show that the equipment will meet satis-factorily all operational requirements under these condi-tions and for.the time periods specified. O f I l i [ L i O a ' l I Page 7 of 7
_ , ~ - - - 1 GENT &l. UNDY ""==' =b" ta" (""- u E't~f D 's , Fro pct 4. 6020 4 b ' *.'*" CNGINE T AS Pu n 1 of 61 Calculated integrated Calculated Maximum Exposure Radia tion - Environ.l Environ. Extreme Relative No rma l ** Accident ** lotal** Exposure for mental mental Temperature ** Humidity ** 99 Maxinum 40 years one year (rad) Testing *** ' Zone t Area Conditions ('F) Reference9 , (7.) Reference Pressure ** Referenceit (a) (b) in + b) (rad) Reference tt Normal 60-304 VC-01 10-00 W-A M - D - i DC-A51-15-l A.1 Control Room 0.1 to 1.5 x lu 9 4.73xIOh 8.23 x IQ'r 1.0 x 103# Zl-EQ-Al (el. 516'-0") +0.21 in W (FiEure 1) LOCA NC VC-01 NC DC-A51-15-7 NC DC-A51-15-7 NC NC NC NC Zl-EQ-Al NA No HEL NA No HEL N/. No HEL NC NC NC NC Zl-EQ-Al HELS Essential & Essential NC NC NC NC Zl-EQ-Al 1,00P NA Essential NA ~ HVAC liVAC HVAC A-2 Switchgear N "" 60-104 7X-01,VX-02 5 40 DC-A51-15-3 p , 1 3.5 x lo's k.18 x loi 4.53 x 105) 1.0 x 10'# Z1-EQ-A2 Poom VX-01, VX-02 DC-A51-15-3 NC NC NC NC NC NC Z1-EQ-A2 (el. 516'-0") LOCA NC NC (Figure 1) HELS NA No IIEL NA No HEL El. No HEL NC NC NC NC Zl-EQ-A2 Loop NA c asential NA Essential N# Fasential NC NC NC NC Zl-EQ-A2 HVAC INAC llVAC A-3A Electrical Normal 60-104 VX-01,VX-02 5-40 DC-A51-15-3 Approx. No Pressure 3.5 x 10] 7 15 x 103.. 7,1$xlo;E 1.0 x 10' # Zl-EQ A3A Equipment an3 Atacspheric Lontrol Switchgear LOCA NC VX-01,VX-02 NC DC-A51-15 3 N: NC NC NC NC NC Zl-EG-A3A Poems HEL8 NA No HEL NA No HEL N% No HEL NC NC NC NC Zl-EQ-A3A F e LOOP NA Essential NA Essential Et Essential NC NC NC NC Zl-EQ-A3A HVAC INAC HVAC. A-3 A-3B Cable Normal 60-104 IX-C1,VX-02 5 40 DC-A51-15-3 Approx. No Pressure 3.5 x 194 5.89 x 10h 9 39 x ICg 1.0 x 10 g Zl-EQ-A3B Spreadir.g Room Atmcapherii Control (el. 536'-0") LOCA NC VX-01,VX-02 NC DC-A51-15-3 NJ NC NC NC NC NC Zl-EQ-A3B (Figure 2) HELB NA No HEL hA Na HEL NL No HEL NC NC NC NC Zl-EQ-A3B toop NA Essential NA Essential KL Essential hC NC NC NC Zl-EQ-A3P INAC a HVAC HVAC HELB - High energy !!ne break
- Subsonal designation for this area in the referenced calculation.
LOCA - Lcss of coolant accident (in containment) ** No eargins other than conservatisms in calculations have been added to the pressure, LOOP = Loss of of f site power temperature, htai11ty va"ues and radia'.lon dases above. NA - Not applicable *** Appropriate margins are included in the recomrnended radiation exposures for testing. NC - No chtnge from normal values # This ose bounds att environ ental conditions. Normal - Normal cperating conditions t Environmental zones are defined in Fie;ures 1 through 9 on pages 13 through 21. tt See pages 58 through 61 for a list of references.
GENT &LUNDY
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- Projrct No. 6020-16 T N GIN E; RS. Page: 2 of 61 -
Radiation, kec wended Calculate d Maximum Calculated Integrated Environ. ' Environ. Extreme Exposure Radiation-Relative he rmal ** Accident ** Iotal** Exposure for mental mental Tempe ra tu re ** Area Conditions 99 Humidity ** 99 Mas te am 40 years one year (rad) Testieg*** Zone t (*F) Re ference (%) Reference Pressare** Referenceit (a) (LA (a + b) (r d) Reference tt
====
l A-3 A-30 Electrical 65-104 DC-A51-15-6 5-60 rC-A51-15-6 -0.2 ) in b DC-A51-15-6 3 5 x loi 5.79 x # 5. 83x10# 1.0 x 10)# 21-EQ-A3C
' (Cont'd) Fquipment and Switchgear . LOCA 48-112 3C6-0481-004 5-68 IC6-0481-004 16.9 psia 3C6-04 F1'-004 NC NC NC 30 Z1-EQ-A3C Rooms (A3C)* (A3C)* (A3C)*
(el. 525 '-7") (Figure 2) HELB 150 1C6-1173-001 100 3C6-1173-001 15.5 psia 1h-1173-001 NC NC NC NC Z1-EQ-A30 (Figures 10, 11 (Node 7) (Node 7) (Node 7) and 26)* LOOP 48-112 3C6-0481-004 5-68 16'.9 psia (Figure 26;E 3C6-0481-004 3C6-0481-004 (A3C)* (A3C)* (A3C)*
"* "* I A-3D Electrical 65-104 DC-A59-15-6 5-60 DC-A59-15-6 -0.2'. in DC-A51-15-6 3 5 x 10 # 7.15 x 10 3, 7.5 x 10 3g 1.0x10% Z1-EQ-A3A Equipment and W Switchgear (A3A)*
LOCA 48-112 3C6-0481-004 5-68 3C6-0481-004 16.9 psia 3C6-0481-004 NC NC NC NC Z1-EQ-A3A Pooms (A3D)* (A 3D ) * (A3D)* (A3A)* (el. 525'-7") Ht.La 150 3c6-1173-001 100 * * "U " El'EQ~^3^ (Figure 2) 3C6-1173-001 15.5 psia 3C6-1173-001 (Figures 10, 11 (Node 7) (Node 7) (Node 7) (A3A)* and 26)* LOOP 48-112 3C6-0481-004 5-68 3C6-0481-004 16.9 psia 3C6-0481-004 NC NC NC NC Z1-EQ-A3A (Figure 26)E , (A3D)* (A3D)* (A3D)* (A3A)* A-4 "*** No Pressure Electrical 60-10k VX-01,VX-02 5-40 DC-A51-15-3 APPrcx. 3.5 x 102 # 2.kl x 10% 2.76x104 1.0 x 109 Z1-EQ-A4 Equipment and 4tmospherie Control Switchgear LOCA NC VX-01,VX-02 NC DC-A51-15-3 NC NC NC NC NC NC Zl-EQ-A4 Pooms (el. 510'-6") HEL8 M No No NA No M NC NC E E Z1-EQ-A4 ) (Figure 3) NA Essential NA Essential NA Essential NC NC NC NC Z1 EQ-A4 HVAC INAC INAC A-5 A-5A Normal 65-104 DC-A51-15-6 5-60 DC-A51-15-6 -0.2F in DC-A51-15-6 5 25 x 103i 5.89 x 105 5.84 x 104 1.0 x 104 # HVAC Equipment Z1-EQ-A5A
' W Poom 59-113 40 16.9 psia LOCA 3C6-0481-004 NC NC NC NC Z1-EQ-A5A
-_ (el. L% '-0") 3(5-Ql-001 A5)* 3(06-0481-004 A5)* ' (A5)*
(Figure 4) (Figures 12, HELB 150 3C6-1173-001 100 306-1173-001 16.5 psia 3M-1173-001 NC NC NC NC Zl-EQ-A5A 13,26)e (Node 9)* (sode 9)* for 7 see. (Node 9)* (Figure 26)' $9-113 LO 3C6-OL81-004 16.9 psia 3C6-0481-004 NC NC NC NC 3(C6-OL81-00L A5)* Z1-EQ-A5A (A5)* HELS - High energy line break
- Subsona L designation for this area in tte referenced calculation.
LOCA - Loss of coolant accident (in containment) ** No margins other than conservatisms in calculations have been added to the pressure, LOOP - Loss of offsite power temperature, hum 1Sity values and radiat:.on doses above. e- Temperature history curves NA - Not applicable m. Pressure history.curres NC - No change from normal values *** Appropriate margins are inq1pded in the recomended radiation exposures for testing. Normal - Norul operating conditions # This dose bounds all envir inn ental conditions. t Environmental rores are cefined in Figures 1 through 9 on pages 13 through 21. t t See pages SS thrcugh 61 for a list of references, i
ENVIRONMENTAL FONE AY TABLE (DEV. b) p ( Proj;ct No. 6020 1 C NGINE7 ASm Page: 3 e f 61 a at n eceu d Calculated Maximum Calculated Integrated Exposure Radtstion Environ Environ = Extreme Metative Nosmal ' AcIJeat" local ** Exposure for mental mental temperature ** Humidity ** Maximam 40 years one year (red) Testing *** 99 99 99 Zon* t Area Conditions (*F) Reference (7.) Re f erence Pres s are** Re ferenc eit (a) (b) (n + b) (rad) Reference A-5 A-5B labs "'**I 104 DC-A51-15-15 40-50 DC-A51-15-15 .o.12do- aC-A51-15-15 5.25 x 10% 5.89 x 104 5.84 x los 1.o x 10d rgg5A (Cont'd) (el,k96*-0"3 .O.7 :n WO * (Figuae 4) LOCA 60-116 3C6-0481-00k LO 3C6-0481-004 16.y psia 306-0A81 004 NC NC NO TC Z (A12)* (A12)* (Al2)* {-p5A Figures Ib,15' HEL3 150 306-1173-001 100 3C6-1173-001 16.5 1sia 3C6-1173-001 NC NC NC NC Z1-EQ-ASA for 7 see. (Node 9)* IA5AI* (Node 9)* (Node 9)e Ifigure 26)8 LOOP 60-116 3M-Oh81-00k k0 3M -0481-004 16.9 psla 3C6-OL81-004 NC NC NC NC Z1-EQ A5A (A12)* (A12)* (A12)# , (A5A)* A-6 "* I 2 A-6A 6$-104 !C-A51-15-6 5-60 DC-A51-15-6 -0.24 in DC-A51-15-6 8.75 x 10 # 5.89 x 109 1.61 x 10 2 1.0 x 10 9 3 21-EQ-A6A Off-gas Equip- WG ment Areas LOCA 39-118 40 16.9 psia NC NC NC NC Z1-EQ-A6A (el. k73'-5') 3(C6-OL81-00h A6)* 3(06-0481-004 A6)* 3C6-0)481-004 (AO (Figure $1 , 150 3M -1173-001 100' 3 5 -1173-001 16.5 psia 3M -1173-001 NC NC NC NC Z1-EQ-A6A f F " 8'C-(Figure 16, (Node 9) t t t (Node 9)ttt (Mode 9) 999 17, 26)* LOOP 59-118 32 81 W L 40 3 81-004 16.9 psia 3 81-004 NC NC NC NC Z1-EQ-A6A (Figure 26) Normal A-( c 65 104 DC-A51-1$-( 5-60 DC-A 51- 15-6 -0.0 ) to DC-A51-15-6 4.W x loM 5.89x13 4.W x 104 1.0 x 10Y Z1-EQ-A6B Charcoal Bed -0.5 in WG P LOCA 60-118 40 p61-@ 16.9 psia NC NC 3C-g81-00L 3 3g81-OOL NC NC Z1-EQ-A6B (Figure 5) ggL, W #-1HW E %WM M.5 psia M-MM NC NC NC NC n-M-AQ (Figures 18, (Node 9)ttt # 7 8'C' (Node 9) t t i (Node 9)ttt 19,26 ys 60-118 81-00h
, 3 LO 3 g81-004 16.9 usia 3 81-00L NC NC NC NC Z1-EQ-A6B (Figure 26)
A-6C Normal 65-104 DC-A51-15-6 5-60 DC-A51-15-6 2
-0.25 to DC-A51-15-6 JA8.75xlO ' CA5.8WC10( CA1.45x10$ gl-EQ-A6C FASAS Poom -0.5 :n WG MAS.75x10 GAA6.57x10 MA7.75x10' SA1.0x10 GAA-1.0x1 [#
(el. 473'-5"). LOCA 60-137 3C6-OL81-00L 40 16.9 psia (Figure 5) 3M-0481-004 305-OL81-00L NC NC NC NC Z1-EQ-A6C (A6)* (AS)* (A8)* (Figures 20, gggg 150 3 b l173-001 100 3C6-1173-001 16.5 psia 3C6-117 NC NC NC NC Zl-EQ-A6C 21,26)* (Node 9) (Node 9) ttt for 7 see. (Node 9)3-001ttt tti (Figure Or,) LOOP 60-137 36-0481-OOL 40 306-0481-004 16.9 psia 3M-0481-00L NC Ir NC NC Z1-EQ-A6C a (A8)* (A8)* (A8)* HLL8 - High energy line break
- Subsonal designation for this area in tie referenced calculat1Cn.
LOCA - Loss of coolant accident (14ccntainment) ** No eargins ottier than conservatisms in calculations have been added to the pressure, 4- Temperature histe,ry curves LOOP = Loss of offsite power temperature, humidity values and radiati >n doses above, NA a- Pressure history purves
- Not app!! cable NC - No change from normal values
*** Appropriate margins are included in the recommended radiation exposures for testiqg.
# This dose bounds all environmental cond;tions.
Normal - Narul oyrating conditions t Environmental zones are def.ned in Fig 2res 1 through 9 on pages 13 through 2L SA = Shielded areas t t See pages $8 through (I for a list of references. CA,. - General acce:;s areas ttt Zone not modeled in the referenced cale llation, conservative values for this node assumed.
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)- l Zimer huclear red Utlon ENVIRONNF.NT7 L ZONE St Tf.8LE (R EV. b)
Date May 12, 1 % 3
- L ' - '
'GNOIN elf 4Sm Project No. 6020-16 Pager 4o;6)
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Calculated Integrated Radiation ec mrended Calculated l Maximum twposure Radiation Environ. Environ. Extreme l Relative No rma l *
- Accident ** Total ** Lxposure lof mental n*ntal Tempe ra tu re ** '9umidity** Maximum 60 years one year (rad) Testing ***
Area Conditions 99 tt tt Zone t (*F) Reference (%) Reference Pre ssure ** ReferenceII (a) (b) in + b) (rad) Re ference
"' N A4 A D 65-10k DC-A51-154 540 IC-A51-15-6 -0.23 to EC-A51-15-6 k.97x10h 5.69 x lug h,97 x Icy 1,0 x loVg g y -A( y U l *
(Cont'd) Condenser Room LOCA 60-118 3C6-Oh81-001 LO 3c6-oh81-004 16.9 ps.a 3c6-OL81-00h NC NC NC NC Z1-EQ-k B (el. 473'-5") (Alo)* (A10)* (A10)* (A/E)* (Figure 5) (F gu 22, HELB 150 3 6 1173-001 *100 Kn-11 16.5 psia NC NC NC NC Z1-EQ-A6B p (Node 9) t ti (' Node %}3-001 tti for 7 sec. (3 NMe6 1173-001
- 9) tti (A6B)*
26)E 60-118 306-0461-004 LO 3C6-0481-004 16.9'ps!a 3 6 0481-00h NC NC NC NC 21-EQ-A6B (F (A10)* (A10)* (A10)* (A6B)
- A-6E 65-122 3 540 DC-A51-15-10 -0.25 to DC-A51-15-10 1.71x10$ 5.89 x102# t.71 x la6 1.0 x 107 -E yTOg-T1 Radweste Tunnel LOCA lC-A51-15-10 -0.5 in W (6-20k 1 3% -Ok81-039 0-90 360L61-005 16.8 psla 3C6-OL81-00* NC NC NC NC Z1-Ea-T1 (Figures k&5) (TI)*
HELB 190 (2 see) 100 3 % -11 3-001 16 psia 3 6 117 NC NC NC NC Z1-E -T1 1gup 3 2 250 (5see) 16117h-001 (node tt (Node 3]J ttt for 7 sec. (Node 3)3-001 ttt (T1 * (Figure 26)' , # I" I Uigures M W LOOP (4- 3 6 0k81-005 8-100 306-0481-00! 16.8 ps a 3C6-0481-005 NC NC NC NC - -T1 A-7 A-7A 65-10h DC-A51-15-6 5-60 DC-A51-15-6 -0.25 in DC-A51-15-6 298x10$ 6.58 x 10) 6.88 x 103p 1.0 x 104# Z1-EQ-A7 HVAC Equip- W ment Poom LOCA 59-128 3c6-Oh81 00h LO 3c0-0481-00L 16.9 rs:a 3c6-OL81-00+! NC NC NC NC Z1-EQ-A7 (el. 570'4") (Figure 6) HELS 115 3 1173-001 100 3 6 1173-001 16.5 psit 3 % -1173-001 NC NC NC NC Z1-EQ-A7 (Figure = 2h, ' ttt (Node 5) t,t for 7 s*" Tode 5) ttt 25,E 8 p 59-128 3% -0481 00b ko 3 6 0481-00L 16.9 ps a ? 1 -0481-004 NC NC NC NC Z1-EQ-A7 (Figure 26) A-7B Normal 65-104 DC-A51-15-6 5-60 rata Acquisi. DC-A51-15-6 -0.25 i n DC-A51-15-6 1.75 x 10' ,5.5 x 10 14 2.3 x 10 1 1.0 x 103 Z1-EG-12 W i tion Module IDCA 59-128 3C6-Oh81-00L 40 36-0481-004 16.9 palt ' 6 0481-004 NC NC NC NC Cubicle Z1-EQ-12 (el. 570'-6") (Figure 6) HELB 115 3 6 1173-001 100 3M-1173-001 16.5 pain 106-1173-001 NC NC NC NC Z1-EQ-12 (Firures 24, Pt tri ( tti 7 "
- 26)# ttt (Figure 26)" LOOP $9-128 3C6-0481-001 40 3c6-oh81-004 16.9 psi i (c6-0481-004 NC NC a
NC NC Z1-EQ-12 HtL8 - liigh energy line break
- Subsonal designation for this area in the geferenced calculation. 4 LOCA - Los s of content accident (in containment) ** No eargins other than enneervatisms in calculations have been added to the pressure, e. Temperature blatory curves LOOP - Loss of of fsite power temperature, humidity values and radiation doser above. m- saure Mory curns NA - Not applicable
*** Appropriate margins are included in the recommended radiation exposures for testing. v. Pelative humidity curves NC - No change from normal values $ - Based on units being sealed to Not-nal #t This dose bounds all environnental condittens.
*igr al operating coniitions Environmental zones are defined in Figures 1 through 9 on pages 13 through 21. Prevent entry of ambient air.
CO - t i h$eN' eb di the r ebb 1MfM8eonservative values for this node assumed.
SAtmENT$ LUNDY
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Project No. 6020-16 J NGINE ~F IS-PdF*1 5 OI #I
- Calculated Integrated Eadiation hec w ended Calculated i j
Maxinen Exposure Radiation Environ. ' Environ- Extreme Relative Nor ma t *
- 4ccLJent** Iotal** Espesure for mental mental Tempe ra tu re **
Zone , Area Conditions (*F) 99 Mumidity** tt wamimum 40 years one year (red) Testing *** 99 Reference (%) De fe renc e Pressure ** Referenceit fa) (b) b + h) (rad) Re fe renc e e . - C-1 Primary Normal 65-150 DC-A51-15-8 ko-90 DC-A51-15-8 .5 to 2 DC-A51-15 EQ-1 59x10' EQ-1.k7x10[ Z1-EQ-C1 Conteirament psig CO-1.59x107 CO-8.8(x13 EG-1.6 3x10dCO-1.0x10
%-9.02x1C, EL-2.0x104e4 Z1-EQ-C)
(Figures 1,2' RAR Table
- k5.Opsig 6,7 &8) LOCA $0 6.2-1 100 FCAR Table 6.2-1 NC NC NC NC " i' (Figure 28)e HELS
- NA NA NA NA NA NA NC NC NC NC 5 LOOP NA NA NA NA NA NA NC NC *
(Figure 29) NC NC l C-2 Wetwell N8'**l 60-90 100 -0.5 to 4.v 6 (Figures 4,5) IQ-1.59x10 t; 1.47x10[ n-EQ C1 3-1.59x10 Co-8.8tix10, rQ-1.63x10 EQ-2.0x10f psig LOCA 275 CO-9.02x10 CO-1.cx10 # n-EQ-C3 EAR Table 100 FSAR Table NC NC
- 45 PK16 NC NC l4 6.2 1 6.2-1 (Figure 28f HELS NA NA NA NA NA' 1A NC NC NC NC *
(Figure 29)" LOOP NA NA NA NA NA NA NC NC NC $C " i / r D-1 D-1A 95 DC-A51-15-1 0-100; - 4tusperic' - 2 3.5 x 10 k 1.10 x 10 1.14 s 10 - 1.0 x 105 8 Z1-EQ-C1A
' Diesel j Generator LOCA '
3 NA NA NA 10 ' HA NA NC NC $C EC Z1-!Q-D1E Building Roof (el.5166'0") ytts ' NA NA NA' NA NA NA NC NC NC (Figure 1) ' NC Z1-IQ-Dit LOOP NA NA NA NA NA NA NC NC NC NC 21-EQ-Dit Normal D-1B 35-122 2 Diesel DC-A51-15-1 5-100 DC-A;' 1-15-1 +0.65 in VD-01 3.5 x 10 h 7 93 x #li 1.14 x lo 3g 1,x 10' # 8 Z1-E4-M B MA w) Cenerator NC DC-A51-15-1 NC NC VD-01 NC NC Building DC-A51-15-1 NC NC Z1.EQ-D1B (el. 535'-7") ggte NA Essential NA Essential NA Essential NC NC NC NC (Figures 2,3) WAC HVAC HVAC Z1-EQ-ElB toop 40-122 Essential NA Essential NA Essential NC NC
- WAC WAC WAC NC NC Z1-EQ-ElB i has - nign energy lane break
- Subsonal designation for this area in the referenced calculation.
LOCA - Loss of coolant accident (in containttent) ** No margins other than conservatises in calculations have been added to the pressure, e- Temperature history curvas LOOP = Loss of offsite power twrature, humidity values and radiation doses above, NA = Not applicable a- Pressare history curves NC - No change from normal values *** Appropriate margins are included in the recommended radiation exposures for testing. v- Pelative humidity curves Normal - Normal operating conditions # This dose bounds all ervirotwental conditions. EQ - Equipment t Environmental zones are defired in Figures 1 through 9 on pages 13 through 21. t t See pages 58 through 61 for a list of references. CO - Coatings
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ENytsnN*ENTJ.L TONE RY ttBtt (PET. b) ' " C GENT M' UNDY - "'" : **r " 2 PsajIct No. 6020-16
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i NGINEEABm Paan & e f 61 i I Eadiation kecowreended Calculated l Calculated Inte gre ter, jwalmum , , Environ < Environ- Extreme pelative ;.or =41 = = Au ident** Io t a l ** Exposure fet mental mental- Tempe ra ture** conditions 99 Humidity ** 99 Maximum 60 years one year (und) Testing *** 99 -Zone , Area (*F) Reference (t) Reference Pressure ** Referenceit (a) (b) (s + b) (rad) Reference R-1 R-1 A 65-10l+ ?C-A51-15-11 0-60 DC-A51-15-11 -0.16 to i DC-A51-15-1) 3.0 x 102# b.7 x ION h.7 x 10% 6.0 x 10'# Z1-tQ-MA Beactor -0.25 in W Bu11dir.g LOCA h$ 129 306-0/>81-002 0-90 306-0681-002 -0.25 DC-A51-25 NC UC NC NC Z1-EQ-nA (el. 5L6'-0") (RI) * (R1) * (Figure 1) ggte 235 W 78+-M 100 MAD 74- M 2k.k psia MAD-74-764 NC NC NC NC Z1-E;-RIA (Firures 30, (Case 2) (Case 2) for 20 see (Case 2) 31, 34)* (Figure 35)" e LOOP 45-129 106-0681-002 0-90 3%-0681-00: -0.25 DC-A51-25 BC NC NC NC n-EQ-MA (Figures 32,33 (RI)* (R1)* R-14 Reactor 65-10l* DC-A51-15-11 040 DC-A51-15 11 4.16 to DC-A51-15-11 7.6 x 10 # 3.7 x 10## 3.7 x 107# 5.0 x 107# 3-EQ-RIS
-0.25 in E .
Puilding LOCA 36-M81-00; kS-129 0-90 36-E21-002 -0.25 in W DC-A51-25 NC NC ,5C NC Z1-EQ-RlB (el. 5L6*-0") (RI)* (RI)* (Figure 1) HELS 235 MAD 74-76k 100 MAD 74-764 24.4 psia MAD 716-764 (Figures 30, (Case 2) ' for 20 sec. (Case 2) BC NC NC NC Z1-EQ-R1B 31 N (Case 2) (rig'ur. L.. t00, 45-129 3 6 -0681-00: 0-90 3 6 0i81-002 -0.25 E DC-A51-25 NC IC NC NC Z1-EQ-RIB (Figures ?2,13), (al) (n). Normal f R-1C r Beactor 65-104 DC-A51 *5-11 0-60 1<-A51-15-11 -0.16 to DC-A51-15-11 SA-6.6x10yA-k.7kalh, ?A-5.k1xld' EA-1.0x107# Z1-EQ-RIC
-0.25 in W: CAA k.9x10gMA-7.2kx1Cs iAA-7.24x1) MA-1.0x107#
Building LOCA b$-igg 3M-of,81-oo: 0-90 3c64tl-002 -0.25 in E DC-A51-25 NC IIC NC NC Z1-EQ-RIC (el. 5L6'-0") (Rs ) * ( Rl)* (Figure 1) HELB 23$ MAD f4- 9 loo MAL 7L-764 24.4 psia MAD 74-76b NC NC NC NC Z1-EQ-RIC (Case 2) (Case 2) for 20 see (Case 2) (rigures 30,
?l, 31a)# LOOP 306-0681-00, 0-W (Figure 35)g b5-129 3y -o, h -002 -0.25 in W - DC-A51-25 NC NC NC NC Z1-EQ-RIC (rigures32,33f (al). ( gi) .
B-2 R-2A A5-10k 0-60 -0. lf. ' i Reactor DC A51-15-11 DC-A51-15-11 DC-A51-15-11 1.71x104 4.74 x 10' 6.45 x Ich 1.0 x 10 # R2 LOCA
-0.25 tr. W Buildirg b$-129 3%-0681-00. 0-90 3M-0E81-002 -0.25 in E DC-A51-25 NC NC NC NC (el. 525'-7") (E2)* (R2)* Z1-EQ-R2 I Figure ?) 240 (R2).
acts 3 % -1173-001 100 3 6 1173-001 16 psia fcr 30 - 1173-001 NJ NC NC NC Z1-E;.-R2 (Node 2)e (Node 2)* 7 secocos (Mode 2)* (52). (Figureg10, 31, 27s 3c6-Or81-00;
. (Fictre 27)a , LOOP h5-129 0-90 3%.621-002 -0.25 in K DC-A51-25 NC NC NC NC Z1-EQ-R2 *
(Figures 3?,Ui (R2)* (IC) * (B2)* nita - Magh energy line break
- Subsonal designation tor this area in the referer.ced calci.tation.
LOCA - Loss of coolant accident (in containment) ** No margins other then conservatisms in calculations have been added to the pressgre LOOP - Loss of of fsite power temperature, humid'ty valucJ and radiation doses. o $ = Terperature history curves NA - Not applicable , NC - No change from normal values *** Appropriate margins are included in the recommended radiation exposures for testin&* T= Relative humidity curves Normal # This dose bounds all environnental conditions.
'3creal crerating conditions t Environmental zones are defined in Figures 1 through 9 on pages 13 thiough 21 SA - Chie16ed Areas t t See pages 58 through 61 for a list of references.
GAA General access areas
i twv190NmTat Z<wt ^ of T7 st t (ptv. F. ) Zim t Nuc17 r F L: tion S ENT31. UNDY Om mi 12. n , w Prrjec t No. 6020-
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ilNDINCEAS. pue : 7 ,y (j I "" * *d'd Calculated l Ma s tanse Calculated Integrated F w po s' u r e Padiation Environ- ' Environ- Entreme Relative hosmal " h ad nt** Lota1** Fsposure for mental mental Temperature ** Humidity ** Maximum 40 years one year (rau) 7esting*** 99 99 99 Zone , Area Onditions (*F) Reference (U peference Pressure ** Referenceit (a) (b) (n + $) (rad) Reference R-2 R-28 N*'*al 65-122 DC-A51-15 11 0-60 DC-A51-15-11 -0.16 to DC-A51-15-11 1.71 x 10 e k.74x10) 6.45 x 10 1.0 a 107# n-WR2 'Coru d) Reactor -0.25 in m (s m Buildira LOCA L5-129 305-0681-00. 0-90 3%-0/41-002 -0.25 in
- DC-A51-25 NC NC NC NC n-W R2 (el. 525'-7") (R2). (R2) * ( F2)*
(Figure 2) HEL8 240 3r6-1173-00 : 100 16 psia (Figures 3 1 -1173-001 34L1173-001 NC NC NC NC - O-R' N (Nate 2)* (No te 2)* for 7 see. ( Node 2)
- mb II'gure 27s,u , LOOP 45-129 3%-0681-00: 0-90 30i-E 81-002 -0.25 in W DC-A51-25 NC f'C PC NC R2 (Fi ,
(Figures 32,n. 65-104 DC-A$1-15-11 0 iO DC.A51-15-11 -0.16 to DC-A51-15-1: 1.71 x 10 4 b.61 x 10' ,' 6.32 x 131 1.0 x 104 z1-E;. F3 R-3 R-3 A ( p3) . Reactor -0.25 in V. Building LOCA 45-129 306-O/61-00? NC 3C6-Oi81-002 -0.25 in W IC-A51-25 NC NC NC NC n-LG-R3 (p3). (el. 503'-6*) (R3) . (R3) . (rir.ure 4) MELS 100 18 psia NC NC NC NC n-EG-R) 225 % 1171-001 3Cr-1173-QO1 IMone f.) 3(Mode
% 1173-)n01 6* for 7 see. 'h* (R3).
(Figares,30, 0-90 NC NC Z1-FQ-F3 31, 27) gnop k$.129 g -o f1-oo, 306-0/21-002 -0.25 in V DC-A51-25 NC NC (Figure 27,, ) * (R3)* (R3) * ( R3) * (Figures ?2.33) Normal 2
- 1. 0 x 109 21-E;- A5 B P-3B 65-10k DC.A51-15-ll 0 60 DC-A51-15 11 -0.16 to DC-A51-15-ll 3 50 x 10 # 8.74 x 1056 8.74x10h Peactor -0.2% in W (A5B)*
LOCA ES-129 3c6-OiC1-00; NC 3$ -0/PL-002 -0.25 in w T4-A51-25 NC NC NC NC Z1-EQ-A5B Building (el. 503'-6") ( R3) * (n). IB psia 3C6-1173-UL,1 NC NC NC NC (A5B)* Z1-E;-A5B (Figure h) MEL8 225 3C6 1173-001 100 36 -1173-001 (Figures 30, (Node 6)* (Node 6)* (Node 6)* 31,27)# LOOP (5-129 35-y 81-on 0@ 303-0 S1-00; -0.25 in C DC-A5a-25 NC NC NC NC Zl-EQ-A5 B (rigure n), , (33) . (33). (Figures 32,31) h-4A Normal Rb Remetor 65-104 DC-A51-15-11 0-60 IC-A51-15-11 -0.10 to TC-A51-15-11 1.71 x 10 i L.61 x IU ' .32 x ld) 1.0 x 107# Z1-EQ-W
-0.25 in V (p).
Building Less Five ECCS LOCA h5-129 3C6-E81-00. NC 3T-0( 91-002 -0.25 in b DC-A51-25 NC NC NC NC Zl-EL.W (p}e Cubicles (W)* (RL)* PRD 74-764 100 fuD 74-764 15.7 rsia MAD 74-764 BC NC NC NC Zl-FQ- W (el. 475' A") HELA 21?- (Case 1) (p). (Figure 5) (Case 1) (Case 1) for 10 see. (Figures 30, 306-0/41-00 0-90 3% -001-00: -0.25 in E DC-A51-25 i NC NC NC NC U-L;-n 31,3qe a LOOP b5-129 (rigure m , (14) . ( m)* I (a). , (Figures 32.13' htLB - riigra e ne r gy l a ne b r e a m
- Subsonal designation for this area in the referenced calculation.
LOCA - Loss of coolant accident (in containm*ct) ** No eargins other thas conservatists in calculations have been added to the paessure, G- 7emperature history curves LOOP - Loss of off s a te power temperature, tumidity values and radiatien doses above . e- Pressure history curves NA - Not applicable *** Appropriate margtns are included in the recommended rad 1ation exposures for testing. ,- Relative humidity curves NC - No change from norTal values # This dose bounds all enviranmental conditions. Nor=al - Norval eterating conditions t Environmental rones are defined in Figures 1 throuEh 9 on pages 13 through 21 t t See pages 58 throust 61 for a list of references.
E' "qGENT%" LUNDY " * " " * " ' "
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O' E'rS E' - Projtet No. 6020-1) Nf3tNC AS _ Page: 8 e f (.)
* *** * # *"d'd Calculated w
; astmwn Calculated Integrated Ewroure Radiatton Environ. Environ. Estreme mental mental
[ Relative :. ores t *
- AcctJent** Iotal** Exposuse for Teeperature** 99]aumidity** % simum Cnnditions 99 40 years one year (rad) Te s t ir.g***
Zone t Area ('F) Reference i ( *. ) Re fe rence Pressure ** Referenceit (a) (b) (a + b) (rad) Re fe rence tt i--is i R4 Fenetor Buildin~ 65-104 DC-A51-15-11 04.0 T-A51-15-11 -o.16 to DC-A51-15-11 1.7141(# l. 61x10'# 4. 32 x10'1 1.Ox10's n -E Q- k. (Cont *d} RIIR Pu.~p Cutiel, -0..*5 1n 7 f
- LP (el. L75* 4") LOCA 45-148 3C-451-15-5 NC DC-A51-15-11 -0.25 in W DC-A51-25 NC NC NC NC 21 LQ-A (Fiore 5) ( A)*
HELS MAE 7k*70s M D 74-76k 15.7 psia MAD 74-764 (Figures 10, 213 (eg,, g) 100 for 10 se- NC NC E NC 21-G- A (Case 1) (Case 1) 21.E)* Esser.tial ( Al' (higure 't7;' LOOP NA NA NA NA NA NC NC NC NC n -E q.W (Figures 32.23[ HVAC ($). 1 65-104 LC-A51-15-11 0 fo DC-A51-15-11 .o.1 to D C-A51-15-11 3,71,1n6# r Buildire k.61x10' # 6.32x1## 1.oxlC7# n-EQ- A PCS Pump (%). Cuticle LOCA k$-lk8 DC-A51-15-5 NC C-A51-15-11 -0.25 in W; DC-A51-25 NC NC NC NC 21-E;- A (el. L75'J ") (W)* (Fio re 5) HELB 213 MAD 74 'X 4 MD 74-76k 15.4 psla MAD 74-76' (Case 1, NC NC NC NC n.7-A (Figures 30, (Care 1) (Case 1) for 10 sec. (34). ill,W# Loop i ssential NA NA NA NA NC NC NC NC Zl-E^- A NA (Fio re 27) , , INAC (g}. (Firures 12.11 B-k D Normal . Peactor Bullitr~ 6 5-10k EC-A51-15-11 0-60 DC-A51-15-11 -0.16 to DC A51-15-ll 1.71x10 8 k.61x10 # 6.32 x 10 1.0 m 10 7 n-M-A
-0.25 in W; ( A)*
RCIC Cubicle LOCA L5-11.8 DC-A51-15-5 NC DC-A51-15-11 -0.25 in WC DC-A51-15 NC NC NC NC Zl-EQ-A (el. 475'J>") (Figure 5) 218 D 71-7 k 5 100 7 5 psia MAD- 4 $ ( A)* HEL5 (Case 1) (Case 1) for 10 sec, NC NC !C NC Z1-EQ- A (Case 1) (g). (Figures p. fl. E ' LOOP NA Essential NA NA NA (Fipre 37)s ' INAC NA NC NC NC NC Zl-Ep'A (Figures 32,H) (A, P-4E No mal D Peactor Duildi' < 65 104 DC-A51-15-11 04,0 DC-A51-15-11 -0.16 to DC A51-15-ll 1.71x10 8 4.61x10f # 6.32 x 10 1.0 x 107 Z1-FQ-6 FER Cuticle -0.25 in W ( A)* LOCA L5-1k8 DC-A51-15-5 NC DC-A51-15-11 -0.25 in W; DC-A51-25 NO NC NC (el. L75'-6") NC Z1-f C- A (g)e I" N 100 HELB 217 I'iAL 74-7a map 7k-764 15.6 psia MAD 74-764 NC NC NC 16C Z1-FQ- A (FW* % (Case 1) (Case 1) r 10 sec. (Case 1) (A)* S1, W ' NA Essential NA MA (Fl o re 17)e , LOOP NA NA NC NC NC (Figures 32. W inAC NC 21-r,.A (9) nLtB = High energy line break
- SubsOn61 de&ignatlon for thte area in the referenced Calculation.
LOCA = Loss of coolant accident (in containment) ** No eargins other them con 9ervatisis in calculations have been added to the pressure, I LOCP - Loss of of f site Iower temperature, tumidity vales an1 radiation dases above. e- Pressure history curves NA - Not applicable
*** Appropriate marglns are included in the recoernended radiation exposures for testing. v- Relatiw huidity curves NC - No change f roen normal values Norul - Norni cperatir.g conditions # This dose bounds t Environmental allare zones envirwental at tined in conditioSs fiorea through 9 on pages 13 througi 21.
tt See pages 58 ttrough 61 for a list of refermees.
" " " " " ' ' U"'2;'sl ""*'
RGENT3.1. UNDY Project No. 6020-15 _ ._ -~D ENO4 NEE AS- Page: 9 of 61 Calculated Integrated Radiation Reco readed Calculated {1animum EwMeure Radiatiop Environ, Environ. Entreme lRelattve Normal " As c iJe nt*
- Iota 1** Laposure for mental cental temperature ** iumidity** 99 Manteum 40 years one year (rad) Testin4***
Conditions 99 99 Zone , Area (*F) Re fe rence (%) Re fe re nce Pressure ** Re ferenceit (a) (b) is + b) (rad) Re fe rence p.4 F R-k F Normal 65-104 TC-A51-15-11 0-( 0 DC-A51 15-11 -0.16 to DC-A51-15-11 1.71x10"# 4.61x10"# 6.32 x If 1.0 x ICI n-F Reactor N11db -o,; 3 g ,, w ( .N. (Cont'd) Elut Heat LCCA 45-148 DC-A51-15-ll NC DC-A51-15-11 -0.25 in E DC-A51-15-ll NC NC NC NC Exchanger Room Zl-F (g.84 (el. 475'-6") (Figure 5) utta 213 MAD-7k-764 loo m 74-764 15.7 psia MAD 74-76k NC NC NC NC Zl-F (Case 1) (Case 1) for 10 see. (Case 1) ,N. gp (Figure 30, NA Essential NA NA NA NA NC NC NC gngp NC Zl-Fq-% 31.Fi HVAC ( Ds) * (Figure 37)' , (Firures 32,31 R-5 P-5A 65-10h DC-A51-15-ll) 0 60 E C-A51-15 11 -0.16 to DC-A51-15-11 3.0x10D# k.8x10'# 5.1 x 1:f'* 1.0 x 107* Ze -n Peactor -0.25 in W. . hilding LOCA L5-129 3C6-0681-00; 0-9) 3C6-OE81-CO2 -0.25 in W: DC-A51-25 BC NC NC NC Zl-F'-R5-(el. 570* 6") (p5). (35)e US} (Figure 6) 23g (Figures 30, HELB MAO-7k-764 100 MA" 7k-764 16.5 psia NC NC NC NC 31,38f (Case 3) (Case 3) for 10 sec. MAD-7k-76)4 (Case 3 rhp5 (Figure 39? ' toop 45-129 3c6-Of 81-00 0-90 306-oC81-002 -0.25 in W LC.A51-25 NC NC NC N0 n-E;-R$ (Figure 32,33) (R5)* (g)* (p5}e DC.A51-15-ll -0.16 to 2
- B-58 (5-104 DC-A51-15-11 0-60 DC-A51-15-11 3.5x10 # 8.65x10 # 8.65 x 10) 1.0 x 10DJ Zl-E;-A7C HVAC Equipment -0.25 in W (A7C)*
Poom LOCA k5-129 3d-0481-00', 0-% 3c6-ok81-OOL -0.25 in W DC-A51-25 NC NC NC NC Zl-E;-A7" (el. 570'-6") sP5)* (M)* (ATC) * (Figure 6) ggt, 218 MA;-7k-764 100 MAD-74-764 16.5 psia MAD-7k-764 NC NC NC NC n-EG-A7C (Case 3) (Case 3) for 10 se.- (Case 3) (A7C)* (Figures 30, 31,38 f , LocP 45-129 3d-Ok81-Oo: 0-90 3c6-Ok81-002 -0.25 in W DC-A51-25 NC NC NC NC ZZl-EG-ATC (Figure 39) v (RS)* (ES)* (A7C)* (Figures 32,33' 6 6 P-5C 65-122 D C-A51-15-11 0-60 DC-A51-15-ll -0.16 to DC-A51-15-11 5.32x10 # 1.02x15# 6.3kx10 # 1.0 x 107 # n P*-2 Reactor -0. 5 in W: -2)* h t loir.g LOCA 45-129 3C6-0681-00 0-90 3d -0C81-002 -0.25 in W DC-A51-25 NC NC NC NC Zl-EQ-F5-2 (el. 570'-6") ( R5) * (M)* (B5-2)* (Figure 6) HEL8 218 MAD-74-764 100 MAD-74-764 ,16.5 psia MAD ?L-764 NC NC NC NC n -EQ-F5-2 (Case 3) (Case 3) : for 10 see, (Case 3) (p5-2)* (Figur*r 30, 31,38f LOOP L5-129 30;-0181-00 o-90 3c6-0681-002 -0.25 in W DC-A51-25 NC NC N. i NC Z1 EQ-RS-2 , (Figure 39f , ( RS) * ( RS)* (R5 2)* (Figures 32,33 HLLB - High energy line break
- Sgbtoral designation for this area in the referenced calculation.
-h atm Mstory mes LOCA - Loss of coolant accident (in containment) ** No eargins other than conservatises in calculatioes have been added to the pressare. W- Fressum history curves LOCP - Lo s s o f o f f s i t e powe r te persture, humidity values and radiation doses above.
NA - Not applicable T- Relative hum 1Sity curvea
*** Appropriate margins are included in the recommended radiation exposures for testing.
NC - No change f rom normal value s e This dose beunds att environmental conditions. Normal - Nor al cperating conditims t Environmental zones are defirrd in Figures 1 thrcngh 9 on pages 13 through 21. t t See pages 58 through 61 fon a list of references.
f,"ta payr" ""' 1p ,'(l' * "a* pEG ENTMUNDY " ""*" " ' ""
^" " c" 5t Project No. 60La t
_ _ _ _ r NGINET see Pa m 10 of 61
**d5**'*" "*'*"d*d '
Calculated Mantuum Calculated Integrated twposure RadLattes Enviros. Environ. Entreme Relative Normalse u sadenree lota1** [sposure fag mental mental Temperature ** !!ualdity** 99 Manteum 40 years one year (rad) ' Testing *** 99 99 Zone t Area Condittoes _ (*F) Reference (Z) Reference Pressure ** Referenceti (a) , (b) In + b) (red) Referesee D R-5 R-5D Normal 65-122 DC-A51-15-1: 0-60 1C-A51-15-11l -0.16 to DC-A51-15-11 3.09x10 # 1.79x15# 4.88 x 10h 1.0 x 10 #i (Cont'd) Reactor -0.P5 In W 21-EG.H5.-1 (p$.1) Building LOCA 45-129 3M-Oral-00 0-90 3C6-Or,81-002 -0.25 in WC DC-A51-25 NC NC NC NC 21 -FQ- R5-1 (el. 570'-6") (RS)* (RS)* ( F5-1) * (Figure 6) HEL8 218 MAD-74-764 100 MAD-74-764 16.5 Pala MAD-7k-764 NC NC NC NC 21-EG-R$.1 (Figuren 30 (Case 3) (Case 3) for 10 sec (Case 3) (R5-1)* 31,38)* toop h5-129 16-Or,81-00? 0-90 3060rAl-00: -0.25 in WC DC-A51-25 NC NC NC NC Z1-EQ-RS-1 (rigure 39)", (RS)* (R5)* (R5-1)* (rigure p.33 R-6 R-6 A 65-104 DC-A51-15-11 0-60 DC-A51-15-11 -0.16 to DC-A51-15-11 2.98x10 # k.65x10 I 4.65x100# 6.0x10 0* Z1-EQ-I(A Beactor 0.7 in WG
- Bu11dir.g LOCA 45-129 306-0681-002 0-W 3M-0681 'J02 4.25 in E DC-A51-25 NC NC NC NC Z1-EQ-EA (el. 593'-6") (Hf ). .
(H (Figure 7) HELB 172
,,, ' " hse fr1 e , 'g (Figures 30, 31,40)* LOOP k5-129 3 6 -0681-002 0-90 35.Or,81-002 -0.25 in E DC-A51-25 Rd NC NC NC (Figure b1), 21 EQ-16A (Fiaures 112,U e (g). (E)*
R.6 8 65-104 DC-A51-15-11 044 DC-A51-15-11 -0.16 to DC-A51-15-11 7.bhx10?# 3.40x107# 3.47x107# 5.0x107# Z1-EQ-EB Reactor -0 ?',in W: Bu11dir:g h5-129 306-Or81-00p Os)0 36 -Oi,81 002 -0. 2', i n W. DC-A51-25 NC NC NC NC Z1-EQ-It B (el. 593'-6 ) (m). (% * (Figure 7) HEL9 172 MAD 74-76h 100 mas 7.-)764 15.1 psia MAD 7b-764 NC NC NC NC Z1-EQ-It B (Case 4) (Caseb) for 10 see (Case Q (Figure,s 3g,go) 30' h5-129 3Cfs-0681-002 0-90 3M -Or,81-002 -0.25 in W: DC-A51-25 NC NC NC gp NC Z1-EQ-k B (F1gure b1)" , (I6) * (M)* (Figures 32,33?
~
Normal R-6 C 65-104 DC-A51-15-11 044 DC-A51-15-11 -0.16 to DC-A51-15-11 b 8.87x10 # 6 3 57x10 # 3.66x106g g,o,go7p gg,gg,,,;o Reactor -0.25 tra E Building k5-129 36 -0681-002 0-90 306-0681-002 -0.25 in W: DC-A51-25 NC NC NC NC Z1-EQ.Ec (el. 593'-6") 220 (gje (16)* (Figure 7) HEL8 %D 74-764 100 MAD 74-764 16.6 paia MAD-74-764l NC NC NC NC Z1-EQ-I6C (Figures 30, (Case 4) (Case b) for 10 sec (Case 4) 31,40)# e (Figure b1) LOOP %5-129 3C6-0681 002 0 90 306-0081-002 -0.25 in W DC-A51-25 NC NC NC NC Z1-EQ-R C
~
(rieures 37,33
> ), ,
l MLLB - High energy line break
- Subsonal designation tot this area la the referer.ced calculation.
LOCA - Loss of coolant accident (in containment) ** No *argins other than conservatisms in calculations have been added to the pressuse. O Temperature history curves ! LOOP - Loss of offsite power temperature, humidity vntues and ra11ation doses above, s. Pressure V.1 story curves NA - Not app!! cable *** Appropriate marg!ns are included In the recomended radiation exposures for testing. v. Relative humidity curves NC - No change f rom nor nal values # This dose bounds all environnental condit tors
- Normal - Norul operatir4 conditions t Environmental ww s are efined in Firuras 1 through 9 on pages 13 through 21.
t t See Pagea 58 through 61 ror a list of references. t
-.m.
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7terner hc1 T r [
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-GENT & LUNDY "" 'r22 1 J e CNGINE' AS_ Prnjrct No. 6010-16 Pa g n Il e f (,1 Calculated ratsulated Integrated 'U**E** """*d Manteum twposure Environ- '
Environ. Entreme Relative Badiation mental mental Temperature ** No rma t * = Accident ** Iota 1** Esposure for Humidity ** Maximum 40 years one year (rad) Zone 9 Area Conditions (*P) Reference99 99 Testing *** 99 (%) Reference Pressure ** Referenceit (a) (b) fa + b) (rad) Re ference
"* "* I B-7 Reactor 65-104 o-60 -0.16 to 2 Building DC-A51-15-11 DC-A51 15-11 DC-A51-15-11 2.o7x10 # 8.65x105# 8.66x105# 1.0alo7# n-E;-yr
-0.25 in W.
(el. 627*-9") LOCA h5-129 3c6-0681-002 NC 3 L o681-002 -0.25 in W DC-A51-25 NC NC (Figure 8) ( gy). NC NC n-EQ-R7 (37)* HELB 17p MAD 74-76 100 14AD 7k-76h 15.1 psia MAD 7k-764 NC NC NC NC n-Eq-gg (Figures 30, (Cass h) ttt (Case 4) M t for 10 sec. (Case 4)tti ( fr k1) y LOOP k5-129 3c6-Of81-002 0-90 3 0 0681-002 '-0.25 in W LC-A51-25 E NC NC NC n-tQ-iq (rigures 32,33 (R7)* (R7)* l I h-8 Main Steam Tunnel Ex 65-122 LC-A51-15-1: 0-60 C-A51-15-11 -0.16 to DC-A51-15-11 1.71x10 # k.61xio6# 6. 32x10"# 1.0x107e n-EQ-9 Botiding Side LOCA 0-90 -0.25 in W k5-152 36-0681-00. $CG-Of,81 002 -0.25 in WC OC-A51-25 NC NC NC (Figun 5) NC Z1-E4-W 290(3 see) 275 (k mee) 3 6 1a73-001 100 306-g i 28.8 psia 306-1173 001 e HELB g5 for 6 sec. NC 7 , (Node 3)* NC NC NC n-EQ-A 7 see) s LOOP 45-152 306-0681-002 0*90 3c6-0681-002 -o.25 in W DC-A51-25 NC NC NC ( 2M NC 21-EQ- 6 s s-1 65-10h No pressure 2 7.66x102# DC-A51-15-4 5-100 DC-A51-15 k Approx. Service kater Atmospherie control 2 98x10 # 4.68x102# 1.oxio"# Z1-EQ-S1 rump LOCA UC DC-A51-15-4 NC NC DC-A51-15A NC NC KC NC NC Structu re Z1-EQ-31 (Figure 9) HELB NA No IEL NA No IEL MA No HEL NC NC NC NC Z1-EQ-31 LOOP PA Essential NA Essential MA Essential NC NC NC NC Z1.EQ-31 HVAC INAC INAC S-2 65-104 DC-A51-15-k DC-A51-15-lh Approx. 2 7.6ex102# 5-100 No pressure Service 2.98x10 # 4.68x10 # 1.Ox10 # Z1-EQ-51 Atmospheric control Wate.- Pump LOCA - - - - *
- NC NC NC NC Z1-EQ-51 Structure (Figure 9) NA No HEL HEL8 NA No HEL NA 10HG NC NC NC NC Z1-EQ-51 toop - -
NC NC NC NC Z1.EQ-51 , HELS - High energy tint break
- Subsonal designation for this ates in the referenced calculation, g- Temperature history curves LOCA - Loss of coolant accident (in Containment)
LOOP - Loss of offsite power ** No cargins other then conservatises in calculations have been added to the pressure, a- Pressure history curves N4 - Not applicable terparature,bumidity values and radiation doses above. v Helative humidity. curves NC - No change from normal values *** AFproPriate margins are included in the recommended radiation exposures for testing. Norzal - Normal operating con 11tions # t This dose bounds all environmental conditions. tt Environmental zones are defined in Figures 1 through 9 on pages 13 throush 21 See pa;es 53 through 61 for a list of references. ttt Zones not soleled in the referericed calculations, conservative values of el. 593'-6" assumed.
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- Calculated %ximun Calculated Integrated Esposure Radiation Env it ori Environ- Extreme ee lative breal = = Accident ** Iotal** Exposure for j mental mental Temperature ** lumidity** Maximum 40 years one year (red) Testing ***
99 99 tt 2cee , Area Conditions ('F) Reference (%) Reference Pressure ** Referenceit (a) (b) b + b) (red) Re fe renc e
~
7-1 Normal Main Stee.m c:5-12e DC-A51-15-6 5-60 tc-A51-154 .125 in ic to-A51-15-6 1.71110"# 5.89x10' # 1.7 x lo' i 1.0 x 10 /# l n -Eq-51 Tur.mel (Aur. Putiding Side) LOCA 66-204 35 -OL81-00' O-90 W -OL81-M5 14.8 f. la 35-Ok81-005 NC N7 NC NO (Figures b 5) 21-EQ-51 290 (2 sec.) (Figures k2, EL8 250 (5 sec.) 3C6-1173-00: 100 W -1173-001 16 psia 35-1173-001 HC NC NC NO 21 Eq-51 L3,26)* 220 (after (NoJe 3)* (Node 3)* for 7 see. (Node 3)* (Figure 26)u , 7 ,ec) (Figures kk,k5 IDOP 66-20k 3C6-0481-00 0-90 pi-0481-005 16.8 psia 36-0481-005 NC NC NO NC Z1-EQ-51 i l eELj - Hidn energy ,ine bresa
- Subsonal designation for this area in the referenced calculation.
LOCA - Loss of coolant acCldent (in cor.tsircent) ** No eargins other than conservatists in Calculations have been added to the pressure G- W ertture history curves LOOP - Loss of offsite power te perature, burddity values and radiation doses above. e 5- Tvess'.re history curyn NA - Not applicable NC - No change from nor*ai values *** Appropriate rargins are included in the recoerended radiation esposures for testing. v. Relative hu=1dity curves e This dose bounds all environ-ental conditions. Ng: mal - Njr al crerstirg cor.ditions t Fnyirorcerdal zor.es are defined in Figuras 1 through 9 on pages 13 through 21
. at ,
t k Nr'e $ 7 s h e h [ Ik the N e!e $alfb(fg;stonservative values for this noie assumed.
4.., e l Z'. =er Nuclear Power Station
.SARGENT&LUNDY
. ! Date:
Project No. 6020-16 May 12, 1983
- ENGINEERS.j f Page: 13 of 61 ENVIRO?' MEN'2AL ::ONE SUM.JsRY TABLE (Rev. 4)
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- i Zin=er Nuclear Power Station
- SARGENT& LUNDY o ce: May 12, 1983 I Project No. 6020-16 ENGINEERSL Page: 15 of 61 ENVIRONMENT.4L ZONE SUM?iARY TABLE (Rev. 4 )
.c
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l Zic:::1st Nuclear Powar Station o te: nay 12, 1983
- SARGENT&LUNDY i Proj ect No. 6020-16 g _ IENGINEERS.s Page: 16 of 61 b
ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) c,
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- a. ,
Zic=st Nuclear Power Station
. SARGENT&LUNDY I na t e.:
Project No. 6020-16 nay 12, 1983
; ENGINEERS. Page: 17 of 61 9
ENVIRONME! ITAL ZOMF St'Pl%RY TABLE (Rev. 4) m n u .c 1 u-r m, g%.,N3 - % , _ _ _ $ _ ,. _ _ _ g.. .- c._: y "'AW- EZ'y[ - QA'- ~*: . (5I a 4IN
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Zi:::mer Nuclazr Power Station SARGENT&l. UNDY Date: nay 12, 19e3 iENGINEERBj Project No. 6020-16 (3 Page: 18 of 61 V ENVIRO?PMAL ZONE SUM'*ARY 'rAELE (Rey, 4) 3 ', ' Ij ,@
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1 l l q a g g RIT'S I 1l Zi::=er Nuclear Power Station Date: May 12, 1983 G M n u kIE a d b M M 'll Project No. 6020-16 e iENGINEERs0
-Q Page: 19 of 61 ENVIROF.MF.HTAL ZONE Supja.ARY 7;BLE (Rev. 4)
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Zi::=er Nuclear Power Station 1 ShRGENT&LUNDY uate: xay 12, 1983 Project No. 6020-16 IENGINEERBu Page: 20 of 61 ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) o u - - y@ .O n~\@ _.
@ s -f ..%.~~:,; en
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i Zi::::er Nuclear Power Station p*l Date: May 12, 1983 gg Project No. 6020-16 W Page: 21 of 61
+ 2 2 ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) gi.-l . 3 C@ mZ - ll -
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~
SARGENT %.LUNDY , -
~'T_. __ENGINEERBd Zinner Nuclear Power Station
- Date- May 12, 1983 i 135.- Project No. 6020-16 Page: 22 of 61 130.{ -
125.-~ i 120.{
; m -
o 115.{ w - o :
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- 80. .
' f ' l ' I 'g I I I Il '
g ' l ' i'g a s i s l ' g iii g sisig - g : s ig i li a]
- TIME RFTER LOSS OF HVAC (HOURS)
Figure 10 - Auxiliary Building Zone A3C and A3D t Summer TemperaLure Transfant (
Reference:
3C6-0481-004, Rev. 1)
n- - ---- O .^
- --.SARGENT&LUNDY
*; ~
~
ENVIRONMENTAL ZONE
SUMMARY
TABLE (Re_v. 4) 90.- D M 12 19b3 Project No. 6020-16 Page: 23 of 61
- 85. -
- 80. L 75.
~
' 70.2 o -
hJ . O t 65.- w ~ a: . D ~ H a- 60. , n: - kJ - n. x: w 55.-' - 0- '
- 50. ,
- 45. ,
40.
- 35. .
i,,ig . , , , ,
,,,ig . .
i i ,ig i 100 .i.giiiig 101 102 10 3 104 TIME AFTER LOS8 OF HYRC OiSURS) Figure li - Auxiliary Building Zones A3C and A3D Winter Temperature Transien' (
Reference:
3C6-0481-004, Rev. 1) l t l
9 - . Q .; - SARGENT&LUNDY i IENGINEERS- EtWIRONMENTAL ZONU htit1 MARY TABLE (Rev. 4_)_ Zimmer Nuclear Power Station ,
._ _ _ ~~T4 6-~. Date: May 12, 1983 Project No. 6020-16 Page: 24 of 61 135.-
130.2.. 125.f . 120.I ss. : 3 o 115.2
'm
- )
110. . . cc . 4
= 105.-
na 1 0. - i C - inJ e- 100.f . 95.J - I 1 ~ S0.- 85.-'
- 80. ~ .
10 0 b 5 I IDI 102
b 103 104
. TINE RFTER LOSS HVRC (HBUR31
~~ Figure 12 - Auxiliary Building Zone ASA Summer Temperature Transient
(
Reference:
Zone AS, Calc. 3C6-0481-004, Rev. O LOOP /LOCA Condition) , I
!. --._ ,. _. m,..,_...___- . _ . -
g'
. -- /
SA ENTFdUNDY ' . c o r
~ ~ '
I E N GIN E E A S _. ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4 ) 83 . I15.- Project No. 6020-16
; Page: 25 of 61 110.
105.i 100.f . 95.2 L : O 90.2 0 :
8 a: 85.
- D -
r . C . a: 80.- na -
- 3. -
r - ta n 75.f . m 70.- e 65.- 60.
- 55. . ,,,,, ,,,,,
,,,,,3 , . , , ,iii, , 10 0 10I 102 10 10 4
- TINE RFTER LBSS HVAC (HOURS 1 Figure 13 - Auxiliary Building Zone ASA Winter Temperature Transient (Reference Zone AS, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
%d a k
~
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SAlmENTS.LUNDY . IENGINEERS ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) Zimer Nuclear Power Station. 14U*[ -
~
Date: May 12, 1983 Project No. 6020-16
- Page: 26 of 61 135.-
130.
~
125. 120.2 8 o 115. -[ - w . W m 110 5 s . cr . g 105.-
- n. -
r - w e 100. 95. 90.- 85.-
- 80. . . .
i.i. .i.i. .
,,,1 iiii; i iii;103 i.igigi,l 100 30 102 10 4 TINE RFTER LOSS HVRC (HOURS)
Figure 14 - Auxiliary Building Zone A5B Summer Temperature Transient (
Reference:
Zone A12, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
ENTTm t. UNDY u - . . - - - - -- ' I _,- IENGINEEAB E?NIRONMENTAL ZONE SUtetARY TABI.F. (Rev. 4 ) Zimmer luclea Power Station
-~ ~_[I3. -
Project No. 6020-16 _- Page: 27 of 61 110.-~ 105. 100. ss. i O 90.- cs W 85.i a a-n: 80. , w Q - x- - 75.- 70.-
- 65. ' -
60.- 55' ' g ' i ' i 'g i i 1ll g 1 i'g iii:l .ii. ii g ii. i i sig 10 10I 102 10 3 10 4 Tit 1E AFTER LOSS HVRC (HOURS) Figure l'5 - Auxiliary Building Zone ASB Winter Ternperature Transient (
Reference:
Zone Al2, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
O 4-SARGENTELUNDY - Et3VIRONMENTAL ZONF. SUFMMARY TABLE (Rev. 4) Zimner Nuclear Power St.stion
.ENGINEERB D 140. - Project No. 6020-16 hge: 28 of 61 135.-
~
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f ' l ' I'g I I I d d'' g.i.i.,,,, 100 3 10 30 4 T!rfE RFTER LOSS HVAC (HOURS) Figure 16 - Auxiliary Building /,one A6A Summer Temperature Transient (
Reference:
7one AG, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
I q) SMG T2illlNDY
.. - Z.Tgy , IENGiNEEAD ] ENVIRONMENTAL ZONE SUFJtARY TABLE (Rev. 41 z2=er "#ciear rover stattoa Date: May 12, 1983
- Project No. 6020-16 Page: 29 of 61 110.i 105.-'
100.- 95.2 O a 90. . . M 3 85.i . e- . C . g 80.-
- c. -
E . ta n 75.-^ 70.i 65.f . 60. 55. d b dd'3 10 0 101 302 TIME HFTER LBSS HVRC (HOURS) dd'I0 4 Figure 17 - Auxiliary Building Zone A6A Winter Temperature Transient (
Reference:
Zone A6, Calc. 3C6-0481-004, Rev, 0, LOOP /LOCA Condition) l
__ __ _ .. ~ - -- - - - ' - - - ~ ~ ~ ~ - ~
'" d
~- E?NIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) 8 '" t- 1 ENGINEERS ~ - D 'I 983 - 140.- Project No. 6020-16 Page: 30 of 61 135.' 130.2 . . 125.{ . 120.'
- u. -
8 115.2-S W 110. s s C". . (c 105.- w G. - X*. - w e- 100.f . 95.{ . 90.2 . es.j 80* . - g I 1 giitil g i 1 g iisil - g i i g i i sil3 g 1gi isl 10 10I 102 10 10 TINE RFTER LBSS HVRC (H00RS3 Figure 18 - Auxiliary Building Zone A6B Summer Temperature Transient (
Reference:
Zone A9, Calc. 3C6-0481-004, Rev. O, LOOP /LCCA Condition)
g SARGENTi-l. UNDY -
. ENGINEERS ENVIRONMENTAL ZONI:
SUMMARY
TABLE (Rev. 4 ) Zimmer Nuclear Power Staon I15. - s Date: May 12, 1983 . Project No. 6020-16 - Page: 31 of 61 110. 105.{ . 100. 95.- O 90.2 o : M 85.-~ D m . a: w 80.-
- n. -
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- 65. .. --
- 60. ..
- 55. . -
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.=
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3.i- - g ii g 10 101 30 2 10 10 4 TIME RFTER LOSS HVRC (HOURS) Figure 19 - Auxiliary Building Zone A6B Winter Temperature Transient (
Reference:
Zone A9, Cale. 3C 6-- 0 4 81 - 0 0 4 , Pev. O, I.OOP/1.OCA Cond i. tion)
SARG T41.UNDNl u_,, yoc1,,, P.., s to uon .
-- - --- ---- l E N GIN E E A B -
ENVIRONMENTAL ZONE SUMM7.RY TABLE (Clev . 41 Date: May 12, 1983 - 34g,. Projee: No. 6020-16 Page: 32 of 61 135. 130.f . 125.i .
~
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>= -
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i.,. iiiig . . i . i .g i s i n g 4 10 0 101 102 30 3 30 TIME RFTER LB33 HVAC (HOURS 1 t l Figure 20 - Auxiliary Building Zone A6C Summer Temperature Transient (ite f e rence : Zone A8, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
DY i Zimmer Nuclerr Pow:r Stction
~
JENGINEEASi ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. ~4) . Date: 'May 12, 1983 115. . Project No. 6020-16 ' Page: 33 of 61 110.-~ 105. 100.-~ 95.: O ' 90.1 a : M 85. m . H . CI: .
. a: 80.-
w D. - C - w s 75.2
- 3 70.i 65.i .
- 60. '
g'i'i'giiill i'I'giIIll iiiii 3 ll ie ii i:i TINE RFTER LOSS HVRC (HOURS) Figure 21 - Auxiliary Building Zone Abc Winter Temperature Transient (
Reference:
Zone AH, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
ISAR Tril. UNDY w g., JENGINEEAS- Zim er Nuclear Power Station ENVIRONMENTAL ZONE SUtiMARY TABLE (Rev. 41 Date: May 12, 1983 *
*7 -
Project No. 6020-16
- Page: 34 of 61 135.-
130.-~ 125. 120.2
- u. -
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g ' i ' I'g i i Ill ' gtigi lll
= =
gigi:l TIME RFTER L8SS HVAC (HOURS) Figure 22 - Auxiliary Building Zone A6D Summer Temperature Transient (
Reference:
Zond A10, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
-. (y .. - .. _ _ _ . . . . . .
SARHENTF2 LUNDY um,, socim, r.,, se,uon . ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) Date: ENGINEE AS _ May 12, 1983
- 115..; Project No. 6020-16
,- Page: 35 of 61 110s '
105.h 100.[ . 95.- ts. _ O 90.2 o : g e5.i 3 . c . a: 80 ta
- n. -
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- 70. .
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- 60. '
- 55. . ,
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'd 'I '
b l 30 0 d ' ' ' ' ' d ' ' ' '102 5dI8'il 10 3 10 4 103 TINE RFTER LOSS HVRC (H8URS) Figure 23 - Auxiliary Building Zone A6D Winter Temperature Transient (
Reference:
Zone A10, Calc. 3C6-0481-004, Rev.0, LOOP /LOCA Condition)
- -- 3 n .
~' '
(~-) 1ENGINEEAB. Zitmer Nuclear Power Station ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4 ) Date: May 12, 1983 - 140.- Project No. 6020-16 Page: 36 of 61 135. 130.l 125.' (Extrapolated Thermal Equilibrium) 120.- A : 8 115.' o .
~
to ~ m 110.,
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, , i- . g i i s i] 4 10 0 10I 102 303 10 T!t1E RFTER LOSS HVAC (HOURS 1 ,
Figure 24 - Auxiliary Building Zone A7A and A7B Summer Temperature Transient (
Reference:
Zone A7, Calc. 3C6-0481-004, Rev. O, LOOP /LOCA Condition)
. -- . gr%, .. , - --,3- - - - - - - - ~ ~ - - - -~~ -- ~~
%/ _
SARGENTil. UNDY umer no1cear Pomer stat,,,n
.._ .. - EN GIN EERS _ bN TAI. ZOW. SMA,RJ TABI,E (Pev. $ Date: May 12, 1983 ~
~
l15.- " Project No. 6020-16 Page: 37 of 61 110.f . 105. 100. 95.- -
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8 90.2 o. W a: 3
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CI: - o: 80.- w - G - x: w t-75.f 70.f . 65.f _ i 60.-
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i . i .g ivig i .i. i i ii; i.i. i i ii; i.. i i ii; 10 101 10 10 10 TINE RFTER LOSS HVRC (HOURS) Figure 25 - Auxiliary Building Zone A7As and A7n Winter Temperature Transient 4 (
Reference:
Zone A7, Calc. 3C6-04D]-004, Rev. O, I.OOP/LOCA Condition)
I Zinner Nuclear Power Station
. SARGENT&LUNDY ,
i oate: nay 12, 1983 Project No. 6020-16
' E N GIN E E R S.J Page: 38 of 61 ENVIROL".1:!'TA ., ZONE SUMM. 3Y TABLE (Rev. 4)
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Figure 26 - Pressure / Temperature Response for High Energy Line ,
- Break (HELB) in Horizontal ( Auxiliary Building) Main Stean Tunnel
I 1 l
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~ ' ~
I Zim er Nuclear Power Station
-SARGENT&LUNDY L,
@;c,"g,2;,1383 L___ . 1ENGINEERSw! Page: 39 of 61
, ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4 ) e+ .,;, . ; . 1 -- .- .- ' ;m,,, , ; , ; v i . . _m.
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k Figure 27 - Pressure / Temperature Response for High Energy Line Break (HELB) in Vertical (Reactor Building) Main Steam Tunnel I W h _m..
i 4 . ..... ~... . . - . . . - - T8.LUNDY ;i O' O. .. l iSARG ~ J _^.! ~ ^~~--~ ~ ~~-]ENGINEERsL Zimmer Nuclear Power Station l , ENVIRONMENTAL ZONE StL*1MXRY TABLE (Fev. '4 ) Date: May 12, 1983 , Project No. 6020-16 l Page: 40 of 61 l l' t i i , t ! l' I i r i FIGURE 28 WILL BE PROVIDED LATER i I i-i I i 1 1 Figure 28 - Primary Containment Zones C1 and C2 Temperature Response l k I 1
L SAR NT hLUNDY 1 a . O.
- . .._ ~ ~ " ~ ~~ ~_)ENGINEE AB . 3 mr ear mer Statirn. ~ '
' ENVIliONMENTAL ZONE fiUMf1Mif TABLE ( het' . 4 Date: May 12, 1983 ;
- Project No. 6020 !
l. Page : 41.of 61 , i' i l i t i FIGURE 29 WILL BE PROVIDED LATER j i , 1 4 4 1 I ' Figure 29 - Primary Containment Zones C1 and C2 Pressure Response i i ; i . 1 : 1 _ ..
_ , s ._ _ _ . . . . ._ . n ZittnrNucicarP:wcrSk,Icn p I - -~ ~ - ~ ~ (.j '
~ ~ ~ -
s - SARGENTi. l. UNDY Date: May 12, 1983 , Project No. 6020-16 L _..__ __. _ .__ EN GIN E E A By ENVIRONMENTAL _3ONE
SUMMARY
TABLU (Rev. 4) Page: 42 of 61 ei i i . . . i IN $R CT13F Y Ikbib biJ'hbEf: dkMh~~Ib]i -" - l l l hMrd-WI I bj. h.._,...uG 81j _ u,,m
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Figure 30 - Reactor Building Zones Rl-R7 Summer Temperature Transient (
Reference:
Calc. 3C6-0681-002, Rev. O, LOOP /LOCA condition)
. ,f3, p) l
,V 7.immer Nucl a r Powxr S i lisn ,
SAR NT e LUNDY m e: nav 12, usa JENGINEEAS - ENVIRONMENTAL ZONE
SUMMARY
TAllLE (IMv . 4) Project No. 6020-16 . i, i. t., i . :, .,
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b fi. !
\ .[. tli . -
.I.
l_ . __ .. _ ^__ . ' } '.__ _' i. 17-- 4-p fII. N ' '
.g ,
, i # . -
~_.___ ,'
m l l
~T
.ip . * . ..; M ee i
;! .I 16- il 4 t
l l 11 It- l
! ;. I ...
.. ^ ] ' -{-y~~~-
l
._l . .. . ._. . ..-... . _-- ~ . . . .. -- *~-
+
[ l ., 8 3 4 t i:t ,1 !i i; t
- 3) 2 . 0083 '4 0083 . G . 0083 0 . 0083 .
l . 0 01:7 i . 2 01:7 I .4Dd 1 60E7 lI! j- 'g I l- I l- 1 l 'I !!! ! ii!- ' I T__T li. .fj :+ l $. .C.S. . )4- . . _ _ ._ .. - - - 3.t. H- -
. r-- + ,
!+h-i Figure 31 - Reactor Iluilding Zones R3-R7 Winter Temperature Transient
(
Reference:
Calc. 3C6-0681-002, Rev. O, Loop /LOCA condition)
3 () NJ , r Zimmer Nuclear Power Station _ ! _.."~ . i_Z . __ EN GIN EMROWENTAL EE A 8]fZONC SUMARY TABLE (RW. 4) Date: May 12, 1983 - Project No. 6020-16 Pagt: 44 of 61 7 , i _
} .
- j. ,
.q . . _ _ ..
~ ~ ~ ~ ~
a ! ~~_ _ _ 33 -.-_ __ _ l
~
]
g . .. _
}
O(}, ,_. - ._ ___ _ ._ ____ _.___ _._ __ ___
+ _q._ .
q_ .N
' ~ ~ ~
/ .g i c
_ ___ . . ._ .. ____ _ _ _ .J. ..
/ __
I, ~-. . _ .; [,_ -, r.
/ _ . . _. . . _ . .
[. ; ... . - .. d---- 6 02 ~ D ~1--
^ ~ ~ ~ ~ ~ ~
,- / 1 4
9 .
/ . .
- ~
.p !.j.'.. _ J
.3 s
____) p_._ ..._._.- ] _1____._i._.. .Lh /
~
_.___~.
~
1_
~~ ~ ~
~.{.
3 . y .. .
~
'f, g____a .Q. s ., ,
,_ - % n g
d:3 *
~ - - ~
~
~
- ~
~. t l
a.._._. _ _ _ _ ._ _ . _ _ . _ - _
._4- . .
_I a ..__.. ... __.__...
. . .a 4.
y . _ e - w . 5 (__ t - { Q{. t
- j. . .
~ ~ ~
_. . _ 27. 1 I' -
~
~
b _
'j fi
~
,,, ... l.
}.' h :.ll'Ih - I
,' l'I lil '
l' I' Il l l Ill I .l l l
l 'I' 4. ' II
_l ',l 'hl i . - Q } -H- Ei
~ ~ ~
}1 10 I T 1[tj,S.IjEg( t,lg l_j~__ 7_ ] ; - -
Figure 32 - Reactor Building Zones Rl-R7 Summer liumidity Transi.ent (
Reference:
Calc. 3C6-0681-002, Rev. 1, LOOP /LOCA Condition) l
r~N g () / (g] s l SARGENT5LUNDY i . u-er nemt r-r stou-
'- - - - - -- -- ' E N ,G IN E3" A B ~~- I ' * "E** OY ' -
Project No. 6020-16 Page: 45 of 61 r 7, p -- 7 ;
- --- ------~
ll1 I-l ;! .: f.1 I. 7 , 4 , , ,, l
. 1. si :
- I 1 j-s' !- i*-- 4 I -
.}. !
.. .L.
00
, _ lI .: 4 I
- t. lL 1 - -
63
*- +t- -
;.fIa'M1 N j.
, 3 ,'
4 i
, l. *:.
"T+----
#4 [44 1 4
~
4
;j-t
;_[_1 *.'. }_}_I H_j ' _.._ ._.. .. _ . - - - - -'-' ----- - --- --- --- ^-~---- - -'-
.t l lili [4 1l l
/
- -" -- ~ s N b'
- ~ ~l~
i i^ p .
;3 d i, r
. ,3 80- r - ------- --- - --- --- -- --- -
i w c .
- r. . t l 3 . j . . _. .-
~
- . .._.. _ .,_ ___,. _ __ / . . . _.. ._...-- - . .. _ . . - - - . -- - - - - - - - - - - -.- - - - - ----
I[e 4 l 4 (l l* !
.i .l
, a____
gg g . r_ . f t: l 1_ 1,l ?. .1
. .f.
l i 1-- - ~ - ~}~ i_._ l _ . . _ . . _ l _.~ l' . __ ___
.___.__} __. . ..__. . .___ . ..__._._ _l._1 ..____ __ __ . . . .___ _-_.. ..___._ -._.-_ .. -____ . - -- ----- - - - ..J- - ---
; . s -
^
g____49 . ,-- ----
)
'~'
a .
.. l _ . . _ _ . --
p
- j d' d l
j g-f g g . ,__
~
'{ -
4
; j ' I' . - -
I i 8 - - 3 I k_ _.... f_4 ___.__._.I 4 - ___24 a - - - .- - - --- - ----- ----
- ,-[ ' N~- '--
i it* I 4) ., - t : - .l ;: p s i { ll' 1 j,1, t .-
^l'
-ij t
. s - -
f til ll;.' fl'l.'l'gii I'I' i'l ' L i 'j if I
.h L l hI l 1 (( j' l ' 3 i;I LI 11l : . ' l.'f'I l.13 'd If l
([ 7 ' i,10
' 2 1 ) 1 D**.1 ;
l '10P! 'i i.. 10 ,1 ..
.M :_ _x_..
t ~ ~ _ _ qa,91. E_ ![ L4_.i.n..:r.a i -.
-t 'r;
.a 1
. ~ E_q1 a. h c,E,.
t t.RNS.If.H.T.d,[
.. . FOn UR yIZ
~ -
---..-c----, -
,i Figure 33 - Reactor Building Zones Rl-R7 Winter liumidity Transient
(
Reference:
Calc. 3C6-06H1-002, Rev. 1, LOOP /LOCA Condition)
~~ ~~ ~~~
i Zim er Nucicar Pow:r L v; ion c (3 SAR T 9.LUNDY one: nay 12, 1983 _-~] EN GI N E E A B Project No. 6020-16 E!NIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) Page: 46 of 61 ~ 300 PUMP CUBICLE, N, EL. 546'-0" - "* ~ HEAT EXCIIANGER ROOH, EL. 570'-6" ) **Use for Zone Rl**
. MAIN FLOOR, EL. 546'-0" -------
FLOOR, EL. 570'-6"
~" ~ PUMP CUBICLE, S. EL. 54'6'-0" HEAT EXCIIANGER CONTROL VALVE ROOM, EL. 593'-6" l
i, i 200 . ZONE EI **" f ...---- y "~ ~
/
/. /
;c g
/
/
/
/- ..........
B .
/... ,/
/ ,. ...-
+
!! .. / ,. /
100 -
~ ... . ___ g ';-----.._..... ...
. .s . ..
i ,I i a l l I I I I I IlI I I l l I t t I t l l l t l 3 3 l g l, j g~ 2x10-2 10-1 10 0 1 1 l 10 5x10 l TIME (SEC) , Figure 34 - Reactor Building Zone R1, IIELB Temperature Transient (
Reference:
Calc. MAD 74-764, Case 2)
s
}
Zicantr Nuclesr Pow r Stab Jn .
- SARG T *l. I LUNUIa s ma nu Date: May 12, 1983
~
"~~7 ENGIN EE AB _
Proj ect No. 6020-16 ~ Page: 47 of 61 ~ ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) 28 . PUMP CUBICLE, N, EL. 546'-0" - - - HEAT EXCHANGER ROOM, EL. 570'-6"
- **Use for Zone Rl**
i - . MAIN FLOOR. Ei.. ".46'-0" ------ FLOOR, EL. 570'-6" l' 24 _,, _ .. _ PUMP CUBICLE, S, EL 546'-0" _ IIEAT EXCHANCER CONTROL VALVE. ROOM, EL. 593'-6" m
'dm b 20 _
%
- ME 84 1d 8
m d p.
~
+ , , . -. . - - - .' ' ^ T _7,,% y e *** % *== % ,
... 5 ,Y ~~
. _ . _ _ , _ _n 'v. , ., ,,, s , .-a *
- W adA* e *-a * ** *
- S **3
., - - ^ - I t I l i Ii11 I I I I I I I I l- 1 I I t i t iit i I I f I IIi
! 12 l0 10-2 10 0 10 1 10~I
) TIME (SEC) j
, Pigure 35 - Reactor Building Zone R1, ilELB Pressure Transient l
I (
Reference:
Calc. MAD 74-764, Case 2) i
i SAITBENTPdLUNDY $ E"FEa*i'2P1VM""' L-- 1emoimeensc i ENVIRONMENTAL ZONE
SUMMARY
TABLE ~ (Rev. 4) Project No. 6020-16 Page: ~ 48 of 61 300 I FLOOR, NE, EL. 475'-6" _ ... _ FIDOR, SE, EL. 475'-6"
**Use for Zones R4A, R4B & R4Fe* **Use for Zone R4C**
_._ FLOOR NW, EL. 475'-6'd __ .__ FLOOR, EL. 503'-6"
, **Use for Zone R4E** -
- 250 4 - * * ~
FLOOR SW, EL. 475'-6" -~~ FLOOR,'EL. 525'-7" 2'
, *
- Use for Zone R4D*
- o"
. sa ~ s g* ,. y
.:s=.
. . m ..:-m
) p., 2 7 , 7-ONE R4Dy ,
. 2
- o' s~~
, y. ras .-
7 150 - (
*/ r.ax/
AAK k_ fortET FM,R4 6
- j j
i
- . nw . ,
. /
f
* /
/..- ... '
/
, ,* s . / -- - - -
100 I I I I I IllI I I I ' ! t t t I t i I I t t I t t t i 1 1 I 0 10 1 h10 I 10' ! 10-1 10 TIME (SEC) Figure 36 - Reactor Building Zone R4,IIELB Temperatu re Transient (
Reference:
Calc. MAD 74-764, Case 1) J t
i l - A _. _.- f^
\
j U Zimmar Nuc1 car Powar b dtien* SARGENT,nLUNDY nate: nay 12, 1983 .
~
l .ENGINEE AS _ Page. 49 of 61 e i ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) 18 . FIDOR, NE, EL. 475'-6" _ , , , FLOOR,.SE, EL.475'-6"
* *Use for Zone R4C*
- 1
* *Use for Zones R4 A, R4B & R4F**
^ _ , _ FLOOR, NW, EL. 475'-6" ,,_,,, FLOGR, EL. 503'-6" 17 - * *Use for Zone R4 E* * , 1
.. _,FLO0E, SW, EL. 475'-6" FLOOR, EL. 525'-7"
**Use for Zone R4D**
e* -,*s'
/- '-
svs 16
- n.
e* 7.anf $4D l -
~
$15
~' N
.) 7''"'e h' % *'*2 %> ~ ~g l.
' - ~ . .
, # . a_
. .se .,,,_,/ . '
J I I I I IIII l i i 1 I i j 14 I I I I I I III I I I I I I I11 1 1 10-2 100 101 7 x 10 10-1 i 4 TIME (SEC) 1 Figure 37 - Reactor Building Zone R4, IIELB Pressure Transient
; (
Reference:
Calc. MAD 74-764, Case 1) 1
e o c) SARGENT&LUNDY : *%F "Ma"*T2" Tbi"" * ~.
-"-~:- JENGINEEABL Project No. 6020-16 Page:
50 of 61 - ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) 300 PUHP CUBICLE, E.,EL. 546'-0" -- . FLOOR, EL. 570'-6"
. - - PUMP CUBICLE, N , EL. 546'-0" HEAT EXCHANGER CONTROL VALVE ROOM,
..- HEAT EXCHANGER ROOM, EL. 570'-6"
- , ** Use for Zone R5**
l 250 - C ff ' Avtwrr;= m b 200 z.s,e)../.
./ .
?
150 - -
'/ . .
.* ,. /... -
/ /
/ . ..'
... / ... .--
~ ' /.._,sy....... .. _ , . _
! 100 "
, . "r . i .7 . . . > > > . . . e a = = * ' ' ' '
0 1 4x10 10-2 10-1 10 10 TIME (SEC) Figure 38 - Reactor Building Zone RS, llELB Temperature Transient (
Reference:
Calc. MAD 74-764, Case 1)
r i! SARutNT41.UND,Y ! o'_ ""' . i __J EN GIN EE A S J
*U' *l$"i2"~i?S Project No. 6020-16
, i Page~ 51 of 61 j ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) i i l l 25 PUMP CUBICLE, E, EL. 546'-0" _ . . . FLOOR, EL. 570'-6" IIEAT EXCHANGER CONTROL VALVE ROOH,
-- PUMP CUBICLE, N, EL. 546'-0" ......
^ EL. 593'-6" 20
~**~
IIEAT EXCIIANCER ROOH, EL. 570'-6" h _
** Use for Zone R5**
g h
- z. ar e
g .a .
- - . .f ,p. . . - . . r.2
. _ . r. .= -----
=. . q . .. ._..
~ 15 _ _ ....../ - ... . _ . 3 r_p. .;_
. ., . .;w
. . _ _ _ 'm_-
10 i i i iieil i i i eiisi i , , , , , , , , , , 1
', 10-2 10-1 - 10 0 10 1 4 x 10 TIME (SEC)
Figure 39 - Reactor Building Zone RS, ilELB Pressure Transient (
Reference:
Calc. MAD 74-764, Case 1)
o SALJENTMUNDY O zi-- r r--Que
" ate: nay 12, 1983 -
Project No. 6020-16
. ___ ENGIN EE AB - ENVIRONMENTAL ZONE
SUMMARY
TABLE -(Rev. 4) , Page: 1 52 of 61 - 300
- PUMP CUBICLE, N, EL. 546'-0" - * *
- HEAT EXCHANGER CONTROL VALVE R00H, i
i EL. 593'-6"
~ * - MAIN FLOOR EL. 54'6'-0" ** Use for Zone R6C**
- - - {Ip0R, W. WL. 593'-6" Use for Zones R6A, R6B & R7**
! 250 - ~** ~ HEAT EXCHANGER POOH, EL. 570'-6".
, C
.; e, g
- e. ' '
200
..+----'.*T*{' .N ,
,,. ,F*
r
/ ~
/
"h ..' -
1 z., / -l i / -
- f6c .* -
z.~.,
/
- 150 -
/ / RCA,fi$ f
. 4 er / .. , -
j
/ / -
/ ,
1 -- ....M*- ._ . = - _ _ . - # ,f.. 100 I i 'l - 1 I l' 1IIII ' I I i l i I I ll 1 1 I I I I I II I I I I I I II 1 10-2 10-1 10" 102 101 TIME (SEC) i ' Pigure 40 - Reactor Building Zones R6 and R7, IIELB Temperature Transient (
Reference:
Calc. MAD 74-764, Case 4)
=
o 4 SARGENT&LUNDY p! , m O .. _~ '!;";" "iay T2, IY8f*" " O .. j IENGINEEASb Project No. 6020-16
- ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) . Page: 53 of 61 l 20 PUMP CUBICLE, N, EL. 546'-0" '
-...- HEAT EXCHANGER CONTROL VALVE ROOM, ,
EL. 593'-6"
-. - MAIN FLOOR EL. 546e-0u --
Use for Zone R6C** FLOOR, W , EL. 593'-6"
** Use for Zones R6A, R6B, R7**
- j. 18 -
-.. - !! EAT EXCl! ANGER ROOM, EL. 570'-6" i
m
$ ZONE $6C
=
16 - L,..~...... y .. p .. - N * .,
......,..p.*,---+-
y *,/ '. y
.. - - .-...%_~..,
14 - _ .._-.-.- -- . - ~. . .
.g XONES ACh f68f $7 ., '
=**"
V 12 I I I I lI' l ' 8 I I I I I I III ' ' ' ' ' I t t t t itf 10-2 10-1 0 10 10 1 10 2 TIME (SEC) 9,t s.2 3 u , , Figure 41 - Reactor Building Zones R6 and R7, liELB Temperattere Transient (
Reference:
Calc. MAD 74-764, Case 4) I
i O O O..- Ziimnzr Nuclear Power Statica
. 220.- ENVIRONMENTAL ZONE
SUMMARY
TABLE - (Rev.' 4 ) Date: May 12, 1983 .~ Project No. 6020-16 Page: 54 of 61 _r L o g 200. d\
-a o n E -
- . R 180.# '
c - e U . 11 . n w
\
. ] s
;-j 160.-
z . , z
- a -
t-z C -
~
140.- 2 M . l z -
- - = .
m .
^ ^ ^
z - - * . . , , , , ,, s. 120.- t i . l m i
>g .
Q 133 2E 3- [ aj 100.- . . . . ,....,....,.... ...,, ........ .... .... ....i efj tu D. 240. '480. "120 . 960. 1200. 1440. 1680. 1920. 2160. 2400. H tit 1E RPTER LOS3 OF HVRC (HOUlt31 2 Pigure 4 2 - Main Steam Tunnel Zone T-1, Sununer Temperature Transient
- g (Refe rence : Calc. 3C6-0481-005, Rev. 1, LOOP /LOCA Condition) 4 en I.
~
o o O. Zimm2r Nuclesr Pow r St tien 180.- ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev.' 4)_ Date: May 12, 1983 ~
- rroject no. 6020-16 .
Page: 55.of 61 b l ' 140.m o . w o a t t
=w ,
w a: - D .' s 120.J ' e g - w m i c - - . m H 4 .6 a d 10,0 . -
- z .
z 3 - W 1, - c (C - w s 80.- M .
=
e _1 . 1 z _
-s.
j: i 60.- gn
. >= tr .
1 g2 m m - 2 2 -
=3 5 40 ....i....i....i i... i
- '2 . . . . .....,....i.... ....
1200. 1440. 1680. 1920. 2160. 2400. ! M3 W 0. 240. 480. 720. 960 I h TINE AFTER LOSS OF HVRC (HOURS)
- 2 Figure 43 - Main Steam Tunnel Zone T-1, Winter Temperature Transient
(
Reference:
Calc. 3C6-0481-005, Rev. O, LOOP /LOCA Condition) l
' i, en
'l
. , , , - - - - - - - - - , - , - , - - - - - - - - - ~ - - - - , - - - - - - - - - - , - - - , - , , , - - , - - - - - - - - - - - , -
O g O O - 100.- "
~
ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) D My1 , 19 3 . Project No. 6020-16 Page: 56 of 61 i 90 7
- e. -
N - _ 80.- i w : H . o
- *] O . -
n - D - 4 I . ) " 60.f ., n - e . J . W 50.- a: _J w - z - i z 40.- o . l t~ . es m - w 30.- e-- - us - z h
] E u
- 20. t h
1 .V W .
>= E 10.-
Qm m - 2 2 - D j;j J 0*- ' ' ' ''''''''''''''''''''''''''''''''''''''''' 2 , gj m O '. 240. 480. 720. 960. 1200. 1440. 1680. 1920. 2160.- 2400. h= T!nt RPTER LO33 0F HVRC (HOURS) 2 , w Figure 44 - Main Steam Tunnel Zone T-1, Summer Relative Humidity Transient (f) (
Reference:
Calc. 3C6-0481-005, Rev. 1, LOOP /LOCA Condition) CC i CC
- 'l (n .
1
O O O _ ENVIRONMENTAL ZONE
SUMMARY
TABLE (Rev. 4) mer uc ear Power Station
- 100.. -
Date: May 12, 1983 - Project No. 6020-16
- Pege: 57 of 61 90.5 ,
M. - M -
~
80.- e-- - o -
- 70.-
c - D - x .
~
~
60.- - a w \ - c - s . W 50.- o: 1 g . z - z 40.- a . c - 1 e - w 30.-o
- m -
t z : l 3 G 20.-
- n p -
i > m t ! >= E 1 0 . 4-cm - zi : D5 a 0. 2 gj m O.* 240. 480. 720, 960. 1200. 1440. 1680. 1920. 2160. 2400. F= TIME RFTER LOSS OF HVRC (HOURS) E ua g Figure 45 - Main Steam Tunnel Zone T-1, Winter Relative Ilumidity Transient g (
Reference:
Calc. 3C6-0481-005, Rev. 1, LOOP /LOCA Condition) 4
,. u) ,
O O - b_NTal. UNDY zi===r nucl=r ro er sectiea Date: May 12, 1983
+
--] EN GIN EE R B " Project No. 6020-16 Page: 58 of 61 .
ENVIRONEMNTAL ZONE
SUMMARY
TABLE (Rev. 4) LIST OF REFEPENCE: Resoonsible S&L Reference Revision Title Division Section DC-A51-15-1 3 Diesel generator room vent. IIVAC NA DC-A51-15-3 3 Ess. switchgear room heat removal llVAC NA DC-A51-15-4 2 Service water pump house IIVAC HVAC NA . DC-A51-15-5 3 CSCS equipment area coolers llVAC NA DC-A51-15-6 2 Turb. building vent , ilVAC NA DC-A51-15-7 3 Control Room IIVAC IIVAC NA DC-A51-15-8 3 Drywell cooling IIVAC NA l DC-A51-15-10 2 Radwaste building vent. ilVAC NA
! DC-A51-15-ll 2 Reactor building vent. IIVAC NA DC-A51-15-15 -
Laboratory IIVAC IIVAC NA VC-01 5-23-75 Con trol room IIVAC llVAC NA
- VD-01 0 Duct pressure drops for DG room IIVAC NA VX-01 0 Switchgear heat removal system IIVAC NA VX-02 0 Energy calculations for accident and ilVAC NA LOEP conditions MAD 74-764 4-7-75 Environmental study for llELB outside the MAD NA primary containment 21 -EO-Al 0 Zone Al, Equipment Qualification Radiation NSLD S&RS*
l Exposure Zl-EQ-A2 0 Zone A2, Equipment Qualification Radiation NSLD S&RS Exposure
- Shielding and Radiological Safety
SAR ENT&LUNDY o O ' L R;a;' "g"If,o"g0i=t'a S s IENGINEERS Project No. 6020-16 - Page: 59 of 61 ENVIRONEMNTAL ZONE
SUMMARY
TABLE (Rev. 4 ) LIST OF REFERENCES Responsible S&L Reference Revision Title Division Section _ Z1-EQ-A3A 0 Zone A3A, Equipment Qualification Radiation NSLD S&RS* Exposure Zl-EQ-A3B 0 Zone A3B, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EO-A4 0 Zone A4, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-ASA 0 Zone ASA, Equipment Qualifica' tion Radiation NSLD S&RS Exposure Zl-EQ-A5B 0 Zone A5B, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EO-A6A 0 Zone A6A, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-A6B 0 Zone A6B, Equipment Qualification Radiation NSLD .S&RS Exposure Zl-EQ-A6C 0 Zone A6C, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-A7 0 Zone A7, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-A7C 0 Zone A7C, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-Cl 0 Zones C1 & C2 Equipment Qualification NSLD S&RS Radiation Exposure Zl-EQ-C3 0 Zones Cl & C2 Coatings Qualification NSLD S&RS Radiation Expocure Zl-EQ-DIA 0 Zone DlA, Equipment Qualification Radiation NSLD S&RS Exposure
- Shielding and Radiological Safety
pJ s SABGENT&LUNDY Z1 ;r uocier P-er sescien ' IENGINEERB _ Date: May 12, 1983 , Project No. 6020-16 , Pane: 60 of 61 ENVIRONEMNTAL ZONE
SUMMARY
TABLE (Rev. 4) LIST OF REFERENCES Responsible S&L Reference Revision Title Division Section Zl-EQ-DlB 0 Zone DlB, Equipment Qualification Radiation NSLD S&RS Exposure
.Zl-EQ-RlA 0 Zone RlA, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-RIB 0 Zone RlB, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-Ric 0 Zone RlC, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-R2 0 Zone R2, Equi t eent Qualification Radiation NSLD S&RS Exposure Zl-EQ-R3 0 Zone R3, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-R4 0 Zone R4, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-R5 0 Zone RS, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-RS-1 0 Zones RSA, B, C Equipment Qualification NSLD S&RS Radiation Exposure Zl-EQ-RS-2 0 Zone R5D, Equipment Qualification Radiation NSLD
- S&RS Exposure Zl-EQ-R6A 0 Zone R6A, Equipment Qualification Radiation NSLD S&RS Exposure .
Zl-EQ-R6B 0 Zone R6B, Equipment Qualification Radiation NSLD S&RS i Exposure Zl-EQ-R6C 0 Zone R6C, Equipment Qualification Radiation NSLD S&RS Exposure Zl-EQ-R7 0 Zone R7, Equipment Qualification Radiation NSLD S&RS Exposure
~
O O O . Zirs sr Nuclear Power St:tica ' d Date: May 12, 1983 . Project No. 6020-16 ' - Page: 61 of 61 FINAL PAGE ' ENVIRONEMNTAL ZONE
SUMMARY
TABLE (Rev. 4) LIST OF REFERENCES Responsible S&L Reference Revision Title Division Section Zl-EQ-T1 0 Zone T1, Equipment Qualification Radiation NSLD S & RS
- Exposure Zl-EO-S1 0 Zone S1, Equipment Qualification Radiation NSLD S&RS
- 3 Exposure 3C6-ll73-001 0 Pressure and Temperature Transient Analysis NSLD Safeguards.
for HELB Outside the Primary Containment Systems 3C6-0481-004 2 Auxiliary Building Environmental' Conditions NSLD Safeguards j Due to Loss of HVAC Systems j 3C6-0481-005 1 Main Steam Tunnel Environmental Conditions NSLD Safeguards Due to Loss of INAC Systems y 3C6-0681-002 1 Reactor Building Long-term Temperature NSLD Safeguards Transient Systems Zl-EQ-12 0 Equipment Qualification Dose to D.A..M. Units NSLD S&RS l4 Shielding and Radiological Safety i - - - - - - - -
3 4 PROJECT NUMBER 4130-OS DATE 22 DEC 83 REVISION 010
- . ZIDMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/AOD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET AP 1AP15EA 480V RXMCC 1A ITE SERIES 5600 H-2158 E-144-1 E/28 R3A R.B. A 2A 5 MINUTES APO1 I . E-1565/1571 503 AP 1AP15EB 480V RXMCC 1B ITE SERIES 5600 H-2158 E-146-1 F/26 R2A R.B. A 2A 5 MINUTES APO2
. E-1575/1580 525 AP 1AP50EA ELECT,11 CAL CONAX CANNISTER H-2167 E-145-1 115 DEG. C1 R.B. P 28 APO3
. PENET. E-1 CORP. E-2727/2729 525 AP 1AP50EB ELECTRICAL CONAX CANNISTER H-2167 E-145-1 120 DEG. C1 R.B. P 28 APO3
. PENET. E-2 CORP. E-2757/2759 525 AP 1AP50EC ELECTRICAL CONAX CANN1 STER H-2167 E-145-1 130 DEG C1 R.B. P 28 %PO3
. PENET. E-4 CORP. E-2769/2772 525 AP 1APSUED ELECTRICAL CONAX CANNISTER H-2167 E-145-1 135 DEG. Cf R.B. P 28 APO3
. PENET. E-5 CORP. E-2741/48/96 525 AP 1AP50EE ELECTRICAL CONAX CANNISTER H-2167 E-145-1 155 DEG. Cl R.B. P 28 APO3
. PENET. E-6 CORP. E-2760/2762 525 AP 1AP50EF ELECTRICAL CONAX CANNISTER H-2167 E-145-1 165 DEG. C1 R.B. P 28 APO3
. PENET. E-8 CORP. E-2733/2736 525 AP 1AP50EG ELECTRICAL CONAX CANNISTER H-2167 E-145-t 222 DEG. C1 R.B. P 28 APO3
. PENET. E-9 CORP. E-2763/2765 525 AP 1AF50EH ELECTRICAL CONAX CANNISTER H-2167 E-145-1 229 DEG. C1 R.S. P 28 APO3
. PENET. E-10 CORP. E-2773/2776 525 AP 1APSOEJ ELECTRICAL CONAX CANNISTER H-2167 E-145-1 241 DEG. C1 R.B. P 28 APO3
. PENET. E-12 CORP. E-2737/2740 525 AP 1AP50EK ELECTRICAL CONAX CANNISTER H-2167 E-145-1 247 DEG. C1 R.B. P 28 APO3
. PENET. E-13 CORP. E-2766/2768 525 I AP 1AP50EL ELECTRICAL CONAX CANNISTER H-2167 E-145-1 259 DEG. C1 R.B. P 28 APO3 i
i
. PENET. E-15 CORP. E-2749/55/97 525
! AP 1AP50EM ELECTRICAL CONAX CANNISTER H-2167 E-145-1 265 DEG. C1 R.B. P 28 APO3
. PENET. E-16 CORP. E-2730/2732 525 J
AP 1AP50EN ELECTRICAL CONAX CANNISTER H-2167 E-146-1 277 DEG. C1 R.B. P 28 APO3
. PENET. E-17 CORP. E-2778/2780 525 PAGE 1 0F 76 O
M (9 ) SARGENT&LUNDY
, - ' PROJECT NUMBER 4130-05 DATE 22 DEC 83
+
PLANT 10 ZIMMER EQUIPMENT QUALIFICATION 001326 REVISION 01C COMPONENT / MODEL SPFC OR
*SY NUMBER EQUIPMENT E.I. DWG COL / ROW CONTAIN
.........===.....,=.......===.. .
MF NUMBER 8/M NO. W/0 N FLD ACT/A00 0588 DATA
- ELEVATN ...
...R................................O...===......... IN OUT SUILD LEV PAS REV CAT.
AP 1AP50EP ELFCTRICAL CONAX CANNISTER H-2167 E-147-1
. . ===.===...........S. ===......=====.=..==. SHEET
===.
PENET. E-18 CORP. 117 DEG. C1 R.8. P 28 E-2726 546 APO3 AP 1AP50ER ELECTRICAL CCNAX CANNISTER H-2167 E-147-1 PENET. E-19 CORP. 249 OEG. C1 R.8. P 28 . E-2726 546 APO3 AP 1AP50ES ELECTRICAL CON 4X CANNISTER H-2167 E-145-1 PENET. E-3 CORP. 125 DEG. C1 R.8. P 28 E-2726 525 APO3 AP 1APSOET ELECTRICAL CONAX CANNISTER H-2167 E-145-1 PENET. E-11 CORP. 235 DEG. C1 R.8. P 28 E-2726 525 APO3 AP 1APSOEU ELECTRICAL CONAX CANNISTER H-2167 E-145-1 PENET. E-14 CORP. 253 DEG. C1 R.8. P 28 E-2726 525 APO3 CA 0001 NED. VOLT. KERITE H-2160A R8 POWER R.B. 2A CA01 CA 0002 LOW VOLT. OKO-POWER H-21608 C1 R.8. NITE 24 CA02
- CA 0003 LOW VOLT. ANA-1 H-21608 POWER CONDA C1 R.B. 2A C403 CA 0004 CONTROL OKO-
. H-2161 C1 NITE R.8. 2A CAO4
- CA 0005 CONTROL ANA-
+ H-21G1 C1 CONDA R.8. 2A CAO5 CA 0006 CONTROL RBESTO H-2161 C1 R.8. 2A CA06 CA 0007 INSTRUMEN- SAMUEL TATION H-2162 C1 R.8. MOORE 2A CAO7 i CA 0008 INSTRUMEN- RAY-TATION H-2162 C1 ] . CHEM R.B. 2A CAOS CA 0009 INSTRUMEN- RBESTO TATION H-2162 C1 R.8. T CAO9 CA 0010 INSTRUMEN- BOSTON TATION H-2162 C1 WIRE R.8. 2A CAto
.PAGE 2 0F 76 e
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, ENOONESRn ,
r - __
5 t PROJCCT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT CUALIFICATION 001326
- PLANT 10 COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/AOD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/0 NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e..............................,................................................................ ... .... ... . ................
CA 0012 SPLICE-KIT KERITE H-2173 C1 R.B. 2A CA12 CA 0013 SPLICE-KIT OKO- H-2173 C1 R.B. 2A CA13
. "JI T E CA 0014 SPIICE-KIT RAY- WCSF-N H-2173 C1 R.B. 2A CA14
. CHEM CA 0015 TERMINAL G.E. CR151D H-2173 R2A R.B. 2A CA15
. BLOCK CA 0016 TERMINAL MARA- 6000 H-2173 R2A R.B. 2A CA16
. BLOCK THON CA 0017 TERMINAL KULKA 7TB-12 H-2173 C1 R.B. 2A CA17 BLOCK CA 0018 TERMINAL BUCH- CAT NO 824 H-2173 R2A R.8. 2A CA18 ELOCK ANAN CM 1CMOO3 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/t8 R3A R.B. N/A A 2A M-81-1 CM01
. OPEN POS. 46302 E-3918 503 CM 1CMOO3 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01
. CLOSED POS. 46302 E-3918 503 CM 1CMOO3 SOLEN 3ID ASCO HTX8320A22V H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO3 E-3918 503 CM LMOO4 SOLENOID ASCO HTX8320A22V H-2852 E-143 B/18 R3A R.B. N/A A 2A M-91-1 CMO3 E-3918 503 CM 1CMOO4 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01 OPEN POS. 46302 E-3918 503 CM 1CMOO4 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01 CLOSED POS. 46302 E-3918 503 CM 1CMOO5 LIMIT SWITCH NAMCO EA-170 H-2852 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMO2 CLOSED POS. 46302 E-3918 525 CM 1CMOOL SOLENOID ASCO HTX8320A22V H-2852 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMO4
. E-3918 525 PAGE 3 0F 76 co o
m m SARGENT&LUNDY ENGINEEPB -
t PROJECT NUMBER 4130-05 DATE 22 DEC 83
- REVISION 010 ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 OATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATH IN OUT BUILD LEV PAS $ REV CAT. SHEET e..........=................... ...........=....................................=............... ... ....,===.....
. . . .=...=..==...==..
CM 1CMOOi LIMIT SWITCH HAMCG EA-170 H-2852 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMO2 OPEN POS. 46302 E-3918 525 CM 1CMOO6 LIMIT SWITCH NAMCO EA-170 H-2852 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMO2
. CLOSED POS. 46302 E-3918 525 CM 1CMOO6 LIMIT SWITCH NAMCO EA-170 H-2852 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMO2 OPEN POS. 46302 E-3918 525 CM 1CMOOG SOLENOID ASCO HTX8320A22V H-2852 E-145 B/21 R2A R.B. N/A A 2A N-81-1 CMO4
. E-3918 525 CM ICMOO7 LIMIT SWITCH TARGET 76F-201 H-2862 E-145 B/21 R2A R.B. N/A A 2A M L1-1 CMOS
. OPEN POS. ROCK E-3918 525 CM 1CM007 LIMIT SWITCH TARGET 76F-201 H-2862 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMOS
. CLOSED POS. ROCK E-3918 525 CM 1C?' Jo7 SOLENOID TARGET 76F-201 H-2862 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMOS
. ROCK E-3918 525 CM 1CM i m LIMIT SWITCH TARGET 76F-201 H-2862 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMOS CLOSED POS. ROCK E-3918 525 CM 1CM ~1 LIMIT SWITCH TARGET 76F-201 H-2862 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMOS OPEN POS. ROCK E-3918 525 CM Icrooa SOLENOID TARGET 76F-201 H-2862 E-145 B/21 R2A R.B. N/A A 2A M-81-1 CMO5 ROCK E-3918 525 CM tcMoo9 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6 CLOSED POS. ROCK E-3918 503 CM 1CMOO3 SOLENOID TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6 ROCK E-3918 503 CM 1CMOO3 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6 OPEN POS. ROCK E-3918 503 CM RM010 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6
. OPEN POS. ROCK E-3918 503 CM R'etO LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6 CLOSED POS. ROCK E-3918 503
.PAGt 4 OF 76 to N
n SARGENTMUNDY
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7
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PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLO ACT/ ADD 0588 DATA
*SY tHIMGER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.....< .......................................... ..................... . ........ ..................................................
CM 1CM010 SOLENOID IARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6
. ROCK E-3918 503 CM 1CMO11 SOLENDID TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6
. ROCK E-3918 503 CM 1CM011 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18s' R3A R.B. N/A A 2A M-81-1 CMO6
. OPEN POS. ROCK E-3918 503 CM 1CM011 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6
. CLOSED POS. ROCK E-3918 503 CM 1CM012 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01 OPEN POS. 46302 E-3918 503 CM 1Cr a 12 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01 CLOSED POS. 46302 E-3918 503 4
CM 1 012 SOLENOID ASCO HTX8320A22V H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO3 E-3918 503 CM 1CMO13 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6
. CLOSED POS. ROCK E-3918 503 CM 1CM013 SOLENOID TARGET 76F-201 H-2862 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO6 ROCK E-3918 503 CM 1CM013 LIMIT SWITCH TARGFT 7CF-201 H-2862 E-143 D/18 R3A R.B. N/A A 24 M-81-1 CMO6 OPEN POS. ROCK E-3918 503 CM 1Cf4014 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01 CLOSED POS. 46302 E-3918 503 CM 1CMO14 LIMIT SWITCH NAMCO EA-170 H-2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CM01
. OPEN POS. 46302 E-3918 503 CM trMO14 SOLENGID ASCO HTX8320A22V H<"2852 E-143 B/18 R3A R.B. N/A A 2A M-81-1 CMO3 E-3918 503 CM trM019 SOLENOID TARGET 76F-202 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO7 ROCK E-3918 503 CM 1mO 19 LIMIT SWITCH TARGET 76F-202 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO7 OPEN POS. ROCK E-3918 503
.PAGF 5 0F 76 m
O M ) M SARGENT&LUNDY
.-M-..
8 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SV NUMBER EQUIPMENT MFR NUMBER B/M NO. W/0 NO. ELEVA1N IN CUT BUILD LEV PASS REV CAT. SHEET e............................................................................................... . ...................................
CM 1CM019 LIMII SWITCH TARGET 76F-202 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CFO7
. CLOSED 005. ROCK E-3918 503 CM 1CMO2O SOLENOID TARGET 76F-202 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO7
. ROCK E-3918 503 CM 1CMO2O LIMIT SWITCH TARGET 76F-202 H-2662 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO7
. CLOSED POS. ROCK E-3918 503 CM 1CMO2O LIMIT SWITCH TARGET 76F-202 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO7
. OPEN POS. ROCK E-3918 503 CM 1CMO21 LIMIT SWITCH TARGET 76F-202 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-81-1 CMO8
. OPEN POS. ROCK E-3918 525 CM 1CM021 LIMIT SWITCH TARGET 76F-202 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-81-1 CMO8
. CLOSED POS. ROCK E-3918 525 CM 1CMO21 SOLENOID TARGET 76F-202 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-81-1 CMO8 ROCK E-3918 525 CM 1CMO22 SOLENOID TARGET 76F-202 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-81-1 CMOS
. ROCK E-3918 525 CM 1CMO22 LIMIT SWITCH TARGET 76F-202 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-81-1 CMO8
. CLOSED POS. ROCK E-3918 525 CM 1CMO22 LIMIT SWITCH TARGET 76F-202 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-81-1 CMO8 OPEN POS. ROCK E-391P 525 CM 1CMO23 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO6 CLOSED POS ROCK E-3918 503 CM 1CMO23 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO6 OPEN POS. ROCK E-3918 503 CM 1CMO23 SOLENOID TARGET 76F-201 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMOG
. ROCK E-3918 503 CM 1CMO24 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO6
. CLOSED POS. ROCK E-3918 503 CM 1CMO24 LIMIT SWITCH TARGET 76F-201 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMO6 CPEN POS. ROCK E-3918 503
.PAGE 6 0F 76 m
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g (O 4 'O PROJECT NUMBER 4130-05 DATE 22 DEC 83
. . REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326 e PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.....m..........................................................................,...,... ......,... .... ........ ........... .....
CM ILMO24 SOLENOID TARGET 76F-201 H-2862 E-143 C/25 R3A R.B. N/A A 2A M-81-1 CMOG
. ROCK E-3918 503 CM 1LT-CMOO8 TRANSMIT ROSE- 1152DP6A22- H-2809 E-144 E/20 R3A R.B. A 2A 1PX34J CMO9
. MOUNT PB E-1995 503 CM 1LT-CMOO9 TRANSMIT ROSE- 1152DP4A22- H-2809 E-142 C/25 R4A R.B. A 2A 1PX22J CM10 MOUNT PB E-1995 475 CM ILT-CMO22 TRANSMIT ROSE- 1152DP6A22- H-2809 E-143 A/18 R3A R.B. A 2A 1PX43J CMO9
. MOUNT PB E-1995 503 CM 1LT-CMO23 TRANSMIT ROSE- 1152DP4A22- H-2809 E-141 B/16 R4A R.B. A 2A 1PX67J CM10
. MOUNT PB E-1995 475 CM 1PL40JA H2/02 FISSION DELPHI H-2188 E-147-1 C/25 R1C R.B. A 2A CM16
. PROD. PNL.1A 546 CM IPL40JB H2/02 FISSION DELPHI H-2188 E-147-1 B/18 RfC R.B. A 2A CM16 PROD. PHL.1B 546 CM 1PT-CM010 TRANSMIT ROSE- 1152GPGA22 H-2809 E-149 B/16 RSA R.B. A 2A 1PX21J CM11 MOUNT PB E-1995 570 CM IPT-CMO21 TRANSMIT ROSE- 1152GP6A22 H-2809 E-151 A/21 RGB R.B. A 2A 1PX35J CM12 MOUNT PB E-1995 593 CM 1PT-CMO81 TRANSMIT ROSF- 1152GPGA22 H-2809 E-142 C/25 R4A R.B. A 2A 1PX22J CM13 MOUNT PB E-1995 475 CM 1PT-CMO82 TRANSMIT ROSE- 1152GP6A22 H-2809 E-141 B/16 R4A R.B. A 2A 1PX67J CM13 MOUNT PB E-1995 475 CM 1TE-CMO43 TEMP ELEM GORDON 404-3107- PO-2949 E-146 314 DEG C2 WETWEL A 2A LOC MTD CMIC M OSO E-1996 519 {'Q Q lp; CM ITE-CMO44 TEMP ELEM CORDON 402-4107- PO-2949 E-145 220 DEG C2 WETWEL A 2A LOC MTD CM15
. 050 E-1996 519 CM ITE-CMO45 TEMP ELEM GORDON 402-4107- PO-2949 E-146 20 DEG C2 WETWEL A 2A LOC MTD CM15
. 050 E-1988 S19 CM 1TE-CMO46 TEMP ELEM GORDON 404-3107- PO-2949 E-145 148 DEG C2 WETWEL A 2A LOC MTD CJtN M O 050 E-199G 519 ,
.PAGE 7 0F 76
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SARGENT&LUNDY ENGINEERD -
10 PROJECT NUMBER 4130-05 DATE ?2 DEC 83 REVISION 010
. ZIMMER EOUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA eSy NupsGER EQUIPMENT MFR B/M NO. W/D NO.
NUMBER ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.............................. ................................................................ . ........ . ........ ........... ..... L et 1TE-CMO47 ILMP ELEM GORDON 404-3107- PO-2949 E-145 142 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-199G 496 CM iTE-CMO48 TEMP ELEM GORDON 404-3107- PO-2949 E-145 222 DEG C2 WETWEL A 2A LOC MTD CM14 05O E-1996 496 CM 1TE-CMO49 TEMP ELEM GORDON 404-3107- PO-2949 E-146 53 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-1996 496 CM 1TE-CMO50 TEMP ELEM GORDON 404-3107- PO-2949 E-146 88 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-199G 496 CM 1TE-CMO51 TEMP ELEM GORDON 404-3107- PO-2949 E-146 27 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-1996 496 CM 1TE-CMO53 TEMP ELEM GORDON 404-3107- PO-2949 E-146 321 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-1996 496 CM ITE-CMO54 TEMP ELEM GORDON 404-3107- PO-2949 E-146 57 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-1996 496 CM iTE-CMO55 TEMP ELEM GORDON 404-3107- PO-2949 E-146 294 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 CM ITE-CMO5G TEMP ELEM GORDON 404-3107- PO-2949 E-146 344 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 CM ITE-CMO57 TEMP ELEM GORDON 404-3107- PO-2949 E-145 238 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 CM ITE-CMO58 TEMP ELEM GORDON 404-3107- PO-2949 E-146 345 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 CM 1TE-CMO59 TEMP ELEM GORDON 404-3107- PO-2949 E-145 200 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 CM ITE-CMOGO TEMP ELEM GORDON 404-3107- PO-2949 E-146 295 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 CM 1TE-CM061 TEMP ELEM GORDON 404-3107- PO-2949 E-145 183 DEG C2 WETWEL A 2A LOC MTD CM14
. OLO E-1996 490 CM ITE-CMO62 TEMP ELEM GORDON 404-3107- PO-2949 E-145 274 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 PAGE 8 0F 76 m
o m M SARGENT&LUNDY
'ENGINEERG
11 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET CM iTE-CMo64 TEMP ELEM GORDON 404-3107- PO-2949 E-145 246 DEG C2 WETWEL A 2A LOC MID CM14
. 050 E-1996 496 CM ITE-CMO66 TEMP ELEM GORDON 404-3107- PO-2949 E-145 217 DEG C2 WETWEL A 2A LOC MTD CM14
. 050 E-1996 496 CM ITE-CMO68 TEMP ELEM GORDON 404-3107- PO-2949 E-145 151 DEG C2 WETWEL A 2A LOC MTD CM14 050 E-1996 496 DC 10C05EB 250VDC ITE SERIES 5600 H-2166 E-148-1 F/16 Ric R.B. A 2A 5 MINUTES DC01
. RX MCC 1A E-2321/2330 546 DC 1DC05EC 250VDC ITE SCRIES 5600 H-2166 E-148-1 D/27 R1C R.B. A 2A 5 MINUTES DC01
. RX MCC 1B 546 HG 1PDT-HGOO1 PRESS DIFFER ROSE- 1152DP4422- H-2809 E-150 E/23 RSA R.B. A 2A 1PX69J HG01 TRANSMITTER MOUNT PB E-2680 570 HG 1PDT-HGOO2 PRESS DIFFER ROSE- 1152DP4422- H-2809 E-150 D/25 RSA R.B. A 2A tPX70J HGOf
. TRANSMITTER MOUNT PB E-2680 570 HG 1T49DOO1-OOBA MOTOR OPER- LIMIT 58-000 H-2210 E-152 E/26 R6 R.B. A 2A M-74 HGO2
. ATED VALVE E-2655 593 HG 1T490001-008B MOTOR OPER- LIMIT SB-OOO H-2210 E-152 E/26 R6C R.B. A 74 M-74 HCO2 ATED VALVE E-2668 593 HG 1T49DOO1-OO9A MOTOR OPER- LIMIT S8-000 H-2210 E-152 E/26 R6C R.B. A 2A M-74 HGC2 ATED VALVE E-2667 593 HG 11490001-009B MOTOR OPER- LIMIT 58-000 H-2210 E-152 E/26 R6C R.B. A 2A M-74 HGO2 ATED VALVE E-2668 593 HG 1T49DOO1-014A MOTOR OPER- LIMIT 58-000 H-2210 E-152 E/26 R6C R.B. A 2A M-74 HGO4 ATED VALVE E-2667 593 HG iT490001-0148 MOTOR OPER- LIMIT 58-000 H-2210 E-152 E/26 R6C R.B. A 2A M-74 HGO4
. ATED VALVE E-2668 593 HG 1T49DOO1-015A MOTOR OPER- ITT NH91G1073L5 H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGOS ATED VALVE E-2667 593 HG 1T49DOO1-0150 MOTOR OPER- ITT NH91G1073L5 H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGOS ATED VALVE E-2668 593
.PAGE 9 0F 76 e
O M M SARGENT&LUNDY iOINGERE-
12 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
....................e2..u.................................. ..................... . ... . ... ...... . ... . .... . ........ .................
HG 1T490001-017A MOTOR OPER- ITT NH91G1073N6 H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGOS
. ATED VALVE E-2667 593 HG 1's490001-017B MOTOR OPER- ITT NH91G1073N6 H-2210 E-152 E/27 R6C R.B. A JA M-74 HGOS
. ATED VALVE E-2668 593 HG iT490001-021A MOTOR OPER- LIMIT S8-000 H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGO4 ATED VALVE E-2667 593 HG iT490001-021B MOTOR OPER- LIMIT 58-000 H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGO4
. ATED VALVE E-2668 593 HG 1T49DOO1-022A MOTOR OPER- LIMIT SB-OOO H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGO6
. ATED VALVE E-2667 593 HG 1T490001-022B MOTOR OPER- LIMIT 58-000 H-2210 E-152 E/27 R6C R.B. A 2A M-74 HGO6 ATED VALVE E-2668 593 HG iT49-DOO1-3 RECOMBINER CTI- P/ND27658 H-2210 E-152 E/27 R6C R.B. A 2A HG11 NUCLEAR 593 HG 1T49-DOO1-6A BLOWER SPEN- H-2210 E-152-1 E/26 R6C R.B. A 2A HG12
. MOTOR CER 593 HG 1T49-DOO1-6B BLOWER SPEN- H-2210 E-152-1 F/26 R6C R.B. A 2A HG12 MOTOR CER 593 HG 1T49-FOO2A MOTOR OPER- LIMIT 5B-000 H-2210 E-148 F/23 R1C R.B. A 2A M-74 HGO7 ATED VALVE E-1735 546 HG 1T49-FOO2B MOTOR OPER- LIMIT 58-000 H-2210 E-148 E/23 RfC R.B. A 2A M-74 HGO7 ATED VALVE E-1745 546 HG 1T49-FOO4A MOTOR OPER- LIMIT SB-OOO H-2210 E-144 B/18 R3A R.B. A 2A M-74 HGO8 ATED VALVE E-1735 510 HG 1T49-FOO4B MOTOR OPER- LIMIT SB-OOO H-2210 E-144 B/18 R3A R.B. A 2A M-74 HGO8
. ATED VALVE E-1745 513 HG 1T49-F305A SOLENOID TARGET 76F-209 H-2862 E/23 RfC R.B. N/A A 2A M-74 HGO9 VALVE ROCK 556 HG iT49-F3058 SOLENOID TARGET 76F-209 H-2862 E/23 Ric R.B. N/A A 2A M-74 HGO9 VALVE ROCK 556
.PAGE 10 0F 76 m
(9 SARGENT&lUNDY
' ENGINEERS .
13 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADO 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN DUT BUILD LEV PASS REV CAT. SHEET HG II49-KOO1 A MILLIVOLT ROSE- 169C1917 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-0147 HG19 CONVERTER MOUNT 535 E-2657 593 HG 1T49-KOO1 B MILLIVOLT ROSE- 169C1917 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-D148 HG19
. CONVERTER MOUNT 535 E-2664 593 HG 1T49-NOO1 A PRESSURE ROSE- 163C1158 H-2210 E-152-1 E/27 R6C R.B. A 2A iT49-D147 HG13
. TRANSMITTER MOUNT 1151AP E-2657 593 HG 1T49-NOO1 B PRESSURE ROSE- 163C1158 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-D148 HG13
. TRANSMITTER MOUNT 1151AP E-2664 593 HG iT49-NOO2 A PRESSURE ROSE- 163C1158 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-0147 HG14
. TRANSMITTER MOUNT 1151AP E-2657 593 HG 1T49-NOO2 B PRESSURE ROSE- 163C1158 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-0148 HG14
. TRANSMITTER MOUNT 1151AP E-2664 593 HG 1T49-NOO4 A FLOW IND. BARTON 145C3OO9 H-2210 E-152-1 E/27 R6C R.B. A 2A IT49-D147 HG17
. SWITCH 288 E-2657 593 HG 1T49-NOO4 B FLOW IND BARION 145C3OO9 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-D148 HG17
. SWITCH 288 E-2664 593 HG 1T49-NOO5 A FLOW IND. BARTON 145C3OO9 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-D147 HG18 SWITC.: 288 E-2657 593 HG II49-NOO5 B FLOW IND. BARTON 145C3OO9 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-0148 HG10
. SWITCH 288 E-2664 593 HG 1T49-NOO6 A FLOW ROSE- 163C1561 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-D147 HG15 TRANSMIITER MOUNT 1151DP E-2657 593 HG 1T49-NOOG B FLOW ROSE- 163C1561 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-0148 HG15
. TRANSMITTER MOUNT 1151DP E-2664 503 HG 1T49-NOO7 A FLOW ROSE- 163C1561 H-2210 E-152-1 E/27 R6C R.B. A 2A 1T49-0147 HG16 TRANSMITTER MOUNT 1151DP E-2657 593 HG 1T49-NOO7 8 FLOW ROSE- 163C1561 H-2210 E-152-1 E/27 R6C R.B. A 2A tT49-0148 HG16 TRANSMITTER MOUNT 1151DP E-2664 593 HP 1E22-COO 1 PUMP G.E. 5K6348XC47A H-2210 E-141 B/16 R4C R.B. A 2A HPO1
. MOTOR 475 l .PAGE 11 0F 76 l m o
M M SARGENT&LUNDY
's 4 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION OtO
. ZIMMER EOUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL EPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET HP 1E22-COO 3 PUMP WEST. 74D24113 H-2185 E-141 B/15 R4C R.B. N/A A 2A HPO2 ,
MOTOR 475 HP 1E22-FOO1 MOTOR OPER- LIMIT SMB-OO H-2210 E-141 C/15 R4A R.B. A 2A M-49 HPO4 ATED VALVE E-1490 475 HP 1E22-FOO4 MOTOR OPER- LIMIT SMB-4 H-2210 E-147 C/18 R1C R.B. A 2A M-49 HPOS
. ATED VALVE E-1491 561 HP 1E22-FOO5 AIR OPER- ASCO WPHTX834472 H-2267 E-147 D/21 C1 DRYWEL N/A P EX M-49 EOO5 ATED VALVE E-2903 578-6 HP IE22-FOO5 LIMIT SWITCH NAMCD EA74010000 H-2267 E-147 D/21 C1 DRYWEL N/A P EX M-49 EOO5
. E-2903 578-6 HP 1E22-FOO5 POS. SWITCH MAG- MPS-15 H-2267 E-141 D/21 C1 DRYWEL N/A A 2A M-49 HPO3
. OPEN/CLOSE LOCK E-2903 578-6 HP 1E22-F010 MOTOR OPER- LIMIT SMB-3 H-2210 E-143 A/18 R3A R.B. A 2A M-49 HPO6
. ATED VALVE E-1495 503 HP 1E22-F011 M. IR OPER- LIMIT SMB-3 H-2210 E-143 A/18 R3A R.B. A 2A M-49 HPO6 ATED VALVE E-1494 503 HP 1E22-FO12 MOTOR OPER- LIMIT SB-O H-2210 E-141 B/18 R4C R.B. A 2A M-49 HPO7 ATED VALVE E-1490 475 HP 1E22-FO15 MOTOR OPER- LIMIT SMB-2 H-2210 E-141 B/18 R4A R.B. A 2A M-49 HPO8 ATED VALVE E-1491 475 HP 1E22-F023 MOTOR OPER- LIMIT SMB-3 H-2210 E-143 A/18 R3A R.B. A 2A M-49 HPO9 ATED VALVE E-1495 503 HP 1E22-F314 MOTOR OPER- LIMIT SMB-OOO H-2852 E-147 D/21 C1 DRYWEL N/A A 2A M-49 HP10 ATED VALVE E-1496 570 HP 1E22-NOO2 A LEVEL SWITCH MAGNET 159C4294 H-2210 E-142 E/24 R4A R.B. A 2A HP11
-ROL 3.5-751tXMPG-M14HY E-2903 475 HP 1E22-NOO2 B LEVEL SWITCH MAGNET 159C4294 H-2210 E-142 E/24 R4A R.B. A 2A HP11
-ROL 3.5-751TXMPG-M14Hf E-2903 475 HP 1E22-NOO5 FLOW TRANS. BAILEY 163C1183 H-2210 A/16 R4C R.B. A 2A 1H22-PO24 HP12 555 E-2857 475
.PAGE 12 0F 76 to o
c) ci SARGENT&LUNDY '
= ENGINEERD -
IS PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA eSV NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILO LEV PASS REV CAT. SHEET e....................................................................... . ............ ... ...... ... ..... ......................... .
HP 1E22-NOO6 FLOW SWITCH BARTON 145C3OO8 4-2210 E-141-1 A/16 R4C R.B. A 2A 1H22-PO24 HP13 289A E-2857 475 HP 1E22-NOO9 OIFF. PRESS. BARTON 145C3OO9 H-2210 E-141-1 A/16 R4C R.B. A 2A 1H22-PO24 HP14 SWITCH 288A E-2857 475 HP 1E22-NO12 PRESS.INO. BARKS- 159C4606 H-2210 E-141-1 A/16 R4C R.B. A 2A 1H22-PO24 HP16
. SWITCH DALE P1HM340SS-V E-2857 475 HP 1E22-NO13 DIFF. PRESS. BARTON 145C3OO9 H-2210 E-141-1 A/16 R4C R.D. A 2A 1H22-PO24 HP15
. INO. SWITCH 288A E-2857 475 IN 11NOOBA MOTOR OPER- LIMIT SMB-OOO-2 H-2852 E-150 D/25 RSA R.B. N/A A 2A M-40-2 INO1 ATED VALVE E-2330 570 IN 11NOO8B MOTOR OPER- LIMIT SMB-OOO-2 H-2852 E-149 B/18 RSA R.B. N/A A 2A M-40-2 INO1
. ATED VALVE E-2331 570 IN 11NO12 LIMIT SWITCH NAMCO EA17031100 H-2266 E-147 D/25 C1 DRYWEL N/A A 2A M-40-2 INO3 CLOSED POS. E-3849 581 IN IINO12 LIMIT SWITCH NAMCO EA17031100 H-2266 E-147 D/25 C1 DRYWEL N/A A 2A M-40-2 INO3
. OPEN POS. E-3849 581 IN TINO12 SOLENOID ASCO HT8320A175 H-2266 E-147 D/25 C1 DRYWEL N/A A 2A M-40-2 INOS E-3849 581 IN 11NO13 LIMIT SWITCH NAMCO EA17031100 H-2266 E-149 C/25 R5A R.B. N/A A 2A M-40-1 INO4 OPEN POS. E-3849 577 IN IINO13 LIMIT SWITCH NAMCO EA17031100 H-2266 E-149 C/25 RSA R.B. N/A A 2A M-40-1 INO4 CLOSED POS. E-3849 577 IN 11NO13 SOLENOID ASCO HT8320A175 H-2266 E-149 C/25 RSA R.B. N/A A 2A M-40-1 IN06
. E-3849 577 IN 11NO61 MOTOR OPER- LIMIT SMB-OOO-2 H-2263 E-149 C/25 RSA R.B. N/A A 2A M-40-1 INO2
. ATED VALVE E-2339 570 IN 11N170 LIMIT SWITCH TARGET 76F-206 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-40-1 INO7 OPEN PDS. ROCK E-3849 533 IN 11N170 LIMIT SWITCH TARGET 76F-206 H-28G2 E-145 C/25 R2A R.B. N/A A 2A M-40-1 INO7 CLOSED POS. ROCK E-3849 533
$PAGE 13 0F 76 m
n SARGENT&LUNDY
= ENGINEERB -
13 O 4 4
- PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588- DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILO LEV PASS REV CAT. SHEET IN IINf70 SOLENOID TARGET 76F-206 H-2862 E-145 C/25 R2A R.B. N/A A 2A M-40-1 INO7 ROCK E-3849 533 IN 11N171 LIMIT SWITCH TARGET 76F-206 H-2862 E-145 C/23 C1 DRYWEL N/A A 2A M-40-1 INO8
. CLOSED POS. ROCK E-3849 524 IN 11N171 LIMIT SWITCH TARGET 76F-206 H-2862 E-145 C/23 C1 DRYWEL N/A A 2A M-40-1 INO8
. OPEN POS. ROCK E-3849 524 IN 11N171 SOLENOID TARGET 76F-206 H-2862 E-145 C/23 C1 DRYWEL N/A A 2A M-40-1 INOS
. ROCK E-3849 524 LC 1E32-BOO 1A HEATER G.E. 47D518673 H-2210 E/21 R3A R.B. A 2A LC01
. 503 LC 1E32-BOO 18 HEATER G.E. 47D518673 H-2210 E/21 R3A R.B. A 2A LC01
. 503 LC 1E32-BOO 1C HEATER G.E. 47D518673 H-2210 E/21 R3A R.B. A 2A LC01
. 503 LC 1E32-BOO 1D HEATER G.E. 47D518673 H-2210 E/21 R3A R.B. A 2A LC01 503 LC 1E32-COO 1 BLOWER SIE- 2CH6-041-1V H-2210 E/19 R3A R.B. A 2A LCO2
. MENS 503 LC 1E32-COO 2A BLOWER SIE- 2CH6-041-1V H-2210 E/22 R3A R.B. A 2A LCO2
. MENS 503 LC 1E32-COO 2B BLOWER SIE- 2CH6-041-1V H-2210 E/22 R3A R.B. A 2A LCO2
. MENS 503 LC 1E32-FOO1A MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/23 R8 STM.TL N/A A 2A M-73-1 LCO3
. ATED VALVE E-1739 525 LC 1E32-FOO18 MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/23 R8 STM.TL N/A A 2A M-73-2 LCO3
. ATED VALVE E-1741 525 LC 1E32-FOO1C MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/21 R8 STM.TL N/A A 2A M-73-2 LCO3 ATED VALVE E-1741 525 LC 1E32-FOO1D MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/21 R8 STM.TL N/A A 2A M-73-2 LCO3 ATED VALVE E-1741 525
.PAGE 14 0F 76 m
vs SARGENT&LUNDY WNetNEERS .
17 (9 4 4 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT CUALIFICATION 001326 *
- PLANT 10 COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/AOD 0588 DATA eSY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e................,=============,==.......===......,................. ===,....... ,===,...................,===,........==......,= ...
LC 1E32-FOO2A MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/23 R8 STM.TL N/A A 2A M-73-1 LC04 ATED VALVE E-1741 325 LC 1E32-FOO2B MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/23 R8 STM.TL N/A A 2A M-73-2 LC04
. ATED VALVE E-1742 525 LC 1E32-FOO2C MOTOR OPER- LaMIT SMB-OOO H-2852 E-146 E/21 R8 STM.TL N/A A 2A M-73-2 LCO4 ATED VALVE E-1742 525 LC 1E32-FOO2D MOTOR OPER- LIMIT SMB-OOO H-2852 E-146 E/21 R8 STM.TL N/A A 2A M-73-2 LC04 ATED VALVE E-1742 525 LC IE32-FOO3A MOTOR OPER- LIMIT SMB-OOO H-2852 E-144 E/23 R3A R.B. N/A A 2A M-73-1 LCOS ATED VALVE E-1742 503 LC 1E32-FOO3B MOTOR OPER- LIMIT SMB-OOO H-2852 E-144 E/23 R3A R.B. N/A A 2A M-73-2 LCOS ATED VALVE E-1758 503 LC 1E32-FOO3C MOTOR OPER- LIMIT SMB-OOO H-2852 E-144 E/23 R3A R.B. N/A A 2A M-73-2 LCO5 ATED VALVE E-1758 503 LC 1E32-FOO3D MOTOR OPER- LIMIT SMB-OOO H-2852 E-144 E/23 R3A R.B. N/A A 2A M-73-2 LCOS ATED VALVE E-1758 503 LC 1E32-FOO6 MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/21 R8 STM.TL N/A A 2A M-73-1 LCO6 ATED VALVE E-1752 503 LC 1E32-FOO7 MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/21 R8 STM.TL N/A A 2A M-73-1 LCO6 ATED VALVE E-1752 503 LC 1E32-FOO8 MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/23 R8 STM.TL N/A A 2A M-73-1 LCO6
. ATED VALVE E-1753 503 LC 1E33-FOO9 MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/23 R8 STM.TL N/A A 2A M-73-1 LCO6 ATED VALVE E-1753 503 LC 1E32-NOO6 A FLOW METER S&K 163C1107 H-2210 E-144 E/19 R3A R.B. A 2A LCO7 20-9651-8550 E-2898 513 LC 1E 32 - rJOO6 E FLOW METER S&K 163C1107 H-2210 E-144 E/20 R3A R.B. A 2A LC07 20-9651-8550 E-2898 512 LC 1E32-NOO6 d FLOW METER S&K 163C1107 H-2210 E 144 E/19 R3A R.B. A 2A LCO7 20-9651-8550 E-2898 512
.PAGE 15 0F 76 to c
n SARGENT&LUNDY
= 8NGENEER8 .
18 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
. ............i..............
LC 1E32-NOO6 N FLOW METER SSK 163C1107 H-2210 E-144 E/19 R3A R.B. A 2A LCO7 20-9651-8550 E-2898 513 LC 1E32-N050 PRESS.TRANS. ROSE- 163C1564 H-2210 E-148-1 E/24 RfC R.B. A 2A 1H22-PO26 LC15
. MOUNT 1151GP 546 LC 1E32-N051 A PRESS.TRANS. ROSE- 163C1558 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC09 MOUNT 1151AP E-2898 503 LC 1E32-NO51 E PRESS.TRANS. ROSE- 163C1558 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC09
. MOUNT 1151AP E-2898 503 LC 1E32-N051 J PRESS.TRANS. ROSE- 163C1558 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC09
. MOUNT 1151AP E-2898 503 LC 1E32-N051 N PRESS.TRANS. ROSE- 163C1558 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC09
. MOUNT 1151AP E-2898 503 LC 1E32-N053 A FLOW TRANS. S&K 163C1158 H-2210 E-144-1 E/tB R3A R.B. A 2A 1H22-PO73 LCOS 91X-16-4-20 E-2898 503 LC 1E32-N053 E FLOW TRANS. S&K 163C1158 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LCO8 91X-16-4-20 E-2898 503 LC 1E32-NO53 d FLOW TRANS. S&K 163C1158 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LCO8 91X-16-4-20 E-2898 503 LC 1E32-N053 N FLOW TRANS. S&K 163C1158 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LCOS 91X-16-4-20 E-2898 503 LC 1E32-NO54 DIFF. PRESS. ROSE- 163C1561 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC11 TRANS. MOUNI 1151DP E-2898 503 LC 1E32-NC55 PRESS. TRANS. ROSE- 163C1564 H-2210 E-144-1 E/24 R3A R.B. A 2A 1H22-PO74 LC12 MOUNT 1151GP E-2900 503 LC 1E32-N056 PRESS.TRANS. ROSE- 163C1558 H-2210 E-144-1 E/24 R3A R.B. A 2A 1H22-PO74 LC12 MOUNT 1151AP E-2900 503 LC 1E32-NO!3 PRESS. TRANS. ROSE- 163C1564 H-2210 E-147-1 C/17 RiC R.B. A 2A 1H22-PC27 LC10 MOUNT 1151GP E-2867 546 LC 1E32-N059 DIFF. PRESS. ROSE- 163C1561 H-2210 E-144-1 E/24 R3A R.B. A 2A 1H22-PO74 LC13 TRANS. MOUNT 1151DP E-290v 503
$PAGE 16 0F 76 O
O (9 M SARGENT&LUNDY
= E NOttt2E A U ..
1? PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.....................-...........,.................................................. .........., ,....... ........,.................
LC IE32-N060 PRESS. TRANS. ROSE- 163C1564 H-2210 E-148-1 E/24 RfC R.B. A 2A 1H22-PO26 LC10
. MOUNT 1151GP 546 LC 1E32-N061 A PRESS. TRANS. ROSE- 163C1564 H-2210 E-144-1 E/18 R3A R.B. 2A A 1H22-PO73 LCt4
. MOUNT 1151GP E-2898 503 LC 1E32-NOG 1 E PRESS. TRANS. ROSE- 163C1564 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC14 MOUNT 1151GP E-2898 503 LC 1E32-NO61 d PRESS. TRANS. ROSE- 163C1564 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC14
. MOUNT 1151GP E-2898 503 LC 1E32-N061 N PRESS. TRANS. ROSE- 1G3C1564 H-2210 E-144-1 E/18 R3A R.B. A 2A 1H22-PO73 LC14
. MOUNT 1151GP E-2898 503 LD 1E31-NOO1 A TEMPERATURE PYCO 145C3224 H-2210 E-148 D/18 RfC R.B. A 2A LD01 ELEMENT E-2676 546 LD 1E31-NOO1 B TEMPERATURE PYC0 145C3224 H-2210 E-148 D/18 RfC R.B. A 2A LD01 ELEMENT E-2677 54G LD 1E31-NOO1 C TEMPERATURE PYC0 145C3224 H-2210 E-148 E/15 RIC R.B. A 2A LD01
. ELEMENT E-2676 546 LD 1E31-NOO1 D TEMPERATURE PYC0 145C3224 H-2210 E-148 E/15 Ric R.B. A 2A LD01
. ELEMENT E-2677 546 LD 1E31-NOO1 E TEMPERATURE PYC0 145C3224 H-2210 E-150 E/23 RSD R.B. A 2A LDO2 ELEMENT E-2676 570 10 1E31-NOO1 F TEMPERATURE PYCO 145C3224 H-2210 E-150 E/2? RSD R.B. A 2A LDO2
. ELEMENT E-2G77 570 LD 1E31-NOO2 A TEMPERATURE PVC0 145C3224 H-2210 E-148 E/18 R1C R.B. A 2A LD01 ELEMENT E-2676 546 LD 1E31-NOO2 B TEMPERATURE PYC0 145C3224 H-2210 E-148 E/18 RfC R.B. A 2A LD01
. ELEMENT E-2677 546 LD 1E31-NOO2 C TEMPERATURE PYC0 145C3224 H-2210 E-148 E/17 RfC R.B. A 2A LDO1
. ELEMENT E-2676 546 LD 1E31-NOO2 D TEMPERATURE PVCO 145C3224 H-2210 E-148 E/17 RfC R.B. A 2A LD01
. ELEMENT E-2677 546
.PAGE 17 0F 76 to n
SARGENTaLUNDY
'ENGINEErtD -
20 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILO LEV PASS REV CAT. SHEET e==............................................................................................................... . .................
LD 1E31-NOO2 E TEMPERATURE PYC0 145C3224 H-2210 E-150 F/21 RSD R.B. A 2A LOO 2
. ELEMENT E-2G76 570 LD 1E31-NOO2 F TEMPERATURE PYC0 145C3224 H-2210 E-150 F/21 RSD R.B. A 2A LDO2 ELEMENT E-2'i77 570 LD 1 E 31 -twO3 A TEMPERATURE PYCO 145C3224 H-2210 E-148 E/18 RiC R.B. A 2A LD01 ELEMENT E-2676 546 LD 1E31-NOO3 8 TEMPERATURE PYC0 145C3224 H-2210 E-148 E/18 RfC R.B. A 2A LD01
. ELEMENT E-2677 546 LD 1E31-NOO3 C TEMPERATURE PYC0 145C3224 H-2210 E-148 E/17 RfC R.B. A 2A LD01
. ELEMENT E-2676 546 LD 1E31-NOO' D TEMPERATURE PYC0 145C3224 H-2210 E-148 E/17 Ric R.B. A 2A LOO 1
. ELEMENT E-2677 546 LD 1E31-NOO3 E TEMPERATURE PYC0 145C3224 H-2210 E-150 E/22 R50 R.B. A 2A LDO2
. ELEMENT E-2676 570 LD 1E31-NOO3 F TEMPFRATURE PVCD 145C3224 H-2210 E-150 E/21 R5D R.B. A 2A LDO2 ELEMENT E-2677 570 LD 1E31-NOO4 A TEMPERATURE PVCO 145C3224 H-2210 E-142 E/16 R4D R.B. A 2A LDO3
. ELEMENT E-2676 473 LO 1E31-NOO4 8 TEMPERATURE PYC0 145C3224 H-2210 E-142 F/16 R4D R.B. A 2A LDO3 ELEMENT E-2677 473 LD 1E31-NOO5 A TEMPERATURE PYC0 145C3224 H-2210 E-142 E/15 R4D R.B. A 2A LDO3
. ELEMENT E-2676 473 LD 1E31-NOO5 B TEMPERATURE PYC0 14".C 32 2 4 H-2210 E-142 E/15 R4D R.B. A 2A LDO3
. ELEMENT E-2677 473 LD 1E31-NOO6 A TEMPERATURE PYC0 145C3224 H-2210 E-144 F/18 R3A R.B. A 2A LDO4 ELEMENT E-2676 505 LD 1E31-NOO6 8 TEMPERATURE PYC0 145C3224 H-22tO E-144 F/17 R3A R.B. A 2A LDO4 ELEMENT E-2677 503 LD 1E31-NOO7 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-142 E/19 R4D R.B. A 2A 1H22-pot 7 LD17 IND. SWITCH 280A E-2841 475
.PAGE 18 0F 76 u) o n
M P SARGENT&LUNDY
= ENGINEER 9-
21 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT QUALIFICATION DO1326
- PLANT ID MODEL SPEC OR COMPONENT / E.I. DWG COL / ROW CONTAIN FLD ACT/tDD 0588 DATA
*SY NUMPdR EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.......,a............................ .
LD tr,1-NOO7 B DIFF. PRESS. BARTON 145C3OO9 H-2210 E-142 F/24 R4E R.B. A 2A 1H22-PO29 LD18 IND. SWITCH 288A E-2874 475 LD 1E31-NOO8 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 E/13 R3A R.9. A 2A 1H22-PO15 LD19
. IND. SWITCH 288A E-2838 503 LD 1E31-NOO8 B DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 D/16 R3A R.B. A 2A 1H22-PO22 LD19
. IND. SWITCH 288A E-2850 503 LD 1E31-NOO8 C DIFF. PRESS. BARTGN 145C3OO9 H-2210 E-144-1 F/24 R3A R.B. A 2A 1H22-PO25 LD19
. IND. SWI T C 288A E-2860 503 LD 1E31-NOO8 D DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 C/25 R3A R.B. A 2A 1H22-PO41 LD19
. IND. SWITCH 288A E-2893 503
- t.D 1E31-NOO9 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 E/19 R3A R.B. A 2A 1H22-PO15 LD19
. IND. SWITCH 288A E-2838 503 LD 1E31-NOO9 B DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 D/16 R3A R.B. A 2A 1H22-PO22 LD19 IND. SWITCH 288A E-2850 503 LD 1E31-NOO9 C DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 F/24 R3A R.B. A 2A 1H22-PO25 LD19 IND. SWITCH 288A E-2860 503 LD 1E31-NOO9 D DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 C/25 R3A R.B. A 2A 1H22-PO41 LD19 IND. SWITCH 288A E-2893 503 LD 1E31-NO10 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 E/19 R3A R.B. A 2A 1H22-PO15 LD19 IND. SWI1CH 288A E-2838 503 LD 1E31-NO10 B DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 D/16 R3A R.B. A 2A 1H22-PO22 LDi9 IND. SWITCH 288A E-2850 503 LD 1E31-NO10 C DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 F/24 R3A R.B. A 2A 1H22-PO25 LD19 IND. SWITCH 288A E-2860 503 LD 1E31-NO10 D DIFF. PRESS. BARTON 145C3OO9 H-2210 E-14f-1 C/25 R3A R.B. A 2A 1H22-PO41 LD19
. IND. SWITCH 288A E-2893 503 LD 1E31-NO11 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 E/19 R3A R.B. A 2A 1H22-PO15 LD19 IND. SWITCH 288A E-2838 503 LD 1E31-NOtt B DIFF. PRESS. BARTON 145(3009 H-2210 E-144-1 D/16 R3A R.B. A 2A 1H22-PO22 LD19
. IND. SWITCH 288A E-2850 503
$PAGE 19 0F 76 m
n SARGENT&LUNDY
= ENGINEER B .
22 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010 ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
... ............. .............. . .................................c................... . .......... ...................................
LD 1E31-NO11 C DIFF. PRESS. BARTON 145C3OO9 H-2210 E-144-1 F/24 R3A W.B. A 2A 1H22-PO25 LD19
. IND. SWITCH 239A E-2860 503 LD 1E31-NO11 D DIFF. PRESS. BARTON 145C3OO9' H-2210 E-144-1 C/25 R3A R.B. A 2A 1H22-PO41 LD19 IND. SWITCH 288A E-2893 503 LD 1E31-NO12 A DIFF. PRESS. BARTON 145C3OO9 H-2210 B/26 R4B R.B. A 2A 1H22-PO18 LD20 IND. SWITCH 288A E-2844 475 LD 1E31-NO12 B DIFF. PRESS. BARTON 145C3OO9 H-2210 E/28 R4E R.B. A 2A 1H22-PO21 LD21
. IND. SWITCH 288A E-2847 475 LD 1E31-NO13 A DIFF. PRESS. BARTON 145C3OO9 H-2?10 E-142 E/19 R4D R.B. A 2A 1H22-PO17 LD17 IND. SWITCH 288A E-2841 475 LD 1E31-NO13 B DIFF. PRESS. BARTON 145C3OO9 H-22tO E-142 F/24 R4E R.B. A 2A 1H22-PO29 LD18
. IND. SWITCH 288A E-2874 475 LD 1E31-NO15 TLOW TRANS. BAILEY 159C46b8 H-2210 E-148-1 D/17 R1C R.B. A 2 !. 1H22-POO2 LD22
. 555 E-2805 546 LO 1E31-NO17 A TEMP ELEM GORDON 404-4107- PO-2949 E-147 C/21 C1 DRYWEL A 2A LD11
. 050 E-2677 583 LD 1E31-NO17 B TEMP ELEM GORDON 404-3107- PO-2949 E-147 D/21 C1 DRYWEL A 2A LD12 050 E-2677 572 LD 1E31-NO17 C TEMP ELEM GORDON 404-4107- PO-2949 E-147 D/23 C1 DRYWEL A 2A LD11 050 E-2677 563 LD 1E31-NO17 D TEMP ELEM GORDON 404-3107- PO-2949 E-147 B/22 C1 DRYWEL A 2A LD12 050 E-2677 551 LD 1E31-NO18 A TEMP. ELEMENT PVCO 145C3224 H-2210 E-143 C/25 R4F R.B. A 2A LDOS E-2676 506 LD 1E31-NO18 8 TEMP. ELEMENT PYC0 145C3224 H-2210 E-143 C/28 R4F R.B. A 2A LDOS
. E-2677 506 LD 1E31-NO18 C TEMP. ELEMENT PYC0 145C3224 H-2210 E-144 D/28 R4F R.B. A 2A LDOS E-2676 506 LD 1E31-NO18 D TEMP. ELEMENT PYC0 145C3224 H-2210 E-144 D/26 R4F R.B. A 2A LDOS
. E-2677 506
$PAGE 20 OF 76 O
M M SARGENT&LUNDY
. --..n o .
23 4 4 <O PROJECT NUM8ER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT QUALIFICATION dot 326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT PUILD LEV PASS REV CAT. SHEET e.........................................r................ . ............ ....................... . ... .... . ... ................
LD 1E31-NO22 A PRESS. SWITCH BARKS- 15904606 H-22to E-142 E/19 R4D R.B. A 2A 1H22-pot 7 LD23
. DALE P1HM340SS-V E-2841 475 lb 1E31-NO22 B PRESS. SWITCH BARKS- 159C4606 H-2210 E-142 F/24 R4E R.B. A 2A 1H22-PO29 LD24 DALE P1HM340SS-V E-2874 475 LD 1E31-NO22 C PRESS. SWITCH BARKS- 159C4606 H-2210 E-142 E/19 R4D R.B. A 2A 1H22-PO17 LD23 DALE PtHM340SS-V E-2841 475 LD 1E31-NO22 D PRESS. SWITCH BARKS- 159C4606 H-2210 E-142 F/24 R4E R.B. A 2A 1H22-PO29 LD24 DALE P1HM340SS-V E-2874 475 LD 1E31-NO24 A TEMPERATURE PYC0 145C3224 H-22tO E-145 B/23 R2A R.B. A 2A LDOS ELEMENT E-267C 525 LD TE31-NO24 8 TEMPERATURE PYC0 145C3224 H-2210 E-141 B/24 R4A R.B. A 2A LD10 ELEMENT E-2677 497 LD 1E31-NO27 A TEMPERATURE PVCO 145C3224 H-2210 E-141 B/28 R4B R.B. A 2A LDO6
. ELEMENT E-2676 490 LD 1E31-NO27 B TEMPERATURE PYC0 145C3224 H-2210 E-141 B/28 R4B R.B. A 2A LDO6
. ELEMENT E-2676 490 LD 1E31-NU27 C TEMPERATURE PYC0 145C3224 H-2210 E-142 D/27 R4E R.B. A 2A LDO7 ELEMENT E-2677 477 LD 1E31-NO27 0 TEMPERATURE PYC0 145C3224 H-2210 E-142 E/27 R4E R.B. A 2A LD07 ELEMENT E-2677 477 LD 1E31-NO28 A TEMPERATURE PYCO 145C3224 H-2210 E-143 C/25 R4F R.B. A 2A LDOS
. ELEMENT E-2676 520 LO 1E31-NO28 8 TEMPERATURE PYC0 145C3224 H-22 0 E-143 C/25 R4F R.B. A 2A LDOS ELEMENT E-2676 520 LD 1E31-NO28 C TEMPERATURE PYC0 145C3224 H-2210 E-144 D/27 R4F R.B. A 2A LDOS ELEMENT E-2677 503 LD 1E31-NO28 D TEMPERATURE PYC0 145C3224 H-22f0 E-144 D/27 R4F R.B. A 2A LDOS ELEMENT E-2677 503
- LO 1E31-NO29 A TEMPERATURE PYC0 145C3224 H-2210 E-146 E/21 R2A R.B. A 2A LDOS
. ELEMENT E-2676 525
.PAGE 21 0F 76 to SARGENT&LUNDY
' ENGINEER 9 -
2C PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET LD 1E31-NO29 B TEMPERATURE PYC0 145C3224 H-2210 E-146 E/21 R2A R.B. A 2A LDO8 ELEMENT E-2677 525 LD 1E31-NO29 C TEMPERATURE PYC0 145C3224 H-2210 E-144 E/23 R8 R.B. A 2A LDO9
. ELEMENT E-2677 525 LD 1E31-NO29 D TEMPERATURE PYCO 145C3224 H-2210 E-144 E/23 R8 R.B. A 2A LDO9 ELEMENT E-2677 525 LD 1E31-NO30 A TEMPERATURE PVCO 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS
. ELEMENT E-2676 525 LD 1E31-NO30 B TEMPERATURE PYC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS ELEMENT E-2677 525 LD 1E31-NO30 C TEMPERATURE PVC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS ELEMENT E-2677 525 LD 1E31-NO30 D TEMPERATURE PYC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS ELEMENT E-2677 525 LD 1E31-NO31 A TEMPERATURE PYC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS
. ELEMENT E-2676 525 LD 1E31-NO31 B TEMPERATURE PYC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS
. ELEMENT E-2677 525 LD 1E31-NO31 C TEMPERATURE PYC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LOO 8
. ELEMENT E-26T7 525 LD 1E31-NO31 D TEMPERATURE PYC0 145C3224 H-2210 E-146 F/24 R2A R.B. A 2A LDOS ELEMENT E-2677 525 LD 1E31-NO35 FLOW TRANS. BAILEY 159C4658 H-2210 E-148-1 D/18 RfC R.B. A 2A 1H22-POO2 LD22 555 E-2805 546 LD 1E31-NO36 FLOW TRANS. BAILEY 159C4658 H-2210 E-148-1 D/18 R1C R.B. A 2A 1H22-POO2 LD22 555 E-2805 546 LD 1TE-LDO38 TEMP ELEMENT GORDON 404-3107- PO-2949 E-142 D/16 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 497 LD ITE-LDO39 TEMP ELEMENT GORDON 404-3107- P0-2949 E-142 D/16 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 497
.PAGE 22 0F 76 o
m SARGENTMUNDY ENGINEERO -
25 PR0dECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLO ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M No. W/D NO. ELEVATN IN OUT BUILD LEV .'.'tS REV CAT. SHEET LD 1TE-LDO40 TEMP ELEMENT GORDON 404-3107- PO-2949 E-142 D/17 R4A R.B. A 2A LOC MTD LD13
. 050 E-2677-1 457 LD iTE-LDO41 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 C/17 R4A R.B. A 2A LOC MTD LD13
. 050 E-2677-1 497 LD 1TE-LDO42 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 C/17 R4A R.B. A 2A LOC MTD LD13
. 050 E-2677-1 497 LD 1TE-LDO43 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 C/18 R4A R.B. A 2A LOC MTC LD13
. 050 E-2677-1 497 LD ITE-LDO44 TEMP ELEMENT GORDOf. 404-3107- PO-2949 E-141 B/18 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 497 LD 1TE-LDO45 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/18 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 497 LD 1TE-LDO46 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/18 R4A R.B. A 2A LOC MTD LD13
. 050 E-2677-1 497 LD 1TE-LDO47 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/20 R4A R.B. A 2A LOC MTD LD13 060 E-2677-1 497 LD 1TE-LDO48 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/21 R4A R.B. A 2A LOC MTD LDf3
. 050 E-2677-1 497 LD 1TE-LDO49 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/22 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 497 LD iTE-LD050 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/23 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 497 LD 1TE-LDO51 TEMP ELEMENT GORDON 404-3107- PO-2949 E-141 B/24 R4A R.B. A 2A LOC MTD LD13 050 E-2677-1 499 LO 1TE-LDOS2 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 B/24 R2A R.B. A 2A LOC MTD LD14 050 E-2677-1 536 LD ITE-LDO53 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 B/23 C1 DRYWEL A 2A LOC MTD LD12 050 E-2677-1 528 LD ITE-LDO54 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 B/23 C1 DRYWEL A 2A LOC MTD LD12 050 E-2677-1 536
.PAGE 23 0F 76
<o O
m n SARGENT&l. UNDY
'ENGINEERD .
23 PROJECT NUMBER 4130-05 DATL 12 DEC 83 REVISION 010 ZIMMER EQUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NtiMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET Lo tTE-LDO55 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 B/24 C1 DRYWEL A 2A LOC MTD LD12
. 050 E-2677-1 545 LD ITE-LDOS6 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 B/23 C1 DRYWEL A 2A LOC MTD LD12
. 050 E-2677-1 550 LD STE-LDO57 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 B/23 C1 DRYWEL A 2A LOC MTD LD12 050 E-2677-1 556 LD 1TE-LDO58 TEMP ELEMENT GORCON 404-3107- PO-2949 E-147 C/23 C1 DRYWEL A 2A LOC MTD LD12
. 050 E-2677-1 565 LD 1TE-LDO59 TEMP ELEMENT GORDON 404-3107- PO-2949 E-147 C/23 C1 DRYWEL A 2A LOC MTD LD12 050 E-2677-1 572 LD ITE-LDO86 TEMP ELEMENT GORDON 404-3107- PO-2949 E-145 C/23 C1 DRYWEL A 2A LOC MTD LD12
. 050 E-2677-1 573 LD 1TE-LDO87 TEMP ELEHENT GORDON 404-3107- PO-2949 E-147 C/23 C1 DRYWEL A 2A LOC MTD *D12
. 050 E-2677-1 572 LD STE-LDOO8 TEMP ELEMENT GORDON 404-3107- PO-2949 E-150 E/19 RSA R.B. A 2A LOC MTD LD15 050 E-2677-1 570 LD ITE-LDO89 TEMP ELEMENT GORDON 404-3107- PO-2949 E-150 E/20 R3D R.B. A 2A LOC MTD LD16 050 E-2677-1 570 LD 1TE-LDO90 TEMP ELEMENT GORDON 404-3107- PO-2949 E-150 E/19 R50 R.B. A 2A LOC MTD LD16 050 E-2677-1 570 LD ITE-LDO93 TEMP ELEMENT GORDON 404-3107- PO-2949 E-150 E/19 RSD R.B. A 2A LOC MTD LD16 050 E-2677-1 570 LD ITE-LDO94 TEMP ELEMENT GORDON 404-3107- PO-2949 E-150 E/20 R50 R.B. A 2A LOC MTD LD16 050 E-2677-1 570 LD 1TE-LDO96 TEMP ELEMENT GORDON 404-3107- PO-2949 E-150 E/19 RSD R.B. A 2A LOC MTD LD16 050 E-2677-1 570 LP 1E21-COO 1 PUMP G.E. SK6339xC14- H-2210 E-141 B/27 R4B R.B. A 2A LPO1
. MOTOR 7A 475 LP 1E21-COO 2 PUMP WEST. 74D24113 H-2185 E-141 B/26 R4B R.B. A A 2A LPO2 MOTOR 475
[ PACE 24 0F 76 u, O M M SARGENT&LUNDY
= ENGINEEMB -
27 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET, LP 1E21-FOO1 MOTOR OPER- LIMIT SMB-O-25 H-2811 E-141 C/27 R4A R.B. A 2A M-50 LPO4
. ATED VALVE E-1455 475 LP 1E21-FOO5 MOTOR OPER- LIMIT SMB-O H-2264 E-147 C/25 RfC R.B. A 2A M-50 LPOS ATED VALVE E-1455 546 LP 1E21-FOO6 SOLENOID ASCO WPHTX834472 H-2267 E-147 D/23 C1 DRYWEL N/A P EX M-50 EOO5 E-1571 578-6 LP 1E21-FOO6 LIMIT SWITCH NAMCO EA74010000 H-2267 E-147 D/23 C1 DRYWEL N/A P EX EOO5 E-1571 578-6 LP 1E21-FOO6 OPEN/CLOSE MAG- MPS-15 H-2267 E-147 D/23 C1 DRYWEL N/A A 2A LPO3
. POS. SWITCH LOCK E-1571 578-6 LP 1E21-F011 MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-141 B/27 R4B R.B. N/A A 2A M-50 LPO6
. ATED VALVE E-1570 475 LP 1E21-FO12 MOTOR OPER- LIMIT SMB-2 H-2819 E-141 C/27 R4F R.B. N/A A 2A M-50 LPO7
. ATED VALVE E-1566 475 LP 1E21-F330 MOTOR OPER- LIMIT SMB-OOO H-2852 E-147 C/22 C1 DRYWEL N/A A 2A M-50 LPOS
. ATED VALVE E-1571 570 LP 1E21-NOO1 PRESS. IND. BARKS- 159C4606 H-2210 E-141-1 B/28 R4B R.B. A 2A 1H22-POO1 LPO9
. SWITCH DALE P1HM340SS-V E-2802 475 LP 1E21-NOO3 FLOW TRANS. BAILEY 163C1183 H-2210 E-141-1 B/28 R48 R.B. A 2A 1H22-POO1 LP10 555 E-2802 475 LP 1E21-NOO4 FLOW IND. BARTON 145C3OO8 H-2210 E-141-1 B/28 R4B R.B. A 2A 1H22-POO1 LP11
. SWITCH 289A E-2802 475 LP 1E21-NOO6 DIFF. PRESS. BARTON 145C3OO9 H-2210 E-141-1 B/28 R4B R.B. A 2A 1H22-POO1 LP12
. IND. SWITCH 288A E-2802 475 LP 1E21-NOO9 PRESS. SWITCH BARKS- 159C4606 H-2210 E-141-1 B/28 R4B R.B. A 2A 1H22-POO1 LPO9
. DALE P1HM340SS-V E-2802 475 NB 1821-FOO1 MOTOR CPER- LIMIT SMS-OOO H-2852 C/21 C1 DRYWEL N/A P 28 M-83-1 NB13
. ATED VALVE 595 NB 1821-FOO2 MOIOR OPER- LIMIT SMB-OOO H-2852 C/21 C1 DRYWEL N/A P 28 M-83-1 NB13 ATEP VALVE 593
.PAGE 25 0F 76 to n
SARGENT&LUNDY
.- -~ - ._
28 PROJECT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010
. ZIMMER EOUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.................................................,...................................... . .......... .... . ... ................ ......
NB 1821-FOO5 MOTOR OPER- LIMIT SMB-OOO H-2852 D/24 C1 DRYWEL N/A P 2B M-21-1 NB13 ATED VALVE 589 NB 1821-FO13A SOLENDID CROSBY CVG-01 H-2210 E-147 D/23 C1 DRYWEL A 2A M-21-1 NBO1
. E-2915 570 NB 1821-FO138 SOLENOID CROSBY CVG-Of H-2210 E-147 D/23 C1 DRYWEL A 2A M-21-1 NBOt
. E-2915 570 NB 1821-F013C SOLENDID CROSBY CVG-01 H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01
. E-2915 570 NB 1821-FO13D SOLENOID CROSBY CVG-01 H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01 E-2915 570 NB 1821-FO13E SOLENGID CROSBY CVG-Of H-2210 E-147 D/23 Cf DRYWEL A 2A M-21-1 NB01 E-2915 570 NB IB21-FOt3F SOLENOID CROSBY CVG-01 H-2210 E-147 D/23 C1 DRYWEL A 2A M-21-1 NB01
. E-2915 570 NB 1821-F013G SOLENDID CROSBY CVG-01 H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01 E-2915 570 NB 1821-FO13H SOLENOID CROSBY CVG-Of H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01
. E-2915 570 NB 1821-FO13K SDLENGID CROSBY CVG-01 H-2210 E-147 D/23 C1 DRYWEL A 2A M-21-1 NB01 E-2915 570 NB 1821-F013L SOLENUID CROSBY CVG-01 H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01
. E-2915 570 NB 1821-F013P SOLENDID CROSBY CVG-01 H-2210 E-147 D/23 C1 DRYWEL A 2A M-21-1 NBOf E-2915 570 NB 1821-FO13R SDLENGID CROSBY CVG-01 H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01
. E-2915 570 NB 1821-FO13S SOLENGID CROSBY CVG-01 H-2210 E-147 D/21 C1 DRYWEL A 2A M-21-1 NB01
. E-2915 570 NB 1821-F016 MOTOR OPER- LIMIT SMB-DOO-5 *1-2264 E-146 C/22 C1 DRYWEL A 2A M-21-4 NB14 ATED VALVE E-1749 525
.PAGE 26 0F 76 o
O M M SARGENT&LUNDY
=ENGINEERO .
29 f PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 '
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADO 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET ees,. .....e=== ,s====ammesses,======,s==========,suss====,seess=======,emmansas.... mme,sesses,e==, esse,===,...s.nemesseme==,me==,
NB 1821 - F 019 MOTOR OPER- LIMIT SMB-OO-7.5 H-2264 E-144 E/23 R3A R.B. N/A A 2A M-21-4 NB15 ATED VALVE E-2334 525 NB 1821-FO22A LIMIT SWITCH NAMCO EA740-80001 H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 N802 E-2915 525 NB 1821-F022A LIMIT SWITCH NAMCO EA740-86000 H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 N803
. E-2915 525 NB 1821-F022A SOLENOID ASCO HTX 0320- H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 N808 A20 E-2915 525 N8 1821-FO22A SOLENOID ASCO HTX 8323- H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NSO9 2OV E-2915 525
*4B 1821-F022A SOLENOID ASCO HTX 8323- H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 N809 2OV E-2915 525 NB 1821-F022A LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NBO4
. E-2915 525 NB 1821-F0228 LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 D/23 C1 DRYWEL A 2A M-21-1 N804
. E-2915 525 NB tB21-FO228 LIMIT SWITCH NAMCO EA740-80001 H-2210 E-146 D/23 C1 DRYWEL A 2A M-21-1 NB02
. E-2915 525 NB 1821-FO228 LIMIT SWITCH NAMCO EA740-86000 H-2210 E-146 D/23 C1 DRYWEL A 2A M-21-1 NBO3 E-2915 525 NB 1821-F0228 SOLEN 0!D ASCO HTX 8320- H-2210 E-146 D/23 C1 DRYWEL A 2A M-21-1 NBO8 A20 E-2915 525 NB 1821-FO228 SOLENDID ASCO HTX 8323- H-2210 E-146 D/23 C1 DRYWEL A 2A M-21-1 NBO9
. 20V E-2915 525 NB 1821-FO228 SOLENDID ASCO HTX 8323- H-2210 E-146 D/23 C1 DRYWEL A 2A M-21-1 N809
. 2OV E-2915 525 NB 1821-F022C LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 D/21 C1 DRYWEL A 2A M-21-1 NBO4 E-2915 525 NB 1821-F022C LIMIT SWITCH NAMCO EA740-80001 H-2210 E-146 D/21 C1 DRYWEL A 2A M-21-1 NBO2 E 2915 525
.PAGE 27 0F 76
<D m SARGENT#dUNDY ENGINEERD-
30 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA l *SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET l ......................................................................................... .......... ........ .... .................
ND 1821-FO22C LIMIT SWITCH NAMCO EA740-86000 H-2210 E-146 D/21 C1 DRYWEL A 2A M-21-1 NB03 E-2915 525 NB 1821-F022C SOLENGID ASCO HTX 8320- H-2210 E-146 D/21 C1 DRYWEL A 2A M-21-1 NBOB -
. A20 E-2915 525 NB 1821-F022C SOLENOID ASCO HTX 8323- H-2210 E-146 D/21 C1 DRYWEL A 2A M-21-1 NBO9 2OV E-2915 525 NB 1821-FO22C SOLENOID ASCO HTX 8323- H-2210 E-146 D/21 C1 DRYWEL A 2A M-21-1 NBO9 20V E-2915 525 NB 1821-F0220 50LENOIO ASCO HTX 8320- H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NBOS"
. A20 E-2915 525 NB 1821-F022D SOLENOID ASCO HTX 8323- H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NR10 A20V E-2915 525 NB 1821-FO220 SOLENDID ASCO HTX 8323- H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NB10 A20V E-2915 525 NB 1821-FO22D LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NBO4
. E-2915 525 NB 1821-F022D LIMIT SWITCH NAMCO EA740-80001 H-2210 E-116 D/22 C1 DRYWEL A 2A M-21-1 NBO2 E-2915 525 NB 1821-F022D LIMIT SWITCH NAMCO EA740-86000 H-2210 E-146 D/22 C1 DRYWEL A 2A M-21-1 NB03 E-2915 525 NB 1821-F028A SOLENDID ASCO HTX 8320- H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NB11 A2O E-2915 525 NB 1821-F02ev SOLENOID ASCU HTX 8323- H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NB12 20V E-2915 525 NB 1821-FO '> INOID ASCO HTX 8323- H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NB12 20V E-2915 525 NB 1821-F020A LIMI T SWITCH NAMCO EA740-86000 H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NBO7 E-2915 525 NB 821-FO28A LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NROS E-2015 525
.PAGE 28 0F 76 to
() SARGENT&LUNDY
. .~.~..a d
31 PROJECT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010 ZIMMER EQUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/A00 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT DUILD LEV PASS REV CAT. SHEET e.................................................................................... . .......... ........ . ........ ........... .....
NB 1821-FO28A LIMIT SWITCH NAMCO EA740-80001 H-2210 E-146 E/23 R2A R.S. A 2A M-21-1 NB06
. E-2915 525 NB 1821-F0288 LIMIT SWITCH NAMCO EA740-80001 H-2210 E-14G E/23 R2A R.B. A 2A M-21-1 NB06 E-2915 525 NB 1821-FO28B SOLENOID ASCO HTX S323- H-2210 E - 146 E/23 R2A R.B. A 2A M-21-1 NB 2 2OV E-2915 525 NB 1821-F0288 SOLENOID ASCO HTX 8323- H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NB12 2OV E-2915 525 NB 1821-F028B LIMIT SWITCH NAMCO EA740-86000 H-2210 E - 14 6 E/23 R2A C.B. A 2A M-21-1 NBO7 E-2915 525 NB 1821-F028B SOLENOID ASCO HTX 8320- H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NB11 A20 E-2915 525 NB 1B21-F0288 LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 E/23 R2A R.B. A 2A M-21-1 NBOS E-2915 525 NB 1821-FO28C LIMIT SWITCH NAMCO EA740-8GOOO H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NBO7 E-2915 525 NB 1821-FO23C SOLENOID ASCO HTX 8323- H-2210 E-146 E/21 R?A R.B. A 2A M-21-1 NB12 20V E-2915 525 NB 1821-F028C SOLENGID ASCO HTX 8323- H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB12 20V E-2915 525 NB 1821-FO28C SOLENOID ASCO HTX 8320- H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB11 A20 E-2915 525 NB 1821-FO28C LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB05 E-2915 525 NB fB21-FO28C LIMIT SWITCH NAMCO EA740-80001 H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB06 E-2915 525 NB 1821-FO28D LIMIT SWITCH NAMCO EA740-80000 H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NBOS E-2915 525 NB 1821-FO280 SOLENOID ASCO HTX 8320- H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB11 A2O E-2915 525
$PAGE 29 0F 76 e
O SARGENT&LUNDY
..naa ...-
32 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION DO1326
- PLANT ID COMPONENT / MODEL SPEC CR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILC LEV PASS REV CAT. SHEET NB 1821-FO280 SOLENDID ASCO HTX 8323- H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB12
. 2OV E-2915 525 NB 1821-F028D SOLENOID ASCO HTX 8323- H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NB12 20V E-2915 525 NB 1821-F028D LIMIT SWI1CH NAMCO EA740-80001 H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NBO6 E-2915 525 NB 1821-FO28D LIMIT SWITCH NAMCO EA740-86000 H-2210 E-146 E/21 R2A R.B. A 2A M-21-1 NBO7 E-2915 525 NB 1821-FO65A MOTOR OPER- LIMIT SMB-3-80 H-2264 E-146 E/23 R-8 R.B. N/A A 2A M-23 NB17 ATED VALVE E-1461 525 NB 1821-FO65B MOTOR OPER- LIMIT SMB-3 80 H-2264 E-146 E/21 R-8 R.B. N/A A 2A M-23 NB17 ATED VALVE E-1761 525 NB 1821-F067A MOTCR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/23 R8 STM.TL N/A A 2A M-21-4 NB18
. ATED VALVE E-2332 503 NB 1821-FO678 MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/23 R8 STM.TL N/A A 2A M-21-4 NB18 ATED VALVF E-2332 503 NB 1821-F067C MOTOR OPEF!- LIMIT SMB-OOO-5 H-2852 E-144 F/21 R8 STM.TL N/A A 2A t, 21-4 NB18 ATED VALVE E-2332 503 NB 1821-F067D MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-144 F/21 R8 STM.TL N/A A 2A M-21-4 NB18 ATED VALVE E-2332 503 NB 1821-NO2O A PRESS. SWITCH BARKS- 164Cf359 H-2210 E-148-1 E/20 RIC R.B. A 2A 1H22-POO4 NB20 DALE B1TM12SS-G2 E-2808 546 NB 1821-NO2O B PRESS. SWITCH BARKS- 164C5359 H-2210 E-147-1 C/17 RfC R.B. A 2A 1H22-PO27 NB20 DALE BITM12SS-GE E-2867 546 NB 1B21-NO2O C PRESS. SWITCH BARKS- 164C5359 H-2210 E-147-1 C/24 R1B R.B. A 2A tH22-POO5 NB21 DALE B.1TM12SS-GE E-2812 546 NR 1821-NO2O D PRESS. SWITCH BARKS- 164C5359 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 NB20 DALE B1TM12SS-GE E-2863 546 NB 1821-NO23 A PRESS. SWITCH BARKS- 164C5359 H-2210 E-148-1 E/20 Ric R.B. A 2A 1H22-POO4 NB20 DALE B1TM12SS-GE E-2808 546
.PAGE 30 0F 7G to ei n
SARGENT&LUNDY
'ENGINEERB -
33 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EOUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET ..............===,-===..................................................,.. .....,==................ . .... . ... . .... ........... .....
NB fB21-NO23 B PRESS. SWITCH BARKS- 164C5359 H-2210 E-147-1 C/17 RIC R.B. A 2A 1H22-PO27 NB20 DALE B1TM12SS-GE E-2867 546 NB 1821-NO23 C PRESS. SWITCH BARKS- 164C5359 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB21
. DALE B1TM12SS-GE E-2812 546 NB 1821-NO23 D PRESS. SWITCH BARKS- 164C5359 H-2210 E-148-1 E/24 RIC R.B. A 2A 1H22-PO26 NB20 DALE B1TM12SS-GE E-2863 546 NB 1821-NO24 A LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/20 R1C R.B. A 2A 1H22-POO4 NB22 . SWITCH -288A E-2808 546 NB 1821-NO24 B LEVEL IND. BARTON 159C4384 E-2210 E-147-1 C/17 R1C R.B. A 2A 1H22-PO27 NB22 . SWITCH -288A E-2867 546 NB 1821-NO24 C LEVEL IND. BARTON 159C4384 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POOS NB23 SWITCH -288A E-2812 546 NB 1821-NO24 D LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 NB22 SWITCH -288A E-2863 546 NB 1821-NO24 E LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/20 RfC R.B. A 2A 1H22-POO4 NB22 SWITCH -288A E-2808 S46 NB 1821-NO24 G LEVEL IND. BARTON 159C4384 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB23 SWITCH -288A E-2812 546 NB 1821-NO26 A LEVEL IND. BARTON 159C4383 H-2210 E-148-1 E/20 RIC R.B. A 2A 1H22-POO4 N828 TRANS. SWITCH 760 E-2808 546 NB 1821-NO2C B LEVEL IND. BARTON 159C4383 H-2210 E-147-1 C/17 R1C R.B. A 2A 1H22-PO27 NB28 TRANS.5 WITCH 760 E-2867 546 NB 1821-NO26 C LEVEL IND. BARTON 159C4383 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB29 TRANS. SWITCH 760 E-2812 546 NB 1821-NO26 D LEVEL IND. BARTON 159C4383 H-2210 E-148-1 E/24 R1C R.B. % 2A 1H22-PO26 NB28 TRANS. SWITCH 760 E-2863 546 NB 1821-NO31 A LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/20 RfC R.B. A 2A 1H22-POO4 NB24 SWITCl1 -288A E-2808 546 NB 1821-NO31 B LEVEL IND. BARTON 159C4384 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB25 SWITCH -288A E-2812 546 $PAGE 31 0F 76 to N
e9 SARGENT&LUNDY
= ENGINGERB .
30 m PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION DJ1326 e PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA *SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D N3. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET .........=.............................................................. ......... .... .... ...... .....................-==...........
NB 1821-NO31 C LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/20 RfC R.B. A 2A 1H22-POO4 NB24 SWITCH -288A E-2808 546 NB 1821-NO31 D LEVEL IND. BARTON 159C4384 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB25 SWITCH -288A E-2812 546 NB 1821-NO36 A LEVEL IND. YARWAY 159C4445 H-22tO E-148-1 E/24 R1C R.B. A EX 1H22-PO26 E001
. SWITCH 4418C E-2864 546 NB 1821-NO36 B LEVEL IND. YARWAY 159C4445 H-2210 E-143-1 E/24 Ric R.B. A EX 1H22-PO26 EOO1 SWITCH 4418C E-2863 546 i
NB 1821-NO36 C LEVEL IND. YARWAY 159C4445 H-2210 E-147-1 C/17 RfC R.B. A EX 1H22-PO27 EOO1
. SWITCH 4418C E-2867 546 NB 1821-NO3G D LEVEL IND. YARWAY 159C4445 H-2210 E-147-1 C/17 RfC R.B. A EX 1H22-PO27 EOOt SWITCH 4418C E-2867 546 NB 1821-NOs7 A LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 NB26
. SWITCH -288A E-2864 546 NB 1821-NO37 B LEVEL IND. BARTON 159C4384 H-22tO E-147-1 C/17 Ric R.B. A 2A 1H22-PO27 NB26 SWITCH -288A E-2867 546 NB 1821-NO37 C LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-DO26 NB26 SWITCH -288A E-2864 546 NB 1821-NO37 D LEVEL IND. BARTON 159C4384 H-2210 E-147-1 C/17 R1C R.B. A 2A 1H22-PO27 NB26 SWITCH -288A E-2867 546 NB 1821-NO38 A LEVEL IND. BARTON 159C4384 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 NB27 SWITCH -288A E-2863 546 NB 1221-NO38 8 LEVEL IND. BARTON 159C4384 H-2210 E-147-1 C/17 RiC R.B. A 2A 1H22-PO27 NB27 SWITCH -288A E-2867 546 NB 1R21-NO44 A LEVEL IND. BARTON 159C4383 H-2210 E-145-1 C/16 R2A R.B. A 2A 1H22-POtO NB30 TRANS. SWITCH 760 E-2831 525 NB 1821 NO44 8 LEVEL IND. BARTON 159C4383 H-2210 E-145-1 B/26 R2A R.B. A 2A 1H22-POO9 NB30 TRANS. SWITCH 760 E-2827 525 NB fB21-NO45 A PRESS. SWITCH BARKS- 164C5359 H-2210 E-148-1 E/24 RfC R.B. A 2A 1H22-PO26 NB2O DALE B1TM12SS-GE E-2864 546
.PAGE 32 0F 76
.o o m n SARGENT&LUNDY
'ENGINJER9 -
35
- h. f PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION DO1326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLO ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET ......===...===...............=.==........==............................ . -=.............. ...... .=. ......................... .....
NR 1821-NO45 B PRESS. SWITCH BARKS- 164C5359 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 NB20
. DALE B1TM12SS-CE E-2863 54G N8 1821-NO45 C PRESS. SWITCH BARKS- 164C5359 H-2210 E-147-1 C/87 RfC R.B. A 2A 1H22-PO27 NB20
. DALE BtTM12SS-GE E-2867 546 NB 1821-NO45 D PRESS. SWITCH BARKS- 164C5359 H-2210 E-147-1 C/17 RfC R.B. A 2A 1H22-PO27 NB20 DALE BtTM12SS-GE E-2867 546 NB 1821-NO47 A PRESS. SWITCH STATIC 145C3012 H-2210 E-148-1 E/20 R1C R.B. A 2A 1H22-POO4 NB32 0-RING 12NAA4i1X10 E-2809 - 546 NB 1821-NO47 B PRESS. SWITCH STATIC 145C3012 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB33 0-RING 12NAA411X10 E-2812 546 NB 1821-NO47 C PRESS. SWITCH STATIC 145C3012 H-2210 E-148-1 E/20 Ric R.B. A 2A 1H22-POO4 NB32 0-RING 12NAA411X10 E-2809 546 NB 1821-NO47 D PRESS. SWITCH STATIC 145C3012 H-22tO E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 NB33 0-RING 12NAA41tX10 E-2812 546 NB 1821-NO48 A PRESS. SWITCH STATIC 145C3012 H-2210 E-148-1 E/24 RfC R.B. A 2A 1H22-PO26 NB32
. 0-RING 12NAA411X10 E-2863 546 NB 1821-NO48 B PRESS. SWITCH STATIC 145C3012 H-2210 E-147-1 C/17 R1C R.B. A 2A 1H22-PO27 NB32 0-RING 12NAA4ttX10 E-2867 546 NB 1821-NO48 C PRESS. SWITCH STATIC 145C3012 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 NB32 0-RING 12NAA41tX10 E-2863 546 NB 1821-NO48 D PRESS. SWITCH STATIC 145C3012 H-2210 E-147-1 C/17 RfC R.B. A 2A 1H22-PO27 NB32
. 0-RING 12NAA411X10 E-2867 546 NB 1821-N051 A PRESS.TRANS. ROSE- 163C1564 H-2210 E-148-1 E/20 R1C R.B. A 2A 1H22-POO4 NB34 MOUNT 1151GP E-2808 546 NB 1821-N051 8 PRESS.TRANS. ROSE- 163C1564 H-2210 E-147-1 C/17 RfC R.B. A 2A 1H22-PC27 NB34 MOUNT 1151GP E-2867 546 NB 1PT-NBOO3A PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RfC R.B. A 2A 1H22-PO26 NB35 TRANSMITTER MOUNT PB E-2863 546 NB IPT-NBOO3B PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RfC R.B. A 2A 1H22-PO26 NB35 TRANSMITTER MOUNT PB E-2863 546
.PAGE 33 0F 76
'O O m M SARGENT&LUNDY
= ENGINEERS .
36 (O r0 4 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EOUIPMENT QUALIFICATION D01326
- PLANT ID COMPONE'tT/ MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET NB 1PT-NBOO3C PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 R1C R.B. A 2A 1H22-PO26 NO35
. TRANSMITTER MOUNT PB E-2863 546 NB IPT-NBOO3D PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RfC R.B. A 2A 1H22-PO26 NB35
. TRANSMITTER MOUNT PB E-2863 546 NB iPT-NBOO3E PRESSURE RGSE- 1152GP9422- H-2809 E-148-1 E-24 Ric R.B. A 2A 1H22-PO26 NB35
. TRANSMITTER MOUNT PB E-2863 546 NB iPT-NGOO3F PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RfC R.B. A 2A 1H22-PO26 NB35 TRANSMITTER MOUNT PB E-2863 546 NB IPT-NBOO3G PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RfC R.B. A 2A 1H22-PO26 NB35 TRANSMITTER MOUNT PB E-2864 546 74 8 1PT-NBOO3H PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 R1C R.B. A 2A 1H21-PO26 NB35 TRANSMITTER MOUNT PB E-2864 546 NB 1PT-NBOO3K PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 R1C R.B. A 2A 1H22-PO26 NB35 TRANSMITTER MOUNT PB E-2864 546 NB 1PT-NBOO3L PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RIC R.B. A 2A 1H22-PO26 NBJS 1RANSMITTER MOUNT PB E-2864 546 NB 1PT-NBOO3P PRTSSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 RfC R.B. A 2A 1H22-PO26 NB35 TRANSMITTER MOUNT PB E-2864 546 NB IPT-NBOO3R PRESSURE ROSF- 1152GP9A22- H-2809 E-148-1 E-24 R1C R.B. A 2A 1H22-PO26 NB35 1RANSMITTER MOUNT PB E-2864 546 NB iPT-NBOO3S PRESSURE ROSE- 1152GP9A22- H-2809 E-148-1 E-24 R1C R.B. A 2A 1H22-PO26 NB35 1RANSMITTER MOUNT PB E-2864 546 NR 1C51-dOO4A VALVL GUIDE G.E. 136C1302 H-2210 E-946 E/25 R2B R.B. N/A A EX EOO8 TUBE 525 NR 1C51-dOO4B VALVE GUIDE G.E. 136C1302 H-2210 E-146 E/25 R2B R.B. N/A A EX EOO8 100E 525 NR 1C51-dOO4C VALVE GUIDE G.E. 136C1302 H-2210 E-146 E/25 R2B R.B. N/A A EX EOO8 TUBE 525 NR 1C51-dOO4D VALVE GUIDE G.E. 136C1302 H-2210 E-146 E/25 R2B R.B. N/A A EX EOO8 TUBE 525
.PAGE 34 0F 76 to O
(9 M SARGENT&l. UNDY ENGINEERG -
37 4 r4 - D PROJECT NUMBER 41;O-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
.....................==r................................................................. . .......... .... .... .... ........... ....,
NR 1C51-KOO2 A VOLTAGE G.E. 163C1263 H-2210 E-145-1 C/16 R2A R.B. A EX 1H22-PO30 EOO8 PREAMP E-2877 525 NR 1C51-KOO2 B VOLTAGE G.E. 163C1263 H-2210 E-145-1 B/19 R2A R.B. # EX 1H22-PO31 EOO8 PREAMP E-2877 525 NR 1C51-KOO2 C VOLTAGE G.E. 163C1263 H-2210 E-145-1 B/26 R2A R.B. A EX 1H22-PO32 EOO8
. PREAMP E-2877 525 NR 1C51-KOO2 D VOLTAGE G.E. 163C1263 H-2210 E-145-1 C/26 R2A R.B. A EX 1H22-PO33 EOO8 PREAMP E-2877 525 NR 1C51-KOO2 E VOLTAGE G.E. 163C1263 H-2210 E-145-1 C/16 R2A R.B. A EX 1H22-PO30 EOO8 PREAMP E-2877 525 NR 1C51-kOO2 F VOLTAGE G.E. 163C1263 H-2210 E-145-1 B/19 R2A R.B. A EX 1H22-PO31 EOO8
. PREAMP E-2877 525 NR 1C51-KOO2 G VOLTAGE G.E. 163C1263 H-2210 E-145-1 B/26 R2A R.B. A EX 1H22-PO32 EOO8 PREAMP E-2877 525 NR 1C51-KOO2 H VOLTAGE G.E. 163C1263 H-22tO E-145-1 C/26 R2A R.B. A EX 1H22-PO33 EOOS PREAMP E-2877 525 NR 1C51-NOO2 A DETECTOR G.E. It2C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 NR 1C51-NOO2 B DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 NR 1C51-NOO2 C DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 NR 1C51-NOO2 0 DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 NR 1C51-NOO2 E DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 NR 1C51-NOO2 F DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 NR 1C55-NOO2 G DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877
.PAGE 30 0F 76 to O
S SARGENT&LUNDY 15f 4OlNEE51D .
30 PROJECT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL /RDW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET NR f t S t NOO2 H DETECTOR G.E. 112C3144 H-2210 E-181 C1 DRYWEL A EX EOO8 E-2877 PC 1HY-PC500 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC501 A U Y. RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC502 AUX RELAY G.E. 12HMA11B11 H-2881 E-146-1 E/17 R4A R.B. A 2A iPL79J PC01 E-2275/2276 479 PC IHY-PC503 AUX RELAY G.E. 12HMA11B11 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01
. E-2275/2276 479 PC 1HY-PC504 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01
. E-2275/2276 479 PC 1HY-PC505 AUX RELAY G.E. 12HMA11B11 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC506 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC507 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PCO1 E-2275/2276 479 PC 1HY-PC508 AUX RELAY G.E. 12HMA11B11 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC509 AUX RELAY G.E. 12HMA11B11 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC510 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC511 AUX RELAY G.E. 12HMA11B11 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-PC512 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PC01 E-2275/2276 479 PC 1HY-FC513 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1Pl79J PC01 E-2275/2276 479
$PAGE 36 0F 76 w
n SARGENT&LUNDY ENGINEERS -
30 PROJECT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010 ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/%DD 0588 DATA eSY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
.................................................. ..............................................,.n...... . ... ..................... .
PC IHY-PC514 AUX RELAY G.E. 12HMA11811 H-2881 E-146-1 E/17 R4A R.B. A 2A 1PL79J PCOI E-2275/2276 479 PC 1HY-PC515 AUX RELAY G.E. 12HMA11011 H-2881 E-146-1 E/17 R4A R.B. A 2A iPL79J PC01
. E-2275/2276 479 PC 1PCOO5A LIMIT SWITCH LICON 65-430140 H-2194 E/23 C1 DRYWEL N/A A 2A PCO2
. OPEN POS. 523 PC 1PCOO5A LIMIT SWITCH LICON 65-430140 H-2194 E/23 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523 PC IPCOO58 LIMIT SWITCH LICON 65-430140 H-2194 C/25 C1 DRYWEL N/A A 2A PCO2 OPEN POS. 523 PC 1PCOO58 LIMIT SWITCH LICON 65-430140 H-2194 C/25 C1 DRYWEL N/A A 2A PCO2
. CLOSED POS. 523 PC 1PCOOSC LIMIT SWITCH LICON 65-430140 H-2194 B/21 C1 DRYWEL N/A A 2A PCO2 OPEN POS. 523 PC 1PCOOSC LIMIT SWITCH LICGN 65-430140 H-2194 B/27 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523 PC 1PCOOSD LIMIT SWITCH LICON 65-430140 H-2194 C/18 C1 DRYWEL N/A A 2A PCO2
. OPEN POS. 523 PC 1PCOO5D LIMIT SWITCH LICON 65-430140 H-2194 C/18 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523 PC 1PCOOGA LIMIT SWITCH LICON 65-430140 H-2194 E/23 C1 DRYWEL N/A A 2A PCO2 CPEN POS. 523 PC iPCOO6A LIMIT SWITCH LICON 65-430140 H-2194 E/23 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523 PC IPCOO68 LIMIT SWITCH LICON 65-430140 H-2194 C/25 C1 DRYWEL N/A A 2A PCO2
. OPEN POS. 523 PC 1PCOO6B LIMIT SWITCH LICON 65-430140 H-2194 C/25 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523 PC 1PCOO6C LIMIT SWITCH LICON 65-430140 H-2194 B/21 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523
.PAGE 37 0F 76
'cS El SARGENT&LUNDY
= ENotNEEf1D .
40 (O te 'O PROJECT NUMBER 4130-05
+
DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC UR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M 130. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET PC 1PCOO6C LIMIT SWITCH LICON 65-430140 H-2194 B/21 C1 DRYWEL N/A A 2A PCO2 OPEN POS. 523 PC IPCOO60 LIMIT SWITCH LICON 65-430140 H-2194 C/18 C1 DRYWEL N/A A 2A PCO2 OPEN POS. 523 PC 1PCOO6D LIMIT SWITCH LICON 65-430140 H-2194 C/18 C1 DRYWEL N/A A 2A PCO2 CLOSED POS. 523 PC 12L-PCOO1 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOOG INDICATION E-2276 475 PC 12L-PCOO2 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX iPL79J EOO6 INDICATION E-2276 475 PC 1ZL-PCOO4 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6 INDICATION E-2275 475 PC 12L-PCOO5 VALuE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6 INDICATION E-2275 475 PC 12L-PCOO7 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.D. A EX 1PL79J EOO6 INDICATION E-2276 475 PC 12L-PCOO8 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOOG
. INDICATION E-2276 475 PC 12L-PC010 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX iPL79J EDO6 INDICATION E-2275 475 PC 12L-PCO11 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6 INDICATION E-2275 475 PC 1ZL-PCO13 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A H.B. A EX 1PL19J EOO6 INDICATION E-2276 475 PC 12L-PC014 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6 INDICATION E-2276 475 PC 1ZL-PCOt6 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6
. INDICATION E-2275 475 PC 12L-PC017 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX iPL79d EOO6 INDICATION E-2275 475
.PAGE 38 0F 76 o
t9 SARGENTfdUNDY
=ENGINTERD _
41 [ / PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT QUALIFICATION D01326 e PLANT ID SPEC OR COMPONENT / MODEL E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET PC 12L-PCO19 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6 INDICATION E-2276 475 PC 12L-PCO2O VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6
. INDICATION E-2276 475 PC 12L-PCO22 VALVE POS G.E. ET-16 H-2881 E-146-4 E/17 R4A R.B. A EX iPL79J EOO6
. INDICATIDt4 E-2275 475 PC 12L-PCO23 VALVE POS G.E. LT-16 H-2861 E-146-4 E/17 R4A R.B. A EX 1PL79J EOO6
. INDICATION E-2275 475 PR 1D13-NOO3 A DETECTOR G.E. 237X731 H-2210 E-144 E/21 R3A R.B. A EX EOO4 E-2914 503 PR 1013-NOO3 B DETECTOR G.E. 237X731 H-2210 E-144 E/21 R3A R.B. A EX EOO4 E-2914 503 PR 1013-NOO3 C DETECTOR G.E. 237X731 H-2210 E-144 E/21 R3A R.B. A EX EOO4 E-2914 503 PR 1D13-NOO3 D DETECTOR G.E. 237X731 H-2210 E-144 E/21 R3A R.B. A EX EOO4 E-2914 503 PR 1D13-NO19 A DETECTOR G.E. 194X927 H-2210 E-151 A/23 R6A R.B. A EX EOO4 E-2914 593 PR ID13-NO19 B DETECTOR G.E. 194X927 H-2210 E-151 A/23 R6A R.B. A EX EOO4
. E-2914 593 PR 1D13-NO19 C DETECTOR G.E. 194X927 H-2210 E-151 A/23 R6A R.B. A EX EOO4 E-2914 593 PR 1D13-NO19 D DETECTOR G.E. 194X927 H-2210 E-151 A/23 R6A R.B. A EX EOO4 E-2914 593 RD 1C11-DOO1-117 SCRAM PILOT ASCO HVA 90-405 H-2210 E-147 C/16 RfC R.B. N/A A 2A RD01 SOLENOIDS 546 RD 1C11-DOO1-118 SCRAM PILOT ASCO HVA 90-405 H-2210 E-147 C/16 R1C R.B. N/A A 2A RD01 SOLENOIDS 546 RD 1C11-FOO9 PILOT ASCO HT8323-22 H-2210 E-147 B/16 R1C R.B. A 2A M-56-3 RDO3 SOLENOID E-2673 546
.PAGE 39 0F 76 to S
n SARGENT&LUNDY M NGINNER fJ .,
42 (9 <O 4 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT CUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.1. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET RD 1C11-FO10 LIMIT SWITCH NAMCO SL-3C-82 H-2210 B/16 R1C R.B. A 2A M-56-3 RDO2
. OPEN POS. 546 RD 1C11-FO10 LIMIT SWITCH NAMCO SL-3C-82 H-2210 B/16 R1C R.B. A 2A M-56-3 RDO2
. CLOSED POS. 546 RD 1C11-FO11 LIMIT SWITCH NAMCO SL-3C-82 H-2210 B/18 R1C R.B. A 2A M-56-3 RDO2
. OPEN POS. 546 RD 1C11-FO11 LIMIT SWITCH NAMCO SL-3C-B2 H-2210 B/18 R1C R.B. A 2A M-56-3 RDO2 CLOSED POS. 546 RD 1C11-F110A SCRAM BACKUP ASCO HT8316C37 H-2210 E-147 A/18 RIC R.B. A 2A RDOS SOL. VALVE E-2673 548 RD 1C11-F1108 SCRAM BACKUP ASCO HT8316C37 H-2210 E-147 A/18 R1C R.B. A 2A RDOS SQL. VALVE E-2673 548 RD 1C11-NO13 A LEVEL SWITCH MAGNET 159C4361 H-2210 B/18 R1C R.B. A 2A RC04
-ROL 5.O-751 560 RD 1C11-NO13 B LEVEL SWITCH MAGNET 159C4361 H-2210 B/19 R1C R.B. A 2A RDO4
. -ROL 5.O-751 553 RD 1C11-NO13 C LEVEL SWITCH MAGNET 159C4361 H-2210 B/25 R1C R.B. A 2A RDO4
. -ROL 5.0-751 559 RD 1C11-NO13 D LEVEL SWITCH MAGNET 159C4361 H-2210 B/25 R1C R.B. A 2A RDO4
-ROL 5.O-751 559 RD 1C11-NO13 E LEVEL SWITCH MAGNET 159C4361 H-2210 B/18 R1C R.B. A 2A RDO4
-ROL 5.O-751 553 RD 1C11-NO13 F LEVEL SWITCH MAGNET 159C4361 H-2210 B/18 R1C R.B. A 2A RDO4
-ROL 5.O-751 553 RE 1REO48 SOLENDID ASCO HT8320A175 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RE01 E-2223 477 RE 1REO48 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 REO2 CLOSED POS. E-2223 477 RE 1REO48 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RE02 OPEN POS. E-2223 477
.PAGE 40 0F 76 e
O m n SARGENT&LUNDY ENGINEEf10 -
03 PROJECT NU.ABER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 OATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D No. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e................................................................................ ... . ....................... . ................
NL 1RE049 SOLENOI" ASCO HTS 320A175 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 REO1
. E-2223 477 RE 1RE049 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 REO2
. CLOSED POS. E-2223 477 RE 1RE049 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RE02
. OPEN POS. E-2223 477 RF 1RFOO1 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RFO1
. OPEN POS. E-2223 475 ,
RF 1RFOO1 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RF01
. CLOSED POS. E-2223 475 RF 1RFOO1 SOLENOID ASCO HT8320A175 H-2266 E-142 D/'5 R4A R.B. A A 2A M-62-1 RFO2
. E-2223 475 RF 'RFOO2 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RF01 OPEN POS. E-2223 475 RF 1RFOO2 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RFO1
. CLOSEL POS. E-2223 475 RF 1RFOO2 SOLENOID ASCO HT8320A175 H-2266 E-142 D/15 R4A R.B. A A 2A M-62-1 RF02 E-2223 475 RH 1E12-COO 2A PUMP G.E. SK6328X- H-2210 E-141 B/26 R4B R.B. A 2A RHO 1 MOTOR C266A 475 RH 1E12-COO 2B PUMP G.E. SK6328X- H-2210 E-142 E/26 R4E R.B. A 2A RHO 1 MOTOR C266A 475 RH 1E12-COO 2C PUMP G.E. 5K6328X- H-2210 E-142 D/27 R4E R.B. A 2A RHO 1 MOTOR C266A 475 RH 1E12-COO 3 PUMP WEST. 74D24113 H-2185 E-142 E/27 R4E R.B. A A 2A RHO 2 MOTOR 475 RH 1E12-FOO3A MOTOR OPER- LIMIT SMB-0-25 H-2811 E-141 C/28 R4F R.B. 2A M-51-4 RHO 4
. ATED VALVE E-1458 475 RH 1E12-FOO3B MOTOR OPER- LIMIT SM8-0-25 H-2811 E-142 D/28 R4F R.B. 2A N-51-4 RHO 4 ATED VALVE E-1478 475
.PAGL 41 OF 76 (D
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PROJECT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION dot 326
- PLANT ID COMPONENT / M00lL SPEC 02 E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUF1E . B/M NO. .W/0 NO.
ELEVATN IN OUT GUILD LEV PASS REV CAT. SHEET RH 1E12-FOO4A MOTOR OPER- LIMIT SMB-T 40 H-2811 E-141 C/25 R4A R.R. A 2A M-51-1 RHOS
. ATED VALVE E-1462 475 RH 1E12-FOO4B MOTOR OPER- LIMIT SMB-t-40 H-2811 E-142 E/25 R4A R.B. A 2A M-51-2 RHOS
. ATED VALVE E-1474 475 RH 1E12-FOO4C MOTOR OPER- LIMIT SMB-t-40 H-28tt E-142 E/25 R4A R.B. A 2A M-51-3 RHO 5
. ATED VALVE E-1473 475 RH 1E12-FOO6A MOTOR OPER- LIMIT SMB-O-40 H-2811 E-141 B/25 R4B R.B. 2A M-51-1 RHO 6
. ATED VALVE E-1458 475 RH 1E12-FOO68 MOTOR OPER- LIMIT SMB-O-40 H-2811 E-142 E/25 R4E R.B. 2A M-51-2 RHO 7
. ATED VALVE E-1473 475 RH 1E12-FOO8 MOTOR OPER- LIMIT SMB-2-60 H-2264 E-145 B/23 R2A R.B. A 2A M-51-3 RHOS
. ATED VALVE E-2331 525 RH 1E12-FOO9 MOTOR OPER- LIMIT SMB-2-60 H-2264 E-145 C/22 C1 DRYWEL A 2A M-51-3 RHO 9 ATED VALVE E-1476 524 RH 1E12-FO11A MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-141 C/27 R4F R.B. A A 2A M-51-1 RH10
. ATED VALVE E-1565 475 RH 1E12-F0118 MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-142 D/28 R4F R.B. A A 2A M-51-2 RHiO
. ATED VALVE E-1575 475 RH 1E12-F014A MOTOR OPER- LIMIi SMB-OOO-2/ H-2265 E-141 C/27 R4F R.B. A A 2A M-30-2 RH11 ATED VALVE HIBC E-1460 475 RH 1E12-FO14B MOTOR OPER- LIMIT SMB-OOO-2/ H-2265 E-142 D/28 R4F R.B. A A 2A M-30-2 RHtt
. ATED VALVE HIBC E-1475 475 RH IE12-FOt6A MOTOR OPER- LIMIT SMB-O-25 H-2811 E-145 B/23 R2A R.B. A 2A M-51-1 RH12 ATED VALVE E-1462 525 l RH 1E12-F016B MOTOR OPER- LIMIT SMB-O-25 H-2811 E-148 E/23 R1C R.B. A 7A M-51-2 RH13 ATED VALVE E-1475 546 RH 1E12-F017A MOTOR OPER- LIMIT SMB-O-25 H-2811 E-145 B/23 R2A R.B. A 2A M-51-1 RH14 ATED VALVE E-1462 525 RH 1E*2-F0178 MOTOR OPER- LIMIT SMB-O-25 H-2811 E-148 E/23 Ric R.B. A 2A M-51-2 RH15 ATED VALVE E-1475 546
.PAGE 42 OF 76 O
M n SARGENT&LUNDY l .. . ....
45 b I PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. 2IMMER EOUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ElEVATN IN DUT BUILD LEV PASS REV CAT. SHEET RH 1Ll2-F021 MOTOR OPER- LIMIT SMB-2-25 H-2263 E-148 E/23 Ric R.B. A 2A M-51-3 RH16
. ATED VALVE E-1475 546 RH 1E12-FO23 MOTOR OPER- LIMIT SMB-1 H-2820 E-149 B/25 RSA R.B. A 2A M-51-2 RH17 ATED VALVE E-2335 570 RH 1E12-F024A MOTOR OPER- LIMIT SMB-2-25 H-2263 E-143 C/18 R3A R.B. N/A A 2A M-51-1 RH18
. ATED VALVE E-1565 503 RH 1E12-FO248 MOTOR OPER- LIMIT SMB-2-25 H-2263 E-143 C/25 R3A R.B. N/A A 2A M-51-2 RH18 ATED VALVE E-1575 503 RH 1E12-F026A MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-141 C/27 R4F R.B. A A 2A M-51-4 RH19 ATED VALVE E-1460 475 RH 1E12-FO268 MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-142 D/28 R4F R.S. A A 2A M-51-4 RH19 ATED VALVE E-1477 475 RH 1E12-FO27A MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-141 A/25 R4B R.B. A A 2A M-51-1 RH2O ATED VALVE E-1460 475 RH 1E12-F0278 MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-142 F/25 R4E R.B. A A 2A M-51-2 RH21 ATED VALVE E-1477 475 RH 1E12-F04e iOTOR OPER- LIMIT SMB-OOO H-2263 E-142 D/28 R4F R.B. A A 2A M-51-2 RH22 ATED VALVE E-1460 475 RH 1E12-FO41A SOLENOID ASCO WPHTX834472 H-2267 E-147 C/23 C. i DRYWEL N/A P EX M-51-1 EOO5 E-2671 574-8 RH 1E12-F041A LIMIT SWITCH NAMCO EA74010000 H-2267 E-147 C/23 C1 DRYWEL N/A P EX EOO5 E-2671 574-8 RH 1E12-F041A OPkN/CLOSE MAG- MPS-15 H-2267 E-147 C/23 C1 DRYWEL N/A A 2A RHO 3 POS SWITCH LOCK E-2671 574-8 RH 1E12-FO41B SOLENOID ASCO WPHTX834472 H-2267 E-147 D/23 C1 DRYWEL N/A P EX M-51-2 EOO5 E-2671 574-8 RH 1E12-FO418 LIMIT SWITCH NAMCO EA740tOOOO H-2267 E-147 D/23 C1 DRYWEL N/A P EX EOO5
. E-2671 574-8 RH 1E12-FO41B OPEN/CLOSE MAG- MPS-15 H-2267 E-147 D/23 C1 DRYWEL N/A A 2A RHO 3
. POS SWITCH LOCK E-2671 574-8
.PAGE 43 0F 76 to O
M M SARGENT&LUNDY ENGINEERB -
43 g q A 1L) Id \ PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EOUIPMENT QUALIFICATION D01326
- PLANT ID COM00NENT/ MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUI MFR NUMBER B/M NO. W/D No. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e.. .....................' MENT.. ....................... . .............................. . .............. .... ...............................
RH 1E12-FO41C OPEN/CLOSE MAG- MPS-15 H-2267 E-147 D/21 C1 DRYWEL N/A A 2A RHO 3 POS SWITCH LOCK E-2671 574-8 RH 1E12-FO41C SOLENDID ASCO WPHTX834472 H-2267 E-147 D/21 C1 DRYWEL N/A P EX M-51-3 EOO5 E-2r'1 574-8 RH 1E12-FQ41C LIMIT SWITCH NAMCO EA74010000 H-2267 E- +7 D/21 C1 DRYWEL N/A P EX EOO5
. E-2671 574-8 RH 1E12-FO42A MOTOR OPER- LIMIT SMB-O H-2264 E-147 B/23 R1B R.B. A 2A M-51-1 RH23
. ATED VALVE E<1461 546 RH 1E12-FO428 MOTOR OPER- LIMIT SMB-O H-2264 E-148 E/23 RIC R.B. A 2A M-51-2 RH24
. ATED VALVE E-1476 546 RH 1E12-F042C MOTOR OPER- LIMIT SMB-O H-2264 E-148 E/23 RfC R.B. A 2A M-51-3 RH24
. ATED VALVE E-1478 546 RH 1E12-FO47A MOTOR OPER- LIMIT SMB-O-25 H-2811 E-143 C/28 R4F R.B. A 2A M-51-4 RH25 ATED VALVE E-1565 503 RH 1E12-F047B MOTOR OPER- LIMIT SMB-O-25 H-2811 E-144 D/28 R4F R.B. A 2A M-51-4 RH25
. ATED VALVE E-1575 503 RH 1E12-F048A MOTOR OPER- LIMIT SMB-3 H-2820 E-143 B/2tl R4F R.B. A 2A M-51-4 RH26
. ATED VALVE E-1461 503 RH 1E12-FO488 MOTOR OPER- LIMIT SMB-3 H-2820 E-142 D/28 R4F R.B. A 2A M-51-4 RH26
. ATED VALVE E-1479 505 RH 1E12-FO49 MOTOR OPER- LIMIT SP3-OOO-5 H-2264 E-142 D/28 R4F R.B. A A 2A M-51-2 RH27 ATED VALVE E-1478 475 RH 1E12-FO50A OPEN/CLOSE MAG- MPS-15 H-2267 E-146 C/21 C1 DRYWEL A 2A RHO 3
. POS 5, WITCH LOCK E-2671 533-10 RH 1E12-FO508 OPEN/CLOSE MAG- MPS-15 H-2267 E-146 D/23 C1 DRYWEL A 2A RHO 3 POS SWITCH LOCK E-2671 533-10 RH 1F12-FO51A SOLENDID ASCO HT8320A175 H-2266 E-143 C/28 R4F R.B. N/A A 2A M-51-4 RH38 E-2671 503 RH 1E12-FO51B SOLENDID ASCO HT8320A175 H-2266 E-144 D/28 R4F R.B. N/A A 2A M-51-4 RH38 E-2671 503
.PAGE 44 0F 76 ED O
M M I SARGENT&LUNDY
=GNOINGERS .
- _ = - - . - _ _ _ _ .
47 r"% /" /S k]A k PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUM8FR EQUIPMENT MFR NUMBER 8/M NO. W/D NC. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
....a.......................................................................... . ....... . ...... ... . .... . ... . ......................
RH 1E12-FOS 2A MOTOR OPER- LIMIT SMS-2 H-2820 E-143 C/28 R4F R.B. A 2A M-51-4 RH28
. ATED VALVE E-1565 503 RH 1E12-FOS 2B MOTOR OPER- LIMIT SMB-2 H-2820 E-144 D/28 R4F R.B. A 2A M-51-4 RH28 ATED VALVE E-1575 503 RH 1E12-F053A MOTOR OPER- LIMIT SMB-3 H-2820 E-145 C/18 R2A R.B. A 2A M-51-1 RH29 ATED VALVE E-1570 525 RH 1E12-FO538 MOTOR OPER- LIVIT SMB-3 H-2820 E-145 C/25 R2A R.B. A 2A M-51-2 RH29 ATED VALVE E-1570 525 RH 1E12-F060A LIMIT SWITCH NAMCO EA-170 H-2852 E-141 C/28 R4B R.B. A A 2A M-51-4 RH42 OPEN POS. 46302 E-2917 475 RH 1E12-FO60A LIMIT SWITCH NAMCO EA-170 H-2852 E-141 C/28 R4B R.B. A 2A F-51-4 RH42 CLOSED POS. 46'O2 a E-2917 497 RH 1E12-F060A SOLENOID ASCO HTX8320A22V H-2852 E-141 C/28 R4B R.B. A 2A M-51-4 RH39 E-2917 497 RH 1E12-FO500 LIMIT SWITCH NAMCO EA-170 H-2852 E-141 D/28 R4E R.B. A 2A M-51-4 RH43
. CLOSED POS. 46302 E-2917 497 RH 1E12-FO600 50LEHOID ASCO HTX8320A22V H-2852 E-141 D/28 R4E R.B. A 2A M-51-4 RH40 E-2917 497 RH 1E12-FO608 LIMIT SWITCH NAMCO EA-170 H-2852 E-141 D/28 R4E R.B. A A 2A M-51-4 RH43 ,
OPEN POS. 46302 E-2917 475 RH 1E12-F064A MOTOR OPER- f.IMIT SMB-OOO-5 H-2264 E-141 C/27 R4B R.B. A A 2A M-51-1 CH30 ATED VALVE E-1760 475 RH 1E12-F064B MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-142 E/27 R4E R.B. A A 2A M-51-2 RH31 ATED VALVE E-1751 475 RH 1E12-F064C MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-142 E/27 R4E R.B. A A 2A M-51-3 RH31 ATED VALVE E-1751 475 RH 1F12-FO65A SOLENOID ASCO HT8320A175 H-2266 E-141 C/28 R4F R.B. A A 2A M-51-4 RH41 E-2671 475 RH 1E12-FO658 SOLENOID ASCO HT8320A175 H-2266 E-142 D/28 R4F R.B. A A 2A M-51-4 RH41 E-2671 475
.PAGE 45 0F 76 to O
(7 M SARGENT&LUNDY
43 ,- tv tv v PROJECT NUMBER 4130-05 DATE 22 DEC 1
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET RH 1E12-FO68A MOTOR OPER- LIMIT SMB-OOO- 2/ . H-22G5 E-141 .C/28 R4F R.B. A 'A 2A M-30-2 RH32
. ATED VALVE HIBC E-1461 475 RH 1E12-FO688 MOTOR OPER- LIMIT SMB-OOO-2/ H-2265 E-142 .D/28 R4F R.B. A A 2A M-30-2 RH32
. ATED VALVE HIBC E-1478 475 a RH 1E12-FO7JA MOTOR OPER- LIMIT SM3-OOO H-2852 E-143 C/28 R4F R.B. N/A A 2A M-51-4 RH33 ATED VALVE E-1566 503 RH 1E12-F0738 MOTOR OPER- LIMIT SMB-OOO H-2852 E-144 D/28 R4F R.B. N/A A 2A M-51-4 RH33 ATED VALVE E-1576 503 RH 1E12-FO74A MOTOR OPER- LIMIT SMB-OOO H-2852 E-143 C/28 R4F R.B. N/A A 2A M-51-4 RH34 ATED VALVE E-1567 503 RH 1E12-FO748 MOTOR OPER- LIMIT Sk3-OOO H-2852 E-144 D/28 R4F R.B. N/A A 2A M-51-4 RH34 1
ATED VALVE E-1576 503 RH 1E12-FC7!,A SOLENGID ASCO HTX8320A22V H-2852 E-141 C/28 R4B R.B. A 2A M-51-4 RH39 E-2917 475 RH 1E12-FO75A LIMIT SWITCH NAMCO 1A-170 H-2852 E-141 C/26 R4B R.B. A A 2A, M-51-4 RH42 OPEN POS. 46302 E-2917 475 RH 1E12-FO75A LIMIT SWITCH NAMCO EA-170 H-2852 E-141 C/28 R4B R.B. A 2A RH42 CLOSED POS 46302 E-2917 475 i RH 1E12-F075B SOLENOID ASCO HTX8320A22V H-2852 E-141 D/28 R4E R.B. A 2A RH40 E-2917 475 RH 1E12-F0758 LIMIT SWITCH NAMCO EA-170 H-2852 E-141 D/28 R4E R.B. A A 2A M-51-4 RH43 OPEN POS. 46302 E-2917 475 RH 1E12-FO758 LIMIT SWITCH NAMCO EA-170 H-2852 E-141 D/28 R4E R.B. A 2A O-51-4 RH43 CLOSED POS. 46302 E-2917 497 RH 1E12-F087A MOTOR OPER- LIMIT SMB-OO H-2820 E-143 C/28 R4F R.B. A 2A M-51-4 RH35 ATED VALVE E-1571 503 RH 1E12-FOa7B MOTOR OPER- LIMIT SMB-OO H-2820 E-144 D/28 R4F R.B. A 2A M-51-4 RH35 ATED VALVE E-1577 503 i RH 1E12-FO99A MOTOR OPER- LIMIT SMB-OOO-2 H-2852 E-145 C/21 C1 DRYWEL N/A A 2A M-51-1 RH36 ATED VALVE E-1749 524 i
.PfGE 46 0F 76 e
1 o S SARGENT&LUNDY WNOINEER9.
49 PROJECT NUM8ER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M WO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET RH 1E12-FO998 MOTOR OPER- LIMIT SMB-OOO-2 H-2852 E-146 C/23 C1 DRYWEL N/A A 2A M-51-2 RH36
. ATED VALVE E-1576 525 RH 1E12-F338A MOTOR OPER- LIMIT SMB-OOO H-2852 E-147 C/22 C1 DRYWEL N/A A 2A M-51-1 RH37
. ATED VALVE E-17GO 570 RH 1E12-F338B MOTOR OPER- LIMIT SMB-OOO H-2852 E-147 D/22 C1 DRYWEL N/A A 2A M-51-2 RH37 ATED VALVE E-1751 570 RH 1E12-F338C MOTOR OPER- LIMIT SMB-OOO H-2852 E-147 D/22 C1 DRYWEL N/A A 2A M-51-3 RH37
. ATED VALVE E-1751 570 RH 1E12-NOO7 A FLOW TRANS. BAILEY 163C1183 H-2210 E-141-1 B/26 R4B R.B. P 28 1H't2-PO 18 RH44 555 E-2844 475 RH 1E12-NOO7 B FLOW TRANS. BAILEY 163C1183 H-2210 E-142 E/28 R4E R.B. P 2B 1H22-PO21 RH45
. 555 E-2847 475 RH 1E12-NOO9 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-147 A/24 RfA R.B. A 2A RH49 IND. SWITCH 288A E-2671 546 RH 1E12-NOO9 B DIFF. PRESS. BARTON 145C3OO9 H-2210 E-148 F/23 Ric R.B. A 2A RH50
. IND. SWITCH 288A E-2671 546 RH 1E12-NOO9 C DIFF. PRESS. BARTON 145C3OO9 H-2210 E-148 F/23 RfC R.B. A 2A RH50
. IND. SWITCH 288A E-2671 546 RH 1E12-NO10 A DIFF. PRESS. BARTON 145C3OO8 H-2210 E-141-1 B/26 R4B R.B. A 2A 1H22-PO18 RH54
. IND. SWITCH 289A E-2844 475 RH 1E12-NO10 B DIFF. PRESS. BARTON 145C3OO8 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH55
. IND. SWITCH 289A E-2847 475 RH 1E12-NO10 C DIFF. PRESS. BADTON 145C3OO8 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH55
. IND. SWITCH 289A E-2847 475 RH 1E12-NO13 FLOW TRANS. Bf! LEY 163C1183 H-2210 E-150 F/24 RSA R.B. P 2B RH46 555 E-2671 570 RH 1E12-NO15 A FLOW TRANS. BAILEY 163C1183 H-2210 E-141-1 B/26 R4B R.B. P 2B 1H22-PO18 RH44
. 555 E-2844 475 .
RH 1E12-NO15 8 FLOW TRANS. BAILEY 163C1183 H-2210 E-142 E/28 R4E R.B. P 2B 1H22-PO21 RH45 555 E-2847 475
.PAGE 47 0F 76 m
O M M SARGENT&LUNDY
-eNescamens . l
50 l ( PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER FOUIPMENT QUALIFICATION DO1326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADD 0588 OATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/O NO. ELEVATN IN OUT BUILO LEV PASS REV CAT. SHEET e........................................................................................ . ................... ................
RH IE12-NO15 C FLOW TRANS. BAILEY 163C1183 H-22tO E-142 E/28 R4E R.B. P 28 1H22-PO21 RH45
. 555 E-2847 475 RH 1E12-NO16 A PRESS. SWITCH STATIC 145C3011 H-2210 E-141-1 B/26 R4B R.B. A 2A 1H22-pot 8 RH56 0-RING SN-AA3 E-2847 475 RH 1E12-NOt6 B PRESS. SWITCH STATIC 145C3011 d-2210 E-142 E/28 RAE R.B. A 2A 1H22-PO21 RH57 0-RING SN-AA3 E-2847 475 RH 1E12-NOt6 C PRESS. SWITCH STATIC 145C3011 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH57 0-RING 5N-AA3 E-2847 475 RH IE12-NO19 A PRESS. SWITCH STATIC 145C3011 H-2210 E-141-1 B/26 R4B R.B. A 2A 1H22-PO18 RH56
. 0-RING SN-AA3 E-2844 475 RH 1E12-NO19 B PRESS. SWITCH STATIC 145C3011 H-2210 E-142 E/28 R4F R.B. A 2A 1H22-PO21 RH57 O-RING SN-AA3 E-2847 475 RH 1E12-NO19 C PRESS. SWITCH STATIC 145C3011 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH57 O-RING SN-AA3 E-2847 475 RH 1E12-NO22 A PRESS.INC. ROBERT 163C1185 H-2210 E-141-1 B/26 R4B R.B. P 28 1H22-PO18 RH58 SWITCH -SHAW SP-222C E-2844 475 RH 1E12-NO22 B PRESS.IND. ROBERT 163C1185 H-2210 E-142 E/28 R4E R.B. P 28 1H22-PO21 RH59 SWITCH -SHAW SP-222C E-2847 475 RH 1E12-NO22 C PRESS.IND. ROBERT 163C1185 H-2210 E-142 E/28 R4E R.B. P 2B 1H22-PO21 RH59
. SWITCH -SHAW SP-222C E-2847 475 RH 1E12-NO26 A PRESS.TRANS. BAILEY 163C1186 H-2210 E-141-1 B/26 R4B R.B. P 2B 1H22-PO18 RH47 556 E-2844 475 RH 1E12-NO26 B PRESS.TRANS. BAILEY 163C1186 H-2210 E-142 E/28 R4E R.B. P 2B 1H22-PO21 RH48 556 E-2847 475 RH 1E12-NO28 PRESS.TRANS. BAILEY 163C1186 H-2210 E-142 E/28 R4E R.B." P 2B 1H22-PO21 RH48 556 E-2847 475 RH IE12-NO29 A DIFF. PRESS. BARTON 145C3OO9 H-2210 E-141-1 B/26 R4B R.B. A 2A 1H22-PO18 RH51 SWITCH 288A E-2844 475 RH 1E12-NO29 8 DIFF. PRESS. BARTON 145C3OO9 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH52 SWITCH 288A E-2847 475
$PAGE 40 OF 76 to O
n SARGENT&LUNDY ENG1HEERD.
S1 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/AOD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
.....e===========,m============,s=====, . wa======,me==ames,mes====.................. ......-m==, we,e===, mas,====,emommesmes=,emen, RH 1E12-NO32 A PRESS. SWITCH BARKS- 164C5359 H-2210 E-141-1 B/26 R4B R.B. A 2A 1H22-PO18 RH60 DALE BITA12SS-GE E-2844 475 RH 1E12-NO32 8 PRESS. SWITCH BARKS- 164C5359 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH61 DALE B1TM12SS-GE E-2847 475 RH 1E12-NO33 A PRESS. SWITCH BARKS- 164C5359 H-2210 E-141-1 B/26 R4B R.B. A 2A 1H22-PO18 RH60 DALE B1TM12SS-GE E-2844 475 9H 1E12-NO33 8 PRESS. SWITCH BARKS- 164C5359 H-2210 E-142 E/28 R4E R.B. A 2A 1H22-PO21 RH61 DALE B1TM12SS-GE E-2847 475 RH 1FDS-RHOO7A PRESSURE BARTON 288A H-2866 D/25 R3A R.B. A 2A 1PX71J RH53 DIFFER SWITCH 503 RH 1PDS-RHOO78 PRESSURE BARTON 288A H-2866 D/25 R3A R.B. A 2A 1PX71J RH53
. DIFFER SWITCH 503 RH 1PDS-RHOOBA PRESSURE BARTON 288A H-2866 B/20 R3A R.B. A 2A iPX72d RH53 DIFFER SWITCH 503 RH 1PDS-RHOOBB PRESSURE BARTON 288A H-2866 B/20 R3A R.B. A 2A 1PX72J RH53 DIFFER SWITCH 503 RH 1PSH-RHOO5A PRESSURE BARTON 288A H-2866 D/25 R3A R.B. A 2A 1PX71J RH53 SWITCH-HIGH 503 RH 1PSH-RHOO58 PRESSURE BARTON 288A H-2866 D/25 R3A R.B. A 2A 1PX71J RH53 SWITCH-HIGH 503 RH IPSH-RHOO6A PRESSURE BARTON 288A H-2866 B/20 R3A R.B. A 2A 1PX72J RH53
. SWITCH-HIGH 503 RH IPSH-RHOO68 PRESSURE BARTON 288A H-2866 B/20 R3A R.B. A 2A 1PX72J RH53 SWITCH-HIGH 503 RI 1E51-COO 2 TURBINE TERRY GS-1 H-2210 E-142 E/15 R4D R.B. A EX EOO7 475 RI 1E51-COO 3 PUMP WEST. 74D24113 H-2185 E-142 E/16 R4D R.B. A A EX EOO7
. MOTOR 475 RI 1E51-FOO4 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 F/15 R4D R.B. P EX M-52-1 EOO7
. CLOSED POS. E-2908 475
.PAGE 49 0F 76 e
S n SARGENTMUNDY
=ENGINEERB.
52 PR0dECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET RI 1E51-FOO4 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 F/15 R4D R.B. P EX M-52-1 EOO7 OPEN POS. E-2908 475 RI 1E51-FOO4 SOLENOID ASCO HT8320A175 H-2266 E-142 F/15 R4D R.B. P EX M-52-1 EOO7 E-2908 475 RI 1E51-FOO5 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 F/15 R4D R.B. P EX M-52-1 EOO7
. CLOSED POS. E-2908 475 RI 1E51-FOO5 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 F/15 R4D R.B. P EX M-52-1 EOO7 CPEN POS. E-2908 475 RI 1E51-FOO5 SOLENOID ASCO HT8320A17ti H-2266 E-142 r/15 R40 R.B. P EX M-52-1 EOO7
. E-2908 475 RI 1E51-FOO8 MOTOR OPER- LIMIT SMB-OO-10 H-2264 E-145 B/25 R2A R.B. A 2A M-52-1 RIO1 ATED VALVE E-2326 525 RI 1E51-FO10 MOTOR OPER- LIMIT SMB-OOO H-2264 E-142 E/18 R4A R.B. A A EX M-52-2 EOO7
. ATED VALVE E-2322 475 RI 1E51-FO12 MOTOR OPER- LIMIT SMB-O-40 H-2264 E-142 E/15 R4D R.B. A A EX M-52-2 EOO7 ATED VALVE E-2324 475 RI 1E51-F013 MOTOR OPER- LIMIT SMB-O-40 H-2264 E-149 C/25 RSA R.B. A EX M-52-2 EOO7
. ATED VALVE E-2325 570 RI 1E51-FO19 MOTOR OPER- LIMIT SMB-OOO H-2852 E-142 E/15 RdD R.B. A 2A M-52-2 RIO2 ATED VALVE E-2323 475 RI 1E51-F022 MOTOR OPER- LIMIT SMB-OO H-2263 E-149 C/24 RSA R.B. A EX M-52-2 EOO7 ATED VALVE E-2323 570 RI 1E51-FO25 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 OPEN POS. E-2908 475 RI 1E51-F025 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7
. CLOSED POS. E-2908 475 RI 1E51-F025 SOLENOID ASCO HT8320A175 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 E-2903 475 RI 1E51-FO26 SOLENDID ASCO HT8320A175 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 E-2908 475
.PAGE 50 0F 76 to O
m n SARGENT&l. UNDY
= ENutNEE RB .
53 f PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M No. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e....................................................................................,... . ............... ........ ........... ......
RI 1E51-F026 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7
. CLOSED POS. E-2908 475 RI 1E51-FO26 LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 OPEN POS. E-2908 475 RI 1E51-FO31 MOTOR OPER- LIMIT SMB-OOO-5 H-2264 E-142 D/11 R4A R.B. A 2A M-52-2 RIO3
. ATED VALVE E-2325 475 RI 1E51-F045 MOTOR OPER- LIMIT SMB-1 H-2820 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 ATED VALVE E-2029 475 RI 1E51-FO46 MOTOR OPER- LIMIT SMB-OOO-5 H-2852 E-142 E/15 R4D R.B. A EX M-52-2 EOO7
. ATED VALVE E-2324 475 RI 1E51-FO59 MOTOR OPER- LIMIT SMB-OO-10 H-2264 E-149 F/19 R3A R.B. A EX M-52-2 EOO7 ATED VALVE E-2326 503 RI 1E51-FO63 MOTOR OPER- LIMIT SMB-O-40 H-2264 E-147 C/22 C1 DRYWEL A 2A M-52-1 RIO5
. ATED VALVE E-1577 570 RI 1E51-FO64 MOTOR OPER- LIMIT SMB-O-40 H-2264 E-147 B/23 R1B R.B. A 2A M-52-1 RIO6 ATED VALVE E-2327 546 RI 1E51-FOG 6 SOLENDID ASCO WPHTX834472 H-2267 E-147 C/22 C1 DRYWEL P EX M-52-2 EOO5
. E-2908 593 RI 1E51-FO66 LIMIT SWITCH NAMCO EA74010000 H-2267 E-147 C/22 C1 DRYWEL P EX EOO5 E-2908 593 RI 1E51-FOG 6 LIMIT SWITCH MAG- MPS-15 H-2267 E-147 C/22 C1 DRYWEL A EX EOO7
. LOCK E-2908 593 RI 1E51-FO68 MOTOR OPER- LIMIT SMB-00-7.5 H-2264 E-144 D/15 R3A R.B. N/A A 2A M-52-1 RIO7
. ATED VALVE E-2327 503 RI 1E51-FO69 MOTOR OPER- LIMIT SMB-OOO H-2852 E-144 D/18 R3A R.B. N/A A 2A M-52-1 RIO8 ATED VALVE E-2329 503 RI 1E51-FO76 MOTOR OPER- LIMIT SMB-OOO H-2852 E-147 C/22 C1 DRYWEL N/A A 2A M-52-1 RIO9 ATED VALVE E-1576 570 RI 1E51-FO80 MOTOR OPER- LIMIT SMB-OOO H-2852 E-143 C/18 R3A R.B. A 2A M-52-1 RIO8 ATED VALVE E-2322 503
.PAGE 51 0F 76 to N
c) SARGENT&LUNDY
= ENGINERMB .
5 ') PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D No. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET RI 1E51-F086 MOTOR OPER- LIMIT SMB-OOO H-2852 E-14:4 B/18 R3A R.B. A 2A M-52-1 RIO4 ATED VALVE E-1578 503 RI 1E51-F 317 MOTOR OPER- LIMIT SMB-OOO h-2852 E-147 C/22 C1 DRYWEL N/A A 2A M-52-2 RIt0
. ATED VALVE E-1463 593 RI 1E51-NOO2 FLOW SWITCH BARTON 145C3OO8 H-2210 E-142 E/17 R4D R.D. A EX 1H22-pot 7 EOO7 289A E-2841 475 RI 1E51-NOO3 FLOW ROSE- 163C1561 H-2210 E-142 E/17 R4D R.B. A EX 1H22-PO17 EOO7
. TRANSMITTER MOUNT 1151DP E-2841 475 RI 1E51-NOO4 PRESS. BAILEY 163C1186 H-2210 E-142 E/17 R4D R.B. P EX 1H22-PO17 EOO7 TRANSMITTER 556 E-2841 475 RI 1E51-NOO5 PRESS. BAILEY 163C1186 H-22iO E-142 E/17 R4D R.B. P EX 1H22-pot 7 EOO7
. iRANSMITTER 556 E-2841 475 RI 1E51-NOO6 PRESS. STATIC 145C3011 H-2210 E-142 E/17 R4D R.B. A EX 1H22-PO17 EOO7
. SWITCH 0-RING GN-AA21 E-2841 475 RI 1E51-NOO7 PRESS. BAILEY 163C1186 H-2210 E-142 E/17 R4D R.B. P EX 1H22-PO17 EOO7 TRANSMITTER 556 E-2841 475 RI 1E51-NOO8 PRESS. ROSE- 1952 H-2210 E-142 E/17 R4D R.B. P EX 1H22-PO17 EOO7 TRAN3MITTER MOUNT E-2841 475 RI 1E51-NOO9 A PRESS. BARKS- 145C3046 H-2210 E-142 E/17 R4D R.B. A EX 1H22-PO17 EOO7
. SWITCH DALE D2d-M80SS E-2841 475 RI 1E51-NOO9 B PRESS. BARKS- 145C3046 H-2210 E-142 E/17 R4D R.B. A EX 1H22-PO17 EOO7 SWITCH DALE D2H-M80SS E-2841 475 RI 1E51-NOtO LEVEL MAGNET 159C4361 H-2210 E-142 D/15 R4D R.B. P EX EOO7 SWITCH -ROL 5.O-751 E-2906 475 RI 1E51-NO12 A PRESS. BAPKS- 145C3043 H-2210 E-142 E/17 R4D R.B. A 2A 1H22-PO17 RI11 SWITCH DALE D2H-M80SS E-2841 475 RI 1E51-NO12 B PRESS. BARKS- 145C3046 H-2210 E-142 F/24 R4E R.B. A 2A 1H22-PO29 RI12 SWITCH DALE D2H-M80SS E-2874 475 RI 1E51-NO12 C PRESS. BARKS- 145C3046 H-2210 E-142 E/17 R4D R.B. A 2A IH22-PO17 Ritt
. SWITCH DALE D2H-M80SS E-2841 475
.PAGE 52 0F 76
<D O
M M SARGENT&LUNDY NO!NEEFtti -
53 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.1. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SV NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e n s , s s e s s e s se ma s e , as sm a s sa m a m as , m ss u e s , m ees s es s o us, me se s s es , m ou sam maam me, m em e s s es , s es , s es, esesse, e s s , se se, ses, ema s, e ssessess e e, emen ,
RI 1ESt-NO12 D PRESS. BARKS- 145C3046 H-2210 E-142 F/24 R4E R.B. A 2A 1H22-PO29 RI12 SWITCH DALE D2H-M80SS E-2874 475 RI 1E51-NO2O PRESS. SWITCH BARKS- 159C4606 H-2210 E-142 E/16 R4D R.B. A EX 1PX28J EOO7
. DALE P1HM340SS-V E-2906 475 RI 1E51-NO21 PRESS. SWITCH BARKS- 145C3046 H-2210 E-142 E/17 R4D R.B. P EX 1H22-PO17 EOO7 DALE D2H-M80SS E-2841 475 RI 1E51-NO34 PRESS. SWITCH ROBERT 163C1185 H-2210 E-142 E/17 R4D R.B. P EX 1H22-PO17 E007
-SHAW SP-222C 415 RI 1SC-RI711 GOV. CONTROL WOOD- 8270-849 H-2210 E-142 E/16 R4D R.B. A EX E007 EGM BOX WARD E-2422 475 RI,1SE-RI711 GOV. CONTROL AIRPAX 1-0003 H-2210 E-142 E/16 R4D R.B. A EX EOO7 SENSING ELEMT E-2422 475 RI 1SE-RI714 TURBINE OVER- AIRPAX 1-O003 H-2210 E-142 E/16 R4D R.B. A EX E007 SPEED TRIP E-2422 475 SENSOR ELEMT RI 15YS-R1711 GOV. CONTROL WOOD- 8271-083 H-2210 E-142 E/16 R4D R.B. A EX EOO7 RAMP GEN. SIG WARD E-2422 475
. CONVERTER RI 15YS-RI714 TURBINE OVER- AIRPAX FSS-845 H-2210 E-142 E/16 R4D R.B. A EX EOO7 SPEED TRIP E-2422 475 CONVERTER RP 1C71-NOO2 A PRESS. SWITCH STATIC 145C3012 H-2210 E-148-1 E/20 RIC R.B. A 2A 1H22-POO4 RPO1 0-RING 12NAAYX9TT E-2809 546 RP 1C71-NOO2 B PRESS. SWITCH STATIC 145C3012 H-2210 E-147-1 C/17 R1C R.B. A 2A 1H22-PO27 RPO1 0-RING 12NAAYX9TT E-2867 546 RP 1C71-NOO2 C PRESS. SWITCH STATIC 145C3012 H-2210 E-147-1 C/24 R1B R.B. A 2A 1H22-POO5 RPO2 0-RING 12NAAYX9TT E-2811 546 RP 1C71-NOO2 O PRESS. SWITCH STATIC 145C3012 H-2210 E-148-1 E/24 R1C R.B. A 2A 1H22-PO26 RPO1 0-RING 12NAAYX9TT E-2863 546 RR 1833-FOt9 SOLENOID ASCO HTX8320A22V H-2852 E-147 C/23 C1 DRYWEL N/A A 2A M-47-1 RRO1 E-2917 546
.PAGE 53 0F 76 ui SARGENT&LUNDY
=ENGINEERO.
S'; PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e..............................,........................... . ..................... .... ... . ..........
. .6 .................
RR 1833-FO19 LIMIT SWITCH NAMCO EA-170 H-2852 E-147 C/23 C1 DRYWEL A 2A RRO3
. OPEN POS. 46302 E-2917 546 3 RR 1833-F019 LIMIT SWITCH NAMCO EA-170 H-2852 E-147 C/23 C1 DRYWEL A 2A RRO3
. CLOSED POS. 46302 E-2917 546 RR 1833-F020 LIMIT SWITCH NAMCO EA-170 H-2852 E-145 B/21 R2A R.B. A 2A RRO4
. OPEN POS. 46302 E-2917 525 RR 1833-F020 LIMIT SWITCH NAMCO EA-170 H-2852 E 145 B/21 R2A R.B. A 2A RRO4 CLOSED POS. 46302 E 4917 525 RR 1833-F020 SOLENOID ASCO HTX8320A22V H-2E52 E-145 B/21 R2A R.B. N/A A 2A M-47-1 RRO2
. E-2917 525 RR 1833-FO23A MOTOR OPER- LIMIT SMB-2 H-2210 E-145 C/23 C1 DRYWEL P EX M-47-1 EOO9 ATED VALVE E-1758 527 RR 1833-FO238 MOTOR OPER- LIMIT SMB-2 H-2210 E-146 D/22 C1 DRYWEL P EX M-47-2 EOO9 ATED VALVE E-1749 532 RR 1833-F355A SOLENDID TARGET 76F-207 H-2862 E - 14 7 C/25 RfC R.B. N/A A 2A M-47-1 RR06 VALVE ROCK E-2917 546 RR 1833-F3558 SOLENOID TARGET 76F-208 H-2862 E-147 C/25 R1C R.B. N/A A 2A M-47-1 RRO7
. VALVE ROCK E-2917 546 RR 1833-F355C SOLENOID TARGET 76F-208 H-2862 E-147 C/25 R1C R.B. N/A A 2A M-47-1 RRO7 VALVE ROCK E-2917 546 RR 1833-F3559 SOLENOID TARGET 76F-207 H-2862 E-147 C/25 R1C R.B. N/A A 2A M-47-1 RR06 VALVE ROCK E-2917 546 RR 1833-F356A SOLENOID TARGET 76F-207 H-2862 E-148 D/18 R1C R.B. N/A A 2A M-47-2 RROG VALVE ROCK E-2917 546 RR 1833-F3568 SOLENDID TARGET 76F-208 H-2862 E-148 D/18 R1C R.B. N/A A 2A M-47-2 RRO7
. VALVE ROCK E-2917 546 RR 1833-F356C SOLENOID TARGET 76F-208 H-2862 E-148 D/18 Ric R.B. N/A A 2A M-47-2 RRO7 VALVE ROCK E-2917 546 RR 1833-F356D SOLENDID TARGET 76F-207 H-2862 E-148 D/18 R1C R.B. N/A A 2A M-47-2 RR06 VALVE ROCK E-2917 546
.PAGE 54 0F 76 us O
SARGEhT&LUNDY __= ENOtNEERD .
57 0 4 4 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010 ZIMMER EOUIPMENT OUALIFICATION D01326
. PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET RR 1833-NO14 A FLOW TRANS. ROSE- 163C1561 H-2210 E-144 1 E/19 R3A R.B. A 2A 1H22-PO15 RROS
. MOUNT 1151DP E-2838 503 RR 1833-NO14 B FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 D/16 R3A R.B. A 2A 1H22-P022 RRO8 MOUNT 11510P E-2850 503 RR 1833-NO14 C FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 F/24 R3A R.B. A 2A 1H22-PO25 RRO8 MOUNT 1151DP E-2860 503 RR 1833-NO14 D FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 C/25 R3A R.B. A 2A 1H22-PO41 RRO8
. MOUNT 1151DP E-2893 503 RR 1833-NO18 A PRESS. SWITCH STATIC 145C3011 H-2210 E-141-1 B/26 R4B R.B. P 2B 1H22-PO18 RRO9
. 0-RING SNAA3STTX10 E-2844 475 RR 1833-NO18 B PRESS. SWITCH BARKS- 159C4606 H-2210 E-142 E/28 R4E R.B. P 28 1H22-PO21 RR10 DALE B1TM12SS-GE E-2847 475 RR 1833-NO24 A FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 E/19 R3A R.B. A 2A 1H22-PO15 RROS MOUNT 1151DP E-2837 503 RR 1833-NO24 8 FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 D/16 R3A R.B. A 2A 1H22 PO22 RROS
. MOUNT 11910P E-2850 503 RR 1833-NO24 C FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 F/24 R3A R.B. A 2A 1H22-PO25 RRO8 MOUNT 1151DP E-2860 503 RR 1833-NO24 D FLOW TRANS. ROSE- 163C1561 H-2210 E-144-1 C/25 R3A R.B. A 2A 1H22-PO41 RRO8 MOUNT 1151DP E-2893 503 RT 1G33-FOO1 MOTOR OPER- LIMIT SMB-OO-15 H-2264 E-147 D/21 C1 DRYWEL A 2A M-55-1 RTO1 ATED VALVE E-1755 546 RT 1G33-FOO4 MOTOR OPER- LIMIT SMB-OO-25 H-2264 E-148 E/21 Ric R.B. N/A A 2A M-55-1 RTO2
. ATED VALVE E-2334 546 RT 1G33-FO40 MOTOR OPER- LIMIT SMB-OO-10 H-2264 E-144 E/21 R3A R.B. N/A A 2A M-55-1 RTO3 ATED VALVE E-1568 522 SC 1C41-COO 1A PUMP MOTOR G.E. TYPE 324AN H-2210 E-149 A/19 RSA R.B. N/A A EX EOO3
. 567 SC 1C41-COO 1B PUMP MOTOR G.E. TYPE 324AN H-2210 E-149 A/19 R5A R.B. N/A A EX EOO3 567
.PAGE 55 0F 76 e
O n n SARGENT&LUNDY
= ENDif9EERO .
58 PROJECT NUMBER 4130-05 DATE 22 DEC 83
- REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID MODEL SPEC OR COMPONENT / E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEJ PASS REV CAT. SHEET e................................................. .............................. .................. ..............................
*iC IC41-FOO1A MOTOR OPER- LIMIT SMR-OOO-2 H-2263 E-149 A/18 HSA R.B. N/A A EX M-57 EOO3
. ATED VALVE E-1456 570 SC 1C41-FGO18 MOTOR OPER- LIMIT SMB-OOO-2 H-2263 E-149 A/18 RSA R.B. N/A A EX M-57 EOO3
. ATED VALVE E-1483 570 SC 1C41-FOO4A EXPLOSIVE CONAX 1832-159- H-2210 B/19 RSA R.B. A EX M-57 EOO3
. VALVE 01 567 SC 1C41-FOO4B EXPLOSIVE CONAX 1832-159- H-2210 B/19 RSA R.B. A EX M-57 EOO3
. VALVE 01 567 VG 1EL-VGO84A IND LTCHT G.E. ET-16 H-2299 A/23 R1B R.B. P EX 1PL69dA EOC6 546 VG ILL-VCO848 IND LIGHT G.E. ET-16 H-2299 A/03 R1B R.B. P EX IPL69dA EOC6
. 546 VG 1EL-VGO84C IND LIGHT G.E. ET-16 H-2299 A/23 R1B R.B. P EX 1PL69dA EOC6
. 546 VG 1EL-VGO85A IND LIGHT G.E. ET-16 H-2299 A/22 R68 R.B. P EX 1PL69dB EOC6
. 593 VG 1EL-VGO858 IND LIGHT G.E. ET-16 H-2299 A/22 R68 R.B. P EX iPL69dB EOO6 593 VG 1EL-VGO85C IND LIGHT G.E. ET-16 H-2299 A/22 RGB R.B. P EX IPL69dB EOO6 593 VG 1FC-VGO39 PROPORTIONAL LOVE 541-851- H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG01 CONTROLLER CON- 8134-8115- E-3434 546 TROLS 816-8174 VG 1FC-VGO40 PROPORTIONAL LOVE 541-851- H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VGO2 CONTROLLER CON- 8134-8115- E-3440 593
. TROLS 816-8174 VG 1FL-VGO45 RET AIR FLOW G.E. ET-16 H-2299 E-147 //22 R1B R.B. N/A P EX 1PL69JA EOC6
. IND LIGHT E-3434 546 VG 1FL-VGO46 RET AIR FLOW G.E. ET-16 H-2299 E-151 A/22 R6B R.B. N/A P EX TPL69dB EOOS
. IND LIGHT E-3440 593 VG 1FSV-VGOO3 A DELUGE VALVE ATKO- FGX5700GX H-2288 E-147 A/22 RfA R.B. A 2A 1PL69dA VGO3 MATIC E-3464 546 w
y .PAGE 56 0F 76 m SARGENTMUNDY 1E N CINCE FtB ..
52 - m t 4 PROJECT NUMBER 4130-05
.DATE 22 DEC 83
, REVISIDN 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET VG 1FSV-VGOO3 8 DELUGE VALVE ATKO- fGK5700GX H-2288 E-147 A/22 RfA R.B. A 2A 1PL69JA VGO3
. MATIC E-3464 546 VG 1FSV-VGOO3 A DEt.UGE VALVE ATKO- FGX5700GX H-2288 E-147 A/22 RfA R.B. A 2A 1PL69JA VGO3
. MATIC E-3464 546 VG 1FSV-VGOO5 B DELUGE VALVE ATKO- FGX5700GX H-2288 E-147 A/22 RfA R.8. A 2A iPL69JA VGO3
. MATIC E-3464 546 VG 1FSV-VGO2O A DELUGE VALVE ATKO- FGX5700GX H-2288 E-151 A/22 R6A R.B. A 2A VGO4
. MATIC E-3465 593 VG 1FSV-VGO2O B DELUGE VALVE ATKO- FGX5700GX H-2288 E-151 A/22 R6A R.B. A 2A VGO4
. MATIC E-3465 593 VG 1FSV-VGO28 A DELUGE VALVE ATKO- FGX5700GX H-2288 E-151 A/22 R6A R.B. A 2A VGO4 MATIC E-3465 593 J
VG 1FSV-VGO28 B DELUGE VALVE ATKO- FGX5700GX H-2288 E-151 A/22 R6A R.B. A 2A VGO4
. MATIC E-3465 593 VG 1FSV-VGO43 B SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 ASA AUX A 2A 1VC04YA VGO5
. VALVE E-3464 496 VG 1FSV-VGO43 D SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 ASA AUX A 2A 1VGO4YA VGO3
- . VALVE E-3464 496 VG 1FSV-VGO43 F SOLEN 0!O ASCO HTX8320A185 H-2289 E-093 F/27 ASA AUX A 2A 1VGO4YA VGO5
. VALVE E-3464 496 VG 1FSV-VGO43 H SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 ASA AUX A 2A 1VGO4YA VGOS
. VALVE E-3464 496 VG 1FSV-VGO44 B SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 A5A AUX A 2A IVGO4YB VGOS VALVE E-3465 496 VG 1FSV-VGO44 D SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 A5A AUX- A 2A 1VGO4YB VGOS
. VALVE E-3465 496
, VG 1FSV-VGO44 F SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 A5A AJX A 2A 1VCO4YB VGO5
. VALVE E-3465 496 VG 1FSV-VGO44 H SOLENOID ASCO HTX8320A185 H-2289 E-093 F/27 ASA AUX A 2A 1VGO4YB VGO5 .
j . VALVE E-3465 A96 , PAGE 57 0F 76 m o n t') SARGENT&LUNDY
'ENEBONEERG .
60
/^N j []
,Y fg]A !'%)
PROJECT PAJMBER 4130-05 DATE 22 DEC 83 REVISIDN 010
. ZIMMER EQUIPMENT OUALIFICATION D01326 e PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CDNTAIN FLD ACT/ ADO 0548 DATA eSY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET 4
e..........es. ...... esseneses,e=====,emensammans,eme .....mase ........... es==,. .....,emeses,........... .se..... asseemme,sene, VG 1FSY-VGO45 CURRENT LOVE 56-851-8115 H-2299 E-147 A/22 RfD R.B. N/A A 2A 1PLG9dA VG12
. RELAY CON- -843-8174 E-3434 546
. TROLS VG 1FSY-VGO45X AUX RELAY G.E. 12HFA51A49H H-2299 E-147 A/22 RIB R.B. N/A A 2A 1PL69JA VG18
. E-3436 546 .
VG 1FSY-VGO46 CURRENT LOVE 56-851-8115 H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69JB VG12
. RELAY CON- -843-8174 E-3440 593
. TROLS VG 1FSI-VGO46X AUX RELAY G.E. 12HFA51A49H H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69JB VG19
, . E-3442 593 VG 1FT-VGO39 DIFF PRESS HAYS 252:A H-2299 E-147 A/23 Ric R.B. N/A A 2A LOC MTD VG13
. TRANSMITTER E-3464 546 VG 1FT-VGO40 DIFF PRESS HAYS 252:A H-2299 E-151 A/23 R68 R.B. N/A A 2A LOC MTD VG14
. TRANSMITTER E-3465 593 VG 1FT-VGO45 DIFF PRESS HAYS 252:0 H-2299 E-101 F/26 R58 R.B. N/A A 2A LOC MTD VG13
. TRANSMITTER E-3464 567 VG 1FT-VGO46 DIFF PRESS HAYS 252:0 H-2299 E-101 F/26 R5B R.B. N/A A 2A LOC MTD VG15
. TRANSMITTER E*3435 567 VG 1FY-VGO39 AUX RELAY G.E. 12HFA51A49H H-2299 E-147 A/22 R1B R.B. N/A A 24 1PL69JA VG18
. E-3436 546 VG 1FY-VGO39 B CURRENT LOVE 56-8115- H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG16 j RELAY CON- 8181-8108- E-3440 546
. TROLS 8174 l
VG 1FY-VGO4C AUX RELAY G.E. 12HFA51A49H H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69JB VG19
. E-3442 593 VG 1FY-VGO40 B CURRENT LOVE 56-8115- H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG17
. RELAY CON- 8181-8108- E-3442 593
. TROLS 8174 VG 1FY-VGO83 AUX RELAY G.E. 12HFA51A42H H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69JA VG20
- E-3435 546 VG 1FY-VGO84 AUX RELAY G.E. 12HFA51442H H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69JA VG20
{ E-3435 546 u) .PAGE 58 0F 76 o M M SARGENT&LUNDY
61 PROJECT NUMBER 4130-05 DATE 22 DEC 83
. RFVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA eSY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D No. ELEVATN IN DUT BUILD LEV PASS REV CAT. SHEET VG 1FY-VGOoS AUX RELAY G.E. 12HFA51A42H H-2299 E-151 A/22 R68 R.B. .N/A A 2A 1PL69dB VG24
. E-3441 593 VG 1FY-VGO86 AUX RELAY G.E. 12HFA51A42H H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69JB VG21
. E-3441 593 VG 1FY-VGOS7 AUX RELAY G.E. 12HMA11811 H-2299 A/22 R68 R.B. A 2A 1PL69JB VG74
. 593 VG 1FY-VCO88 AUX RCLAY G.E. 12HMA11811 H-2299 A/23 R1B R.B. A 2A 1PL69JA VG75
. 546 a VG 1FY-VGOB9 AUX RELAY G.E. 12HMA11B11 H-2299 A/23 R1B R.B. A 2A iPL69JA VG76 546 l VG 1FY-VGO90 AUX RELAY G.E. 12HMA 11'111 H-2299 A/22 R6B R.B. A 2A 1PL69JB VG77
. 593 VG 1FZ-VGOO7A DAMPER ITT NH-95-C260- H-2874 E-147 A/25 R1A R.B. A 2A VG22
. ACTUATOR 2C617 E-3466 546 VG 1FZ-VGOO78 DAMPER ITT NH-95-C260- H-2874 E - 147 A/25 R1A R.B. A 2A VG22
. ACTUATOR 2C617 E-3466 546 VG 1FZ-VGOO7C DAMPER ITT NH-95 H-2874 E-147 '
A/25 R1B R.B. A 2A VG23
. ACTUATOR E-3464 546 VG 1FZ-VG014 DAMPER ITT NH-95-C260- H-2874 E-149 A/25 RfA R.B. A 2A VG22
. ACTUATOR 2C617 E-3464 546 VG 1FZ-VGO22A DAMPER ITT NH-95-C260- H-2874 E-149 A/23 RSA R.B. A 2A VG24
. ACTUATOR 2C617 E-3466 570 i VG 1FZ-VGO228 DAMPER ITT Mi-93-C260- H-2874 E-151 A/25 R68 R.B. A 2A VG25 l . ACTUATOR 2C617 E-3466 593 VG 1FZ-VGO22C DAMPER ITT NH-95 H-2874 E-151 A/27 RGB R.B. A 2A VG25
. ACTUATOR E-3465 593
, VG 1FZ-VGO29 DAMPER ITT NH-95-C260- H-2874 E-149 A/25 RSA R.B. A 2A VG24
. ACTUATOR 2C617 E-3465 570 VG 1FZ-VGO31A DAMPER ITT NH-95-C260- H-2874 E-101 G/26 R58 R.B. A 2A VG26
. ACTUATOR 2C617 E-3464 567
.PAGE 59 0F 76 to n
SARGENT&LUNDY
62 PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET VG 1FZ-voO310 DAMPER ITT NH-95-C260- H-2874 E-101 G/26 R50 R.B. A 2A VG26 ACTUATOR 2C617 E-3464 567 VG 1FZ-VGO32A DAMPER ITT NH-95-C260- H-2874 E-101 G/26 RSS R.B. A 2A VG26
. ACTUATOR 2C617 E-3465 567 VG 1FZ-VGO328 DAMPER ITT NH-95-C260- H-2874 E-101 G/26 R58 R.B. A 2A VG26
. ACTUATOR 2C617 E-3465 567 VG 1FZ-VGO49 DAMPER ITT NH-91-C2OO- H-2874 E-147 A/27 R1B 5t.B. A 2A VG27
. ACTUATOR 2C617 E-3466 546 VG 1FZ-VGO50 DAMPER ITT fui-91-C2OO- H-2874 E-151 A/25 R68 R.B. A 2A VG28
. ACTUATOR 2C617 E-3466 593 VG 1HS-VGOO3A CONTROL G.E. SB-1 H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG29
. SWITCH E-3434 546 VG IHS-VGOO3B CONTROL G.E. SB-1 H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG29
. SWITCH E-3434 546 VG 1HS-VGOOSA CONTROL G.E. 58-1 H-2299 E-147 A/22 R1B R.B. N/g A 2A 1PL69dA VG29
. SWITCH E-3434 546 VG 1HS-VGOO58 CONTROL G.E. SB-1 H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG29
$ WITCH E-3434 54G VG 1HS-V~>20A CONTROL G.E. SB-1 H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG30
. SWITCH E-3440 533 VG 1HS-VGO200 CONTROL G.E. SB-1 H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG30 SWITCH E-3440 593 VG 1HS-VGO28A CONTROL G.E. SB-1 H-2299 E-151 A/22 RGB R.B. N/A A 2A 1PL69dB VG30 SWITCH E-3440 593 VG 1HS-VGO28B CONTROL G.E. 58-1 H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG30
. SWITCH E-3440 593 VG 1JY-VGOO8 INSTR. POWER KEPCO PCX72-0.3 H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69JA VG31 SUPPLY E-3436 546 VG 1JY-VGO23 INSTR. POWER KEPCO PCX72-0.3 H-2299 E-151 A/22 R68 E.B. N/A A 2A 1PL69dB VG32
. SUPPLY E-3442 593 PAGE 60 0F 76 a
n m SARGENTMUNDY 1NGINEEF1D -
C3
, PROJECT NUMBER 4130-C5 OATE 22 DEC 83
. REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADO 0588 DATA
*SY NUMBER EQUIPMENT MFR NUM3ER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e..................................... ......... ......................................................... ... ....
VG 1KY-VGO39 TIME DELAY AGA- 7012AD H-2299 E-147 A/22 R1B R.B. N/A A 24 1PL69dA VG33 RELAY STAT E-3436 546 VG tKY-VGO40 TIME DELAY AGA- 7012AD H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG34
. RELAY STAT E-3442 593 VG 1KY-VGO45 TIME DELAY AGA- 7032ADC H-2299 E-147 A/22 R1B R.B. N/A A 2A iPL69JA VG40
. RELAY STAT E-3436 546 VG 1KY-VGO46 TIME DELAY AGA- 7032ADC H-2299 E-151 A/22 RGB R.B. N/A A 2A IPL69dB VG41
. RELAY STAT E-3442 593 VG 1KY-VGO50 TIME DELAY AGA- 7012AF H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69JA VG35
. RELAY STAT E-3436 546 VG 1KY-VGO72 TIME DELAY AGA- 7012AD H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69JA VG33
. RELAY STAT E-3436 546 VG 1KY-VGO73 TIME DELAY AGA- 7032AEC H-2299 E-147 A/22 R1B R.B. N/A A 2A iPL69dA VG42
. RELAY STAT E-3436 546 VG 1KY-VGO74 TIME DELAY AGA- 7012AH H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG36
. RELAY STAT E-3436 546 VG 1KY-VGO76 TIME DELAY AGA- 7032AEC H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69J8 VG43 RELAY STAT E-3442 593 VG 1KY-VGO77 TIME DELAY AGA- 7012AH H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG37 RELAY STAT E-3442 593 VG 1KY-VGO78 TIME DELAY AGA- 7012AD H-2299 E-151 A/22 RGB R.B. N/A A 2A 1PL69dB VG34
. RELAY STAT E-3442 593 VG 1KY-VGO83 TIME DELAY AGA- 7022-PE H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69JA VG38 RELAY STAT E-3436 546 VG 1KY-VGOO4 TIME DELAY AGA- 7022-PE H-2299 E-147 A/22 R1B R.B. N/A A 2A iPL69dA VG38 RELAY STAT E-3436 546 VG 1KY-VGOB5 TIME DELAY AGA- 7022-PE H-2299 E-151 A/22 R68 R.B. N/A A 2A iPL69dB VG39
. RELAY STAT E-3442 593 VG 1KY-VGO86 TIME DELAY AGA- 7022-PE H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG39 RELAY. STAT E-3442 593
$PAGE 61 0F 76 e
O b SARGENT&LUNDY
= ENGINEER O .
C4 m (n
/ b& ,-
PROJECT NUMBER 4130-05 DATE 22 DEC 83
' REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID' COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET VG 1KY-VG089 TIME DELAY AGA- 7022-AD H-2299 E-147 A/23 R1B R.B. A 2A 1PL69JA VG72
. RELAY STAT E-3436 546 VG 1KY-VGO90 TIME DELAY AGA- 7022-AD H-2299 E-147 A/22 R6B R.B. A 2A 1PL69dB VG73
. RELAY STAT E-3436 593 VG 1KY-VGO92 TIME DELAY AGA- 7012AD l4-2299 E-147 A/22 R1B R.B. A 2A 1PL69JA VG33
. RELAY STAT E-3436 546 VG 1KY-VGO93 TIME DELAY AGA- 7012AD H-2299 E-151 A/22 R68 R.B. A 2A 1PL69dB VG34
. RELAY STAT F-3442 593 VG 1LS-VGOO3 LEVEL SWITCH MER- 201WT9806- H-2288 E-147 A/24 RfA R.B. A 2A VG44 COID 52C60 E-3464 546 VG ILS-VGOO5 LEVEL SWITCH MER- 201WT9806- H-2288 E-147 B/25 R1A R.B. A 2A VG44 COID 52C60 E-3464 546 VG 1LS-VGO2O LEVEL SWITCH MER- 201WT9806- H-2288 E-151 A/24 R6A R.B. P 2B VG45
. COID 52C60 E-3465 593 VG 1LS-VGO28 LEVEL SWITCH MER- 201WT9806- H-2288 E-151 A/24 R6A R.B. P 2B VG45
. COID 52C60 E-3465 593
.VG 1PDT-VGOO8 DIFF PRESS ITT- 385 H-2288 E-147 A/22 R1B R.B. A 2A iPL69JA VG46
. XMITTER BARTON 1990PU E-3464 546 VG 1PDT-VGO23 DIFF PRESS ITT- 385 H-2288 E-151 A/22 R6A R.B. A 2A VG47 XMITTER BARTON 1990PU E-3465 593 VG IPDY-VGOO8 CURRENT RELAY LOVE 48-8115- H-2299 E-147 A/22 R1B R.B. N/A A 2A 1PL69dA VG48 l CON- 843-816- E-3434 546
. TROLS 8174 VG 1PDY-VGO23 CURRENT RELAY LOVE 48-8115- H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG49 CON- 843-816- E-3440 593 TROLS 8174 VG 1PL69dA ESS-1 SGTSET POWERS H-2239 E-146-1 A/23 R1B R.B. A 2A VG78
. NO.1A REGULATOR 546 VG 1PL69dB ESS-2 SGTSET POWERS H-2299 E-151 A/22 R68 R.B. A 2A VG79
. NO.1B REGULATOR 593 VG 1TE-VGO35 TEMP ELEMENT ALISON 1052-RTO H-2288 E-147 A/27 R1B R.B. A 2A VG50 CONT. E-3464 546
, ci . g ,PAGE 62 0F 76 , n SARGENT&LUNDY
C5
/
k, (O J v ) PROJECT NUMBER 4130-05 DATE 22 DEC 83. REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
*.......................................................... ..,......... . ............ . .=............ . ........ . .... . .................
VG 1TE-VGO36 TEMP ELEMENT ALISON 1052-RTD H-2288 E-147 A/23 RIA R.B. ,N/A A 2A VG51
. CONT. E-3464 546 VG iTE-VGO37 TEMP ELEMENT ALISON 1052-RTD H-2288 E-151 A/23 R68 R.B. N/A A 2A VG52
. CONT. E-3465 593 VG iTE-VGO38 TEMP ELEMENT ALISON 1052-RTD H-2288 E-151 A/23 R6A R.B. N/A A 2A VG53
. CONT. E-3465 593 VG STI-VGO35A TEMPERATURE G.E. 180 H-2299 E-147 A/22 R1B R.B. N/A P 28 1PL69JA VG67
. INDICATOR E-3434 546 VG iTI-VGO36A TEMPERATURE G.E. 180 H-2299 E-147 A/22 R1B R.B. N/A P 2B 1PL69JA VG6T
. INDICATOR E-3434 546 VG 1TI-VGO37A TEMPERATURE G.E. 180 H-2299 E-151 A/22 R6B R.B. N/A P 28 iPL69JB VG68
. INDICATOR E-3440 593 VG iTI-VGO38A TEMPERATURE G.E. 180 H-2299 E-151 A/22 R68 R.B. N/A P 28 iPL69JB VG68 INDICATOR E-3440 593 VG iTSY-VGOO7 AUX RELAY G.E. 12HMA11B11 H-2299 E-147 A/22 R1B R.B. N/A A 2A tPL69JA VG58
. E-3464 546 VG 1TSY-VGO22 AUX RELAY G.E. 12HMA11811 H-2299 E-151 A/22 R68 R.B. N/A A 2A 1PL69dB VG59
. E-3442 593 VG iTS-VGOO3 TEMP SWITCH MER- 7038-80452 H-2288 E-147 A/22 RfA R.B. N/A A 2A VG56 COID E-3404 546 VG ITS-VGOO5 TEMP SWITCH MER- 7038-80452 H-2288 E-147 A/22 RfA R.B. N/A A 2A VG56 COID E-3464 546 VG iTS-VGO2O TEMP SWITCH MER- 7038-80452 H-228S E-151 A/22 R6A R.B. N/A A 2A VG57
. COID E-3465 593 VG iTS-VGO28 TEMP SWITCH MER- 7038-80452 H-2288 E-151 A/22 RSA R.B. N/A A 2A VG57
. COID E-3465 593 VG 1TT-VGO35 TEMPERATURE ALLI- 1052 H-2288 E-147 A/22 R1B R.B. A 2A 1PL69JA VG54
. TRANSMITTER SON E-3464 546 VG iTT-VGO36 TEMPERATURE ALLI- 1052 H-2288 E-147 A/22 R1B R.B. A 2A 1PL69JA VG54
. TRANSMITTER SON E-34C4 546
$PAGE 63 0F 76 e
n SARGENT&LUNDY
.nm
Y PROJECT NUMBER 4130-05 DATE 22 DEC 83
. REVISION 010
. ZIMMER EOUIPMENT QUALIFICATION 001326
- PLANT 10 COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLO ACT/A00 0588 DATA
*SY MJMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e..................................... . .......................................... .......
VG iTT-VGO37 TEMP ALLI- 1052 H-2288 E-151 A/23 R6B R.B. A 2A VG55
. TRANSMITTER SON E-3465 593 VG 1TT-VGO38 TEMP ALLI- 1052 H-2288 E-151 A/23 R6A R.B. A 1A VG55
. TRANSMITTER SON E-3465 593 VG 1VG01CA FAN MOTOR WEST. 76C53097 H-2290 E-101 G/26 R58 R.B. N/A A 2A VG60
. E-1359 567 VG 1VGOICB FAN MOTOR WEST. 76C53097 H-2290 E-101 G/24 R58 R.B. N/A A 2A VG6C E-1395 567 VG 1VGO2CA FAN MOTOR WEST. 78D36171 H-2288 E-147 A/27 R1B R.B. N/A A 2A VG61
. E-1454 546 VG 1VGO2CB FAN MOTOR WEST. 78D36171 H-2288 E-151 A/25 RGB R.B. N/A A 2A VG62
. E-1471 593 VG IVGO3CA FAN MOTOR WEST. 73D70443 H-2288 E-147 A/25 R1B R.B. N/A A 2A VG63
. E-1451 546 VG tVGO3CB FAN MOTOR WEST. 73D70443 H-2288 E-151 A/25 RGB R.B. N/A A 2A VG64 E-1469 593 VG IVGO4AA ELECTRIC INOEE- 9M/A H-2288 E-147 A/24 R1B R.B. N/A A 2A VG65 HEATER CD E-3621 54G VG 1VGO4AB ELECTRIC INDEE- 9N/A H-2288 E-151 A/25 R6A R.B. N/A A 2A VG66
. HEATER CD E-3621 593 VG tZS-VGOO7AA DAMPER POS NAMCO EA74020100 H-2874 E-147 A/25 RfA R.B. A 2A VGO6
. SWITCH E-3466 346 VG 125-VGOO7AB DAMPER POS NAMCO EA74020100 H-2874 E-147 A/25 RfA R.B. A 2A VGOG
. SWITCH E-346C 546 VG 125-VGOO7BA DAMPER POS NAMCO EA74020100 H-2874 E-147 A/25 R1A R.B. A 2A VGO6
. SWITCH E-3466 546 VG IZS-VGOO78B DAMPER POS NAMCO EA74020100 H-2874 E-147 A/25 RfA R.B. A 2A VGO6 SWITCH E-3466 546 VG 125-VGOO7CA DAMPER POS NAMCO EA74020100 H-2874 E-147 A/25 RtB R.B. A 2A VGO7
. SWITCH E-3464 546
.PAGE 64 OF 76 c$
n M SARGENT&LUNDY ENOfNSUt D .
07 0 4 4 PROJECT NUMBER 4130-05 DATE 22 DEC 83 s REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC DR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADO 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
- VG 125-VGOO7CB DAMPER POS NAMCO EA74020100 H-2874 E-147 A/25 R1B R.B. A 2A VGO7
. SWITCH E-3464 546 VG 1ZS-VG014A DAMPER POS NAMCO EA74020100 H-2874 E-149 A/25 RSA R.B. A 2A VGO8
. SWITCH E-3464 570 VG 125-VGO148 DAMPER POS NAMCO EA74020100 H-2874 E-149 A/25 RSA R.B. A 2A VGO8
. SWITCH E-3464 570 VG 1ZS-VGO22AA DAMPER POS NAMCO EA74020100 H-2874 E-149 A/25 RSA R.B. A 2A VGOS SWITCH E-3466 570 VG 125-VGO22AB DAMPER POS NAMCO EA74020100 H-2874 E-149 A/25 RSA R.B. A 2A VGOB
. SWITCH E-3466 570 VG 125-VGO22BA DAMPER POS NAMCO EA74020100 H-2874 E-151 A/25 R6A R.B. A 2A VG70
. SWITCH E-3466 593 VG 125-VGO22BB DAMPER POS NAkCO EA74020100 H-2874 E-151 A/25 R6A R.B. A 24 VG70
. SWITCH E-3466 593 VG 1ZS-VGO22CA DAMPER POS NAMCO EA74020100 H-2874 E-151 A/25 R68 R.B. A 2A VG10'
. SWITCH E-3465 593 VG 125-VGO22CB DAMPER POS NAMCO EA74020100 H-2874 E-151 A/25 R68 R.B. A 2A VG10
. SWITCH E-3465 593 VG 1ZS-VGO29A DAMPER POS NAMCO EA74020100 H-2874 E-149 A/25 RSA R.B. A 2A VGO8
. SWITCH E-3465 570 VG 125-VGO298 DAMPER POS NAMCO EA74020100 H-2874 E-149 A/25 RSA R.B. A 2A VGO8 SWITCH E-3465 570 VG 125-VGO31A DAMPER POS NAMCO EA74020100 H-2874 E-101 G/26 R58 R.B. N/A A 2A VGO9
. SWITCH E-3464 567 VG 125-VGO31B DAMPER POS NAMCO EA74020100 H-2874 E-101 G/26 R58 R.B. N/A A 2A VGO9
. SWITCH E-3464 567 VG 1ZS-VGO32A DAMPER POS NAMCO EA74020100 H-2874 E-101 G/26 RSB R.B. N/A A 2A VGO9 SWITCH E-3465 567 VG 1ZS-VGO328 DAMPER POS NAMCO EA74020100 H-2874 E-101 G/26 R53 E.B. N/A A 2A VGO9 SWITCH E-3465 567
.PAGE 65 0F 76 o
n i l SARGENTMUNDY
. -o.ux.m
C8 . ] ry p NJ t w.A PROJECT NUMBER 4130-05 DATE 22 DEC 83
- REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET VG 1ZS-VGO43BA DAMPER POS NAMCO EA70070001 H-2289 E-093 F/27 A5A AUX N/A A 2A 1VGO4YA VG71
. SWITCH OPEN E-3464 496 VG 125-VGO4388 DAMPER POS NAMCO EA70070000 H-2289 E-093 F/27 ASA AUX N/A A 2A TVGO4YA VG11
. SWITCH CLOSED E-3464 496 VG 1ZS-VGO44BA DAMPER PDS NAMCO EA70070001 H-2289 E-093 F/27 A5A AUX N/A A 2A 1VGO4YB VG71
. SWITCH OPEN E-346S 496 VG 12S-V'GO44BB DAMPER POS NAMCO EA70070000 H-2289 E-093 F/27 ASA AUX N/A A 2A 1VGO4YB VG11
. SWITCH CLOSED E-3465 496 VG 125-VGO49A DAMPER POS NAMCO EA74020100 H-2874 E-147 A/27 R1B R.B. A 2A VGO7
. SWITCH E-3466 546 VG 125-VGO498 DAMPER POS NAMCO EA74020100 H-2874 E-147 A/27 R1B R.B. A 2A VGOT
. SWITCH E-3566 546 VG 125-VGO50A DAMPER POS NAMCO EA74020100 H-2874 E-151 A/27 R68 R.B. A 2A VG10
. SWITCH E-3466 593 VG 1ZS-VGO50B DAMPER POS NAMCO EA74020100 H-2874 E-151 A/27 R68 R.B. A 2A VG10
. SWITCH E-3566 593 VP 1VPOO6A MOTOR OPER- LIMIT SMB-OOO-5 H-2811 E-146 D/24 R2B R.B. A 2A M-88-1 VPO2
. ATED VALVE E-2330 527 i
VP 1VPOO68 MOTOR OPER- LIMIT SMB-OOO-5 H-2811 E-145 B/23 R2A R.B. A 2A M-88-1 VPO3
. ATED VALVE E-2339 527 VP 1VPO12A MOTOR OPER- LIMIT SMB-OOO-5 H-2811 E-146 D/24 R2B R.B. A 2A M-88-1 VPO2
. ATED VALVE E-2330 527 VP 1VPO128 MOTOR OPER- LIMIT SMB-OOO-5 H-2811 E-145 B/23 R2A R.B. A 2A M-88-1 VPO3
. ATED VALVE E-2339 527 VP 1VPO45A MOTOR OPER- LIMIT SMB-OOO H-2811 E-146 B/22 C1 R.B. A 2A M-88-1 VPO4
. ATED VALVE E-1756 537 VP 1VPO45B MOTOR OPER- LIMIT SMB-OOO H-2811 E-145 D/22 C1 R.B. A 2A M-88-1 VPO4
. ATED VALVE E-1756 537 VO 1FSV-VOO31 SOLENOID ASCO HTX8321A- H-2265 E-146 E/24 R2B R.B A 2A M-103 VQO3
. VALVE GEMO E-3693 525
[PAGE 66 0F 76 3 m M SARGENT&LUNDY
..,4 4mm
m m n 4 h h'L.) G PROJECT NUMBER 4130-05 DATE 22 DEC 83
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADO 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/0 NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHE E.T e.................................................................................... ..............................................
VQ 1FSV-VQO32 SOLENOID ASCO HTX8321A- H-2265 E-146 A/18 RSA R.B A 2A M-103 VQO1
. VALVE 6EMO E-3693 570 VQ 1FSV-VQO33 SOLEN 0!D ASCO HTX832 A- H-2265 E-149 C/18 RSA R.B. A 24 M-103 VQOf
. VALVE- 6EMO E-3693 570 VQ 1FSV-VQO34 SOLENOID ASCO HTX8321A- H-2265 E-149 C/18 RSA R.B. A 2A M-103 VQO1
. VALVE 6EMO E-3693 570 VQ 1FSV-VQO37 SOLENOID ASCO HTX8321A- H-2265 E-143 R/19 R3A R.B A 2A M-103 VQO2
[ . VALVE 6EMO E-3693 517 VQ 1FSV-VQO38 SOLENOID ASCO HTX8321A- H-2265 E-143 E/24 R3A R.B A 2A M-103 VQO2
. VALVE 6EMO E-3693 518 VQ 1FSV-VQO39 SOLEN 0!O ASCO HTX8321A- H-2265 E-144-1 E/25 R3A R.B. A 2A M-103 VQO2
. VALVE 6EMO E-3693 503 VQ 1FSV-VQO40 SOLENOID ASCO HTX8'321A- H-2265 E-144 E/25 R3A R.B. A 2A M-103 VQO2
. VALVE 6EMO E-3693 503 VQ IVQOOSA LIMIT SWITCH TARGET 76F-205 H-2862 B/18 RSA R.B. N/A A 2A M-103 VQO4
. CLOSED POS. ROCK 584 VQ IVQOO5A SOLENDID TARGET 76F-205 H-2862 E-149 B/18 RSA R.B. N/A P 28 M-103 VQO4 ROCK E-3693 584 -
VQ 1VQOOSA LIMIT SWITCH TARGET 76F-205 H-2862 B/18 RSA R.B. N/A A 2A M-103 VQO4
. OPEN POS. ROCK 584 VQ IVOOO58 LIMIT SWITCH TARGET 76F-205 H-2862 B/19 RSA R.B. N/A A 1A M-103 VQO4
. CLOSED POS. ROCK 584 VQ IVQOOSB SOLENOID TARGET 76F-205 H-2862 B/19 RSA R.B. N/A P 2B M-103 VQO4
. ROCK 584 VO IVQOO58 LIMIT SWITCH TARGET 76F-205 H-2862 B/19 RSA R.B. N/A A 2A M-103 VQO4
. OPEN POS. ROCK 584 VO IVQOO8A SOLENOID TARGET 76F-205 H-2862 E-143 B/20 R3A R.B. N/A P 28 M-103 VQO5
. ROCK E-3693 517 VQ IVQOOJA LIMIT SWITCH TARGET 76F-205 H-2862 B/20 R3A R.B. N/A A 2A M-103 VQOS CLOSED POS. ROCK 517
$PAGE 67 0F 76 e
n M SARGENT&LUNDY ENG1NEEftD ,
70 4 4 9 PROJECT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326 e PLANT ID COMPONENT / MODEL SPEC OR E.I. DWC COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIFMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET ene,ssessessesses,esames======s,mme===,seeme==eswa,==es===e,emas===munes,sesseems,was,ess,massee,ess, sees,ess,wgse,massenemmes.neen, VQ 1VQOO8A LIMIT SWITCH TARGET 76F-205 H-2862 B/20 R3A R.B. N/A A 2A M-103 VQOS OPEN POS. ROCK 517 VO IVOOO88 SOLENOID TARGET 76F-205 H-2862 E-143 B/20 R3A R.B. N/A P 2B M-103 VOOS
. ROCK E-3693 517 VO 1VOOO8B LIMIT SWITCH TARGET 76F-205 H-2862 B/20 R3A R.B. N/A A 2A M-103 VOO5
. OPEN POS. ROCK 517 VO 1VOOO88 LIMIT SWITCH TARGET 76F-205 H-2862 B/20 R3A R,8. N/A A 2A M-103 VQO5 CLOSED POS. ROCK 517 VR 1XY-VR060A SMOKE DETECT PYROT- DIS 3/5A H-2299 E-141 B/27 R2A R.B. N/A N FX LOC MTD EOO2
. RONICS E-3722 525 VR 1XY-VRO608 SMOKE DETECT PYROT- DIS 3/SA H-2299 E-141 C/27 R2A R.B. N/A N EX LOC MTD EOO2 RONICS E-3722 525 VR 1XY-VR060C SMOKE DETECT PYROT- DIS 3/5A H-2299 E-141 A/25 R2A R.B. N/A N FX LOC MTD EOO2 RONICS E-3722 525 VR 1XY-VR060D SMOKE DETECT PYROT- DIS 3/5A H-2299 E-141 B/25 R2A R.S. N/A N EX LOC MTO EOO2 RONICS E-3722 525 VR 1XY-VR060E SMOKE DETECT PYROT- DIS 3/5A H-2999 E-141 A/21 R2A R.B. N/A N EX LOC MTD EDO2 RONICS E-3722 525 VT 1XY-VTO52K SMOKE DETECT PYROT- DIS 3/5A H-2299 E-093 J/26 ASA AUX N/A N EX LOC MTD EOO2
. RONICS E-3697 496 VY 1TE-VYOO9 TEMP ELEMENT ROSE 88-14 H-2809 E-142 E/26 R4E R.B. A 2A VYO1 MOUNT E-3666 475 VY 1TE-VYO10 TEMP ELEMENT ROSE 88-14 H-2809 E-141 A/26 R4B R.B. A 2A VYO2
. MOUNT E-3666 475 VY iTE-VYO11 TEMP ELEMENT ROSE 88-14 H-2809 E-142 E/16 R4D R.B. A 2A VYO3 MOUNT E-3666 475 VY 1TE-VYO12 TEMP ELEMENT ROSE 88-14 H-2809 E-141 A/16 R4C R.B. A 2A VYO4 MOUNT E-3666 475 VY 1TS-VYOO1 TEMP SWITCH UNITED 3OO-6AS H-2299 E-142 F/26 R4E R.B. N/A A 2A LOC MTD VYOti
. ELEC. E-1470 475
$PAGE 68 0F 76 e
O n n SARGENT&LUNDY
= ENGINEEftD -
71 l PROJECT NUMBER 4130-05 DATE 22 DEC 83 REVISION 010
. ZIMMER EQUIPMENT OUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL /RDW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D No. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET VY 115-VYOO2 TEMP SWITCH UNITED 3OO-6AS H-2299 E-142 B/25 R4B R.B. N/A A 2A LOC MTD VYO6 ELEC. E-1451 475 VY iTS-VYOO3 TEMP SWITCH UNITED 3OO-6AS H-2299 E-142 F/17 R4D R.B. N/A A 2A LOC MTD VYO7 ELEC. E-1452 475 VY iTS-VYOO4 TEMP SWITCH UNITED 3OO-6AS H-2299 E-141 A/17 R4C R.B. N/A A 2A LOC MTD VYO8
. ELEC. E-1488 475 VY 1TZ-VYOO1 A DAMPER ITT NH-95C2602- H-2868 E-144 E/28 R3A R.B. A 2A VYO9 ACTUATOR L37 E-3692 520 VY 1TZ-VYOO1 B DAMPER ITT NH-95C2602- H-2868 E-144 E/28 R d" R . B . A 2A VY13 ACTUATOR L37 E-3692 520 VY ITZ-VYOO2 A DAMPER ITT NH-95C2602- H-2868 E-143 B/28 R3A R.B. A 2A VYO9 ACTUATOR L37 E-3692 516 VY iTZ-VYOO2 B DAMPER ITT NH-95C2602- H-2868 E-143 C/28 R4F R.B. A 2A VY13 ACTUATOR L37 E-3692 521 VY ITZ-VYOO3 A DAMPER ITT NH-95C2602- H-2868 E-144 E/16 R3A R.B. A 2A VYO9
. ACTUATOR L37 E-3692 508 VY iTZ-VYOO3 B DAMPER ITT NH-95C2602- H-2868 E-142 F/15 R4D R.B. A 2A VY10 ACTUATOR L37 E-3C92 473 VY iTZ-VYOO4 A DAMPER ITT NH-95C2602- H-2868 E-143 A/15 R3A R.B. A 2A VYO9 ACTUATOR L37 E-3692 503 VY 1TZ-VYOO5 DAMPER ITT NH-95C2602- H-2868 E-144 E/28 R4F R.B. A 2A VY13
. ACTUATOR L37 E-3692 503 VY 1TZ-VYOOG DAMPER ITT NH-95C2602- H-2868 E-143 F/28 R4F R.B. A 2A VY13 ACTUATOR L37 E-3692 503 VY 1TZ-VYOO7 DAMPER ITT NH-95C2602- H-2868 E-142 F/15 R4D R.B. A 2A VY10
. ACTUATOR L37 E-3692 499 VY iTZ-VYOO8 DAMPER ITT NH-95C2602- H-2868 E-141 A/15 R4C R.B. A 2A VY11 ACTUATOR L37 E-3692 503 VY 1VYO1C FAN MOTOR WEST. 76D53112 H-2290 E-144 D/28 R3A R.B. N/A A 2A VY12 E-1470 503
.PAGE 69 0F 76 to O
m M SARGENT&LUNDY TNGINEEAD -
72
, l PROJECT NUMBER 4130-05 DATE 22 DEC 83 ' REVISION 010 ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADO 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMGER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET e==,.===............-==========,..... ,========= .......... ............
. . am.............. . ................ . ...s, VY IVYO2C FAN MOTOR WEST. 76053112 H-2290 E-143 B/26 R3A R.B. N/A A 2A VY12
. E-1451 503 VY 1VYO3C FAN MOTOR WEST. 76053112 H-2290 E-144 E/15 R3A R.B. N/A A 2A VY12
. E-1452 503 VY 1VYO4C FAN MOTOR WEST. 76053112 H-2290 E-143 B/16 R3A R.B. N/A A 2A VY12 E-1488 503 VY 1XY-VYO35A SMOKE DETECT PYROT- DIS 3/SA H-2299 E-14l B/28 R4B R.B. N/A N EX LOC MTD EOO2 RONICS E-3722 475 VY 1XY-VYO35B SMOKE DETECT PYROT- DIS 3/SA H-2299 E-141 B/28 R4B R.B. N/A N EX LOC MTD EOO2
. RONICS E-3722 475 VY 1XY-VYO35C SMOKE DETECT PYROT- 01S 3/SA H-2239 E-141 B/27 R4B R.B. N/A N EX LOC MTD EOO2 RONICS E-3722 475 VY 125-VYOO1A DAMP CLOSE NAMCO EA75020100 H-2868 E-144 D/27 R3A R.B. A 2A IVYO6YA&B VY14 POS. SWITCH E-3692 521-1 VY 1ZS-VYOO18 DAMP CLCSE NAMCO EA75020100 H-2868 E-144 D/27 R4F R.B. A 2A 1VYO8Y VY17 POS. SWITCH E-3692 520-8 VY 1ZS-VYOO2A DAMP CLOSE NAMCO EA75020100 H-2868 E-143 B/28 R3A R.B. A 2A IVY 12Y VY14 POS. SWITCH E-3692 516 VY 1ZS-VYOO2B DAMP CLOSE NAMCO EA75020100 H-2868 E-143 C/28 R4F R.B. A 2A IVYO2Y VY17 POS. SWITCH E-3692 521 VY 1ZS-VYOO3A DAMP CLOSE NAMCO EA75020tOO H-2866 E-144 F/iti R3A R.B. A 2A IVYO9Y VY14
. POS. SWITCH E-3692 508 VY 12S-VYOO3B OAMP CLOSE NAMCO EA75020100 H-2868 E-142 F/16 R4D R.B. A 2A 1VY11Y VY15 POS. SWITCH E-3692 500 VY 1ZS-VYOO4A DAMP CLOSE NAMCO EA75020100 H-2868 E-143 C/16 R3A R.B. A 2A 1VY15Y VY14
. POS. SWITCH E-3692 513 VY 1ZS-VYOOS DAMP CLOSE NAMCO EA75020100 H-28G8 E-144 D/28 R4F R.B. A 2A 1VY13YA&B VY17 P05. SWITCH E-3692 521-1 VY 125-VYOO6 DAMP CLOSE NAMCO EA75020100 H-2868 E-143 C/28 R4F R.B. A 2A 1VYO1Y VY17 POS. SWITCH E-3692 516
.PAGE 70 0F 76 m
N n SARGENT&LUNDY TNOINEERS .
13 (n.) v , PROJECT NUMBER 4130-05 . DATE 22 DEC 83
. ZIMMER EQUIPMENT CUALIFICATION 001326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EQUIPMENT MFR NUMCER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET VY 125-VYOO7 DAMP CLOSE NAMCO EA75020100 H-28t,8 E-142 F/15 R4D R.B. A 2A 1VY14Y Vf15
. POS. SWITCH E-3692 499 VY 1ZS-VYOO8 DtMP CLOSE NAMCO EA75020100 H-2868 E-141 B/15 R4C R.B. A 2A 1VYO4Y VY16
. POS. SWITCH E-3692 501-8 '
tdR 1LT-WRO36 LEVEL XMITTER ROSE- 1152GP4A- H-2809 E-152 E/23 R6C R.B. A 2A 1PX24J WRO1
. MOUNT 22PB E-1995 593 WR ILT-WRO37 LEVEL XMITTER ROSE- 1152GP4A- H-2809 E-152 E/23 R6C R.B. A 2A 1PX25J WRO1
. MOUNT 22PB E-1995 593 WR 1PS-WR141 PRESSURE BARTON 288A H-2866 E-147 B/28 R1C R.B. A 2A 1PXO6J WRO2
. SWITCH E-1981 546 WR 1PS-WR142 PRESSURE BARTON 288A H-2866 E-147 D/28 RfC R.B. A 2A 1PXO6J WRO2
. SWITCH E-1981 546 WR 1PS-WR143 PRESSURE BARTON 288A H-2866 E-147 B/27 Ric R.B. A 2A 1PXO7J WRO2
. SWITCH E-1981 546 WR 1PS-WR144 PRESSURE RARTON 288A H-2866 E-147 B/27 RiC R.B. A 2A 1PXO7J WRO2
. SWITCH E-1981 546 WR 1PS-WR145 PRESSURE BARTON 288A H-2866 E-145 B/27 R2A R.B. A 94 1PXO8J WRO3
. SWITCH E-1981 525 WR 1PS-WR146 PRESSURE BARTON 288A H-2866 E-145 D/27 R2A R.B. A 2A 1PXO8J WRO3
. SWITCH E-1981 525 WR 1PS-WR147 PRESSURE BARTON 288A H-2866 E-145 C/25 R2A R.B. A 2A 1PXO9J WRO3
. SWITCH E-1981 525 WR 1PS-WR148 PRESSURE BARTON 288A H-2866 E-145 C/25 R2A R.B. A 2A 1PXO9J WRO3
. SWITCH E-1981 525 WR 1PT-WRO51 PRESSURE ROSE- 1152GP7A22- H-2809 E-143 B/28 R3A R.B. A 2A 1PX18J WRO4
. TRANSMITTER MOUNT PB E-1995 503 WR 1PT-WRO53 PRESSURE ROSE- 1152GP7A22- H-2809 E-143 A/28 R3A R.B. A 2A IPX19J WRO4
. TRANSMITTER MOUNT PB E-1995 503 WR 1PT-WRO55 PRESSURE ROSE- StS2GP7A22- H-2809 E-150 E/27 RSA R.B. A 2A WRO5 e
. TRANSMITTER MOUNT PB E-1995 570
$PAGE 71 0F 76 m
O M M SARGENT&LUNDY
=SNONMER9
l PROJCCT NUMBER 4130-05 DATE 22 DEC 83
, REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION D01326
- PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SV NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SitEET t'R 1PT-WRO57 PRESSURE ROSE- 1152GP7A22- H-2809 E-150 E/25 RSA R.B. A 2A WROS
. TRANSMITTER MOUNT PB E-1995 570 WR 1TE-WRO33 TEMP ELEMENT ROSE 183-108-1 H-2809 E-143 A/24 R3A R.B. A 2A LOC MTD WR06
. MOUNT E-3740 516 WR 1TE-WRC)5 TEMP ELEMENT ROSE 183-108-1 H-2809 E-149 D/26 RSA R.B. A 2A LOC MTD WRO7
. MOUNT E-3740 579 WR ITE-WRO38 TEMP ELEMENT GORDON 402-4107 PO-2949 E-143 B/24 R3A R.B. A 2A LOC MTD WROS
. E-3740 513 WR ITE-WRO40 TEC ELEMENT GORDON 402-4107 PO-2949 E-?49 C/28 R54 R.B. A 2A LOC MTD WRO9 E-3740 579 WR ITE-WR176 TEMP ELEMENT GORDON 402-4107 PO-2949 E-148 D/26 Ric R.B. A 2A LOC MTD WR10
. E-3740 547 WR 1WRO1PA PUMP WEST. 74C24114 H-2185 E-143 B/28 RCA R.B. N/A A 2A WR11
. MOTOR E-1351 503 WR 1WRO1PB PUMP WEST. 74C24114 H-2185 E-143 A/28 R3A R.B. N/A A 21 WR11 MOTOR E-1396 503 WR 1WRO1PC PUMP WEST. 74C24114 H-2185 E-150 E/28 RSA R.B. N/A A 2A WR12
. MOTOR E-1360 570 WR 1WRO1PD PUMP WEST. 74C24114 H-2185 E-150 D/28 RSA R.B. N/A A 2A WR12
. MOTOR E-1403 570 WR 1WRO54 MOTOR OPER- LIMIT SMB-OOO H-2264 E-145 C/27 R2A R.B. N/A A 2A M-58-4 WR13
. ATED VALVE E-1457 525 WR IWROSS MOTOR OPER- LIMIT SMB-OOO H-2264 E-145 B/23 R2A R.B. N/A A 2A M-58-4 WR14 ATED VALVE E-1494 525 WR 1WR158A MOTOR OPER- LIMIT SMB-OOO H-2852 E-150 F/20 RSA R.B. N/A A 2A M-58-2 WR15
. ATED VALVE E-1495 570 WR 1WR1580 MOTOR OPER- LIK.T SMB-OOO H-2852 E-150 F/23 RSA R.B. N/A A 2A M-58-1 WR15 ATED VALVE E-1753 570 WR 1WR160A MOTOR OPER- LIMIT SMB-OOO H-2852 E-150 F/20 RSA R.B. N/A A 2A M-58-2 WR15 ATED VALVE E-1493 570
$PAGE 72 0F 76 e
M n SARGENTMUNDY
? ENDINITE519 .
75 A
& f q ,1 _
PROJECT NUM8ER 4130-05 DATE 22 DEC 83
' REVISION 010
. ZIMMER EOUIPMENT OUALIFICATION 001326
- PLANT ID MODEL SPEC OR COMPONENT / E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SY NUMBER EOUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET
.................................................. ......................... 2...............................
WR 1WR1600 MOTOR OPER- LIMIT SMB-OOO H-2852 E-150 F/23 RSA R.B. N/A A 2A M-58-1 WRt5
. ATED VALVE E-1753 570 WS 1PS-WS249 PRESSURE BARTON 288A h-2866 E-092 H/15 ASA AUX N/A A 2A WS15
. SWITCH E-1989 496 WS edS-WS250 PRESSURE BARTON 288A H-2866 E-092 H/15 ASA AUX N/A A 2A WS15
. SWITCH E-1989 496 WS 1PS-WS251 PRESSURE BARTON 288A H-2866 E-092 H/17 ASA AUX N/A A 2A WS15
. SWITCH E-1986 496 WS 1PS-WS252 PRESSURE BARTON 288A H-2866 E-092 H/17 ASA AUX N/A A 2A WS15
. SWITCH E-1989 496 WS 1PS-WS253 PRESSURE BARTON 288A H-2866 E-092 J/23 ASA AUX N/A A 2A WS15 SWITCH E-1989 496 WS 1PS-WS254 PRESSURE BARTON 288A H-2866 E-092 J/23 ASA AUX N/A A 2A WS15
. SWITCH E-1989 496 WS 1PS-WS255 PRESSURE BARTON 288A H-28G6 E-092 H/20 ASA AUX N/A A 2A WS15
. SWITCH E-1989 496 1
WS 1PS-WS256 PRESSURE BARTON 288A H-2866 E-092 H/20 ASA AUX N/A A 2A WS15
. SWITCH E-1989 496 WS 1PT-WS160 PRESSURE ROSE- 1152GP7A22- H-2809 E-142 E/26 R4E R.B. A 9A WSO1 TRANSMITTER MOUNT PB E-1995 475 WS 1PT-WS161 PRESSURE ROSE- 1152GP7A22- H-2809 E-141 B/25 R4A R.B. A 2A WSO2 TRANSMITTER MOUNT PB E-1995 475 WS 1WSO12A MOTOR OPER- LIMIT SMB-OOO-2 H-2264 E-142 D/27 R4F R.B. N/A A 2A M-30-2 WSO3
. ATED VALVE E-1480 475 WS 1WSO128 MOTOR OPER- LIMIT SMB-OOO-2 H-2264 E - 141 C/27 R4F R.B. N/A A 24 M-30-2 WSO3 ATED VALVE E-1490 475 WS 1WSO13A MOTOR OPER- LIMIT SMB-OOO H-2264 E-142 D/27 R4F R.B. N/A A 2A M-30-2 WSO4 ATED VALVE E-1481 491 WS 1WSO138 MOTOR OPER- LIMIT SMB-OOO H-2264 E-141 C/27 R4F R.B. N/A A 2A M-30-2 WSO4 ATED VALVE E-1491 475
.PAGE 73 0F 76 8
R SARGENT&LUNDY
. = _ _.
73 PROJECT NUMBER 4130-05
,s DATE 22 DEC 83
. ZIMMLR EQUIPMENT QUALIFICATION 001326 e PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA'
*SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHEET o.............................. . ................................................................ .................. . . . . . . . . . . . . . . . . ..
% 1WSO14A MOTOR OPER- LIMIT SMB-OOO H-2852 E-142 D/27 R4F R.B. N/A A 2A M-30-2 WSoti
. ATED VALVE E-1480 475 WS 1WSO14B MOTOR OPER- LIMIT SMB-OOO H-2852 E-141 C/27 R4F R.B. N/A A 2A M-30-2 W SO*,'
. ATED VALVE E-1492 475 WS 1WSO2O LIMIT SWITCH NAMCO EA17031100 H-2266 E-143 A/23 R3A R.B. N/A A 2A M-30-2 WSOS CLOSED POS. E-1989 503 WS 1WSO2O LIMIT SWITCH NAMCO EA17031100 H-2266 E-143 A/23 R3A R.B. N/A A 2A M-30-2 WSO9
. OPEN POS. E-1989 503 l WS 1WSO2O SOLENDID ASCO HV2OO-924- H-2266 E-143 A/23 R3A R.B. N/A A 2A M-30-2 WS12 i . 2VF E-1989 503 i l l WS 1WSO25 SOLENDID ASCO 8320A90 H-2266 E-148 E/27 RfC R.B. N/A A 2A M-30-2 WS13 E-1989 546 WS 1WSO25 LIMIT SWITCH NAMCO EA17031100 H-2266 E-148 E/27 RfC R.B. N/A A 2A M-30-2 WS10
. CLOSED POS. E-1989 546 WS 1WSO25 LIMIT SWITCH NAMCO EA17031100 H-2266 E-148 E/27 RfC R.B. N/A A 2A M-30-2 WS10 l
. OPEN POS. E-1989 546 j WS 1WSO30 LIMIT SWITCH NAMCO EA17031100 H-2266 E-150 E/28 RSA R.B. N/A A 2A M-30-2 WS11
. OPEN POS. E-1989 570 WS 1WSO30 LIMIT SWITCH NAMCO EA17031100 H-2266 E-150 E/28 RSA R.B. N/A A 2A M-30-2 WS11 )
. CLOSED POS. E-1989 570 j WS 1WSO30 SOLENOID ASCO HV2OO-924- H-2266 E-150 E/28 RSA R.B. N/A A 2A M-30-2 WS14 2VF E-1989 570 WS 1WSO73A MOTOR OPER- LIMIT SMB-OOO H-2264 E-141 C/27 R4F R.B. N/A A 2A M-30-2 WSO6
. ATED VALVE E-1458 475 WS 1WSO73B MOTOR OPER- LIMIT SMB-OOO H-2264 E-142 TU27 R4F R.B. N/A A 2A M-30-2 WSO6 ATED VALVE E-1482 4 ; 5' WS 1WSO76A MOTOR OPER- LIMIT SMB-OOO-2 H-22G3 "-150 F/26 RSA R.B. N/A A 2A M-58-1 WSO7
. ATED VALVE E-1481 570 WS 1WSO768 MOTOR OPER- LIMIT SMB-OOO-2 H-2263 E-142 F/18 R4D R.B. N/A A 2A M-58-2 WSO8 ATED VALVE E-1493 479
.PAGE 74 0F 76 l co O
(9 (9 SARGENT$dUNDY 7BN0tNUEftB -
77 v j- ' PROJECT NUFBER 4130-05
- DATE 22 DEC 8%
REVISION 010
. ZIMMER EQUIPMENT QUALIFICATION 001326
- PLANT 10 COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
*SV NUMBER EQUIPMENT MFR NUMBER B/M f40. W/D NO. ELEVATN IN OUT BUILO LEV PASS REV CAT. SHEET
. PACE 75 OF 76 (O
o i SARGENT&LUNDY 3FNOINEEFtB ,.
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f PROJECT NUMBER 4130-05 DATE 22 DEC 83-PLANT ID- ZIMMER EQUIPMENT OUALIFICATION 001326- REVISION 010
*SY COMPONENT /- MODEL NUMBER 'EQUIPM SPEC OR E.I. OwG MFR COL / ROW CONTAIN
.......................ENT.... .................. ./M NO........ W/D NO.
NUMBER B ELEVATN FLD ACT/ ADO 0588 DATA
.......................IN..
~ OUT BUILD LEV PASS REV CA
..........................T...
SHEET
.PAGE 76 0F 76 5
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FILE: SOLID STATE REVISED: 12/27/33 ENVIRO'::!E':TAL CUALITICATIO': DOCL7! CITATION REFERE!:CES
. MA::'JFACTURER: N/A .
MODEL NUMBER: N/A CO:?0:; cit: SOLID STATE ELEC. F0t ' T P . DESCRIPTION %
', , REFERE::CC
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- 1) Environmental Conditions i x Zimmer Desis;n Criteria A51-9 Rev. 4
[ May 12, 1983
- 2) Table 2.1-1, Revised 12/21/83 j Environmental Qualification Report Safety Related Equipment Contain h g for Class lE Equipment Solid State Electronics F d Environments \
s D:
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EX DATA SilEt;: E001 JUSIIFICA'IION FOR EXEMPTING EOUIPMENT l FROM ENVIRONMENTAL QUALIFICATION REQUIREMENTS
@d, SYSTEM: Nuclear Boiler EQUIPMENT TAG NUMBERS: IB21-NO36 A,B,C.D MANUFACTURER: Yarway_
MODEL NUMBER: 4418C
-POWER: [ ESSENTIAL POWER C .NON-ESSENTIAL POWER ESSENTIAL POWER NON-ESSENTIAL CABLE JUSTIFICATION:
Level indicating switch provides no safety function to mitigate LOCA or HELB conditions. Switches are classified esssatial because they are required to mitigate ATWS conditions. Failure mode effects analysis shows that failure . fN
\,/I of this device will not affect plant safety.
l e 4 e . 9 FAILURE MODEL EFFECTS ANALYSIS (ATTACHED): -NB43, NB44 . . PREPARED BY: .. d. M
~'
n.) DATE: 7 /2 -p %
. -- ..., . _ . . . - . . . . . . . - - - - .w .-- - .. *-..-m.
=* - -.-w, w <-y, y- yr ,m-y---w g y v g- mm,-.w,, .p_ 9 9
05/11/62 CISCIO:AII GAS & ELECTb1C CONPA4Y PAGE 103 10: no-43 at.. d. ZIMPEk tduCLEAR POW 8F STATIOS UNIT 1 REV A
.JTIFIC ATIO ri FOR INTERI:t GPERATION OF: 1821-NO36A,C LOCATION'9-1C DESCRIPTION: LEVEL INDICATING SWITCH SYSTE!4: NUCLEAR BOILER (NB) SUBSYS REC PUMP TRIP (B33A)
SAFETY FUNCTION EMERGENCY REACTOR SHUTDOWN (ERS) SECIRCULATION PUMP ON LOW WATEP LEVEL SENSING FEATURE DIV:I
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL CONTACTS OPEN A LOCA CONTACTS CLOSED 3 1/2 HRS + B MSL/FW BREAK CLOSE Oh DEhAAD 3 1/2 HPS + C RCIC BREAK CLOSE ON DEMAt:D 3 1/2 HRS + D PKCU bpFah CLOSE On DEM At:0 3 1/2 HRS +
--------- -------------------QUALIFICATION SUveARY-----------------------------
PAPASETER -----DEP.0t4STRATED----- ----------------REQUIRED---------------- EVENT A EVENT D EVEtiT C EVENT D TE?PEFATUFE, DEG F 250 45-129 230 213 234 IECF-H2O N0dE -0.25 16 PSIA 15.7 PSIA 24 PSIA 100 100 100 h' *JS S UP E . IDITY, %RH RaDIATI0t!,, RADS 100 NOME 0-90 7.24E6 6.6ES 6.6ES 6.6E5 OPERABILITY 3 1/2 HBS 100 DAYS 1 DAY 1 DAY 1 DAY OTHER: !;/ A
--------- -------------------- CLASS 1 E I ri T E R F A C E S - - - - -- ---- - -- - --- - - -- - - - - - - -- ------- - ----- I:iPUTS --------------- ----------------- GUTPUTS --------------
80TIVE PbvER: iv / A iDTIVE POWER: d/A
~
CONTROL POhEC: 6,9KV SdGR 1E CUB 5 00HTPGL PueER: N/A set. SING SIG:AL: P P'l AATER LEVEL S- 82A CLOSES BELO'; LEVEL 2 EXECUTE SIG;i AL: 833A-K101A,K101C COMMAND SIGNAL: N/A INHIBIT SIG7.AL: 1521-f.036A-22 i d 21 -!' 0 3 6 C -Z2 . PROCESS SIGJAL: N/A C0aTACT PROTECTORS PERdISSIVE SIGNAL: N/A ( ,j ***** CINCIeNATI GAS & ELECTRIC PROPRIETARY INFORM.ATION ***** (
05/11/e2 CInCId:4ATI GAS & EL6CThIC COMPANY PAGE 104 ID: 4c-43 "*t. H. ZI't"ER r.UCLEAP P0aER STATIOt- UNIT 1 REV A hEr.II AL FAILURE FAILUPE ISOLATION IfTERFACE: Sh2A CONTACTS C-i.0 DEVICE: NA CAUSE: Sh0PI TO GROUND BASIS: DC SYSTEM UNGROUNDED FAILUBE MODE: NO EFFECT FAILURE EFFECT: tJONE PUTEf.TIAL FAILURE FAILUBE ISCLATION IN1ERFACE: Sh2A CONTACTS C-hD DEVICE: NA CAUSE: OPES CIRCUIT BASIS HON-PROPAGATING FAILURE FAILUPE ubDE: OPEN C0tiTACTS FAILUBE EFFECT: RECIRC PUMP "A" TFIP 0.4 LOW WATER LEVEL IS UUAVAILABLE. . POTEtiTIAL FAILUPE FAILUFE ISOLATION INTERFACE: SW2 A COr. TACTS C-110 DEVICE: NA
- SHORT CIRCUIT BASIS: N0d-PROPAGATING h)CAUSE' F ILURE F 0DE: CLOSED CONTACTS FAILURE 9
FAILUFE EFFECT: IbADVERTENT TRIP OF RECIRC PdNP "A" 04 LO4 #ATER LEVEL SIGNAL. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: SW2A CONTACTS C-NO CEVICE: NA CAUSE: CALIBPATIUd ORIFT BASIS: N0a-PROPAGATING FAILURE FAILuhE .vcDE: Cor T ACT OPEN/ CLOSED FAILURE EFFECT: CCdSEQUEMCE THE SAME AS OPEN CIRCUII/SHORI CIBCUIT. [ . [ i w-. w .. 4 = + = - -
05/11/d2 CI.CIWr4ATl GAS & ELECT 91C CDiPANY PAGE 105 ID i.6-43 AM. F. . ZI'..%ER *:UCLEAR PO* EF ST ATIO*i Ut:II 1 REV A 4
, .g St l (N 'pECIPCULATION PU.9P TRIP IS DESIGNED TO MITIGATE ATWS AND IS NOT BE I PEQUIREC TO !;1TIG ATE LOCA 08 HELO. FAILURE DOES *'OT PROPAGATE.
t .
REFERENCES:
P=83-1 PEV. V: E1010/PG.-RR02 REV. 4; E0 DATA SHEET NB31. t t'ITI G ATIC 4 EVEliT CAPABILITY A B C D ADE00 ATE X X X X INADEQUA12 - - 1
.Q 4
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y* w- g,-w+- 9y---.ygy 2sy-y-u-m g-yp- -yy-w=--+--tmvr w r ir--w-
C I T.C I t. A l l GAS & ELECIPlC COMFA"Y PAGE 106 I 05/11/a2 REV A l ID2 hB-44 o'. h. II.MEP JUCLdAh PO'iER STATIDH U7 IT 1 l
~
JbSTIFICATION FOR IuTERIM OPEPATION OF: 19 21 -il0 3 6 B , D LOCATION:R-1C DESCRIPTION: LEVEL INDICATING SWITCH NUCLEAR BOILER (dB) SUBSYS REC PUMP TRIP (B33'A) SYSTEM: SAFETY FUNCTIUN:EPERGEf!CY REACTOR SHUTDOWh (EPS) TRIP RECIRCULATION PUMP DN LO/' LEVEL SEhSING FEATURE DIV:II
-- ---------DEVICE STATUS--------- ---ESTIMATED TIME--- -------EVEf3T----
- 10 FAILURE NORNAL CONTACTS OPEd CONTACTS CLDSED 3 1/2 HRS +
A LOCA 3 1/2 HRS + B MSL/FW BREAK CLOSE 0:3 A DENAr<D CLOSE ON A DEMAND 3 1/2 HRS + C RCIC PREAK 3 1/2 HRS + D RWCU BPEAK CLOSE Ota A DEMAND
--------- ----- ----- -------QUALIFICATION SUM.*ARY-----------------------------
----------------REQUIRED----------------
PARAMETEp -----DEMONSTRATED----- EVENT D EVEST A EVENT 3 EVE.NT C 45-129 230 213 234 IFMPEPATUPE, DEG F 25 15.7 PSIA 24 PSIA
-0.25 16 PSIA ISSURE. IiiC H-n 20 N O. . E 0-90 100 100 100 6'MIDITY.
s
%RH 100 7.24E6 6.6ES 6.6E5 6.6ES RADIATI0t!. RADS N06E 100 DAYS 1 OAY 1 DAY 1 DAY OPERABILITY 3 1/2 HRS OTHER: N/A
--------- -------------------- CLASS 1E INTERFACES -----------------------------
----------------- OUTPUTS --------------
--- ----- ----- 1r. PUTS ---------------
N/A MOTIVE POWER: N/A MOTIVE POWER: CONTROL PbhEP: 6,9KV SdGP 1D CUB 5 CDuTROL POWER: N/A SEtsSING SIG i AL: PPV AATEd. LEVEL Sa s2A CLOSES BEL 0e 333-K1013,K101C LEVEL 2 EXECUTE SIGNAL: COMMAND SIGNAL: N/A INHIBIT SIG:;AL: 1821 '30365-Z2 n/A 1521 'iO 360-Z2 PRCCESS SIG.!AL: CO.-lT ACT PFJTECTORS PER.:ISSIVE SIG:;AL: N/A kj) ***** CIhCINJATI GAS & ELECTRIC PROPRIETARY INFOR'4 ATIOr! *****
l 05/11/82 CI-CI. ATI GAS 6 ELECTFIC CUMPAI.Y PAGE 107 cm. H. IIt+E4 ..UCLEAR PO.vER STATIO'. Ut.IT 1 REV A 10: r.e-44 O,'E:4TI Fw i AL FAILURE FAILURE ISOLATION If.TEHFACE: SL2A CONTACTS C-40 OEVICE: NA CAdSE: SHORT TO GA00a0 BASIS: OC SYSTEM UNGROUNDED FAILURE MODE: NO EFFECT FAILURE EFFECT: NONE POTENTIAL FAILURE FAILUPE ISOLATION II;TERF ACE: Sa'2 A C-ObTACTS C-NO DEVICE: NA CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE HDDE: OPEl. CONTACTS FAILURE EFFECT: BECIBC PUMP "B" TRIP O!4 L0n WATER LEVEL IS UNAVAILABLE. , , POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: S*s2A COUTACTS C-NO DEVICE: NA SHORT CIhCUIT SASIS: NON-PROPAGATING
')CAUSE:
aILUBE uoDE: CLOSED C0hTACTS FAILURE EFFECT: 16ADVEPTELT TRIP OF RECIRC PUdP B" 03 LOW WATER LEVEL SIGNAL. POTEliTI AL FAILURE FAILURE ISOLATION INTERFACE: SW2A CONIACTS C-MO DEVICE: NA CAUSE: CALIBRATION DRIFT BASIS: NON-PROPAGATI.VG FAILURE .400E: CouTACT OPEM/CLOSE0 l FAILG8E EFFECT: CONSEcuENCES THE SAME AS OPEN CIRCUIT /SHORT CIRCUIT l l F% l ( !)
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A ' 05/11/62 CIiCI5NATI GAS & ELt.CTRIC COhPAttY 4 PAGE 108
-ids 7.d=44 *>. 84 . ZI'sER n U C L E A R.. ,P D .rd R S I A T UfJ IT ION l ' PEV A -
15: ' [)% PECIPCULATICS PU."P TRIP IS pESIGNED TO MITIGATE ATAS AND IS NOT BEQUIRED TO MITIGATE LOCA'AhD HEL8. FAILURE DOES NOT PROPAGATE. REFERhNCES* M-83-1 REV. V; E101U/PG-BP03 REV. Yr EQ DATA SHEET NB31
. 3
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MITIGATIO: EVEt!T . CAPABILITY A B C D ADEOUATE --X X X X Ili ADE00 AT E , t - -
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EX DATA S:-:EET: E002 JUSTIFICATION FOR EXEMPTING EOUIPMENT FROM ENVIRONMENTAL OUALIFICATION REOUIREMENTS SYSTEM: Reactor Building Ventilation, luroine Asuilding ventilation, Core Standby Cooling System Equipment Cooling EQUIPMENT TAG NUMBERS: MANUFACTURER: Pyrotronics MODEL NUMBER: DIS 3/5A POWER: b ESSENTIAL POWER NON-ESSENTIAL POWER U ESSENTIAL POWER, NON-ESSENTIAL CABLE JUSTIFICATION: These smoke detectors are listed as I ESS-1 P in the instrument index. Review of electrical drawings reveals that the cables to the detectors are non-essential. Instrument index will be changed to note that these are non-essential. Justi-
, fication to be provided with Justification for Interim Operation to show that u failure cannot effect plant safety.
FAILURE MODEL EFFECTS ANALYSIS (ATTACHED): To be orovided with JIO ,m PREPARED BY: . // DATE: '7 - ' 2 ~/ '
EN DATA SilEE!: E003 JUSTIFICATION FOR EXEMPTING EOUIPMENT [ ROM EWIRONMENTAL OUALIFICATION REQUIREMENTS SYSTEM: Standby Liquid Contrn! EQUIPMENT TAG NUMBERS: See attached EQEL MANUFACTURER: See attached EQEL MODEL NUMBER: See attached EQEL POWER: ESSENTIAL POWER C NON-ESSENTIAL POWER U ESSENTIAL POWER, NON-ESSENTIAL CABLE JUSTIFICATION: The Standby Liquid Control System provides an alternate method of achieving suberitic.ality in the hypothetical event of failure to insert the control rods in accordance with General Design Criterion 22. Operation is manually initiated and boron is injected to accomplish safe shutdown. It is an independent backup system to the~ Control Rod Drive System. It is not needed to mitigate LOCA or HEL3 Conditions. Failure mode effect analysis showsthat no failure mode exists that could propagate electrically to disable any other safety related system. FAILURE MODEL EFFECTS ANALYSIS (ATTACHED): SC-1,2,3,4,5,6,7,& 8
-- PREPARED BY:
/[. M -
/
DATE: 7- / 2 -p u . ~ = . - - , , . . .
. . . . . - . , - - -- -- . - . . - - ~
19 ,3
' $ \n, m
PROJECT NUMBER 4130-05 DATE 29 dCN 82 REVISION 006 ZIMMER EQUIPMENT OUALIFICATION - D01346 1
- PLANT 10 COMPONENT / MODEL SPEC OR E.1. DWG COL /30W CONTAIN FLD ACT/ ADO 0500 DATA eSV NUMBER EQUIPMENT MFR . NUMBER 8/M NO. W/D NO. ELEVATN IN OUT 8UILD LEV PASS REV CAT. SHT.
SC 1C41-FOO8 LIMIT SWITCH NAMCO EA-170 H-2852 C/29 Cl DRYWEL P EX EOO3
. 46302 540 SC tC41-F031 LIMIT SWITCH NAMCO EA-700 H-2264 A/20 RSA R.B. P EX EOO3 i 80011 570 3 SC IC41-F031 LIMIT SWITCH NAMCO EA-700 H-2264 A/20 RSA R.B. P EX EOO3 80012 570 t . _ - ..
SC IC41-COOlA PUMP MOTOR G.E. TYPE 324AN H-22tO E-149 A/19 RSA R.B. N/A A EX EOO3 567 SC IC41-COOtB PUMP MOTOR G.E. TYPE 324AN H-22tO E-149 A/19 R54 R.S. N/A A EX EOO3 567 SC IC41-FOOfA MOTOR OPER- LIMIT SMB-OOO-2 H-2263 E-149 A/18 RSA R.S. N/A A EX M-51 EOO3 ATED VALVE E-1456 570 SC IC41-FOOtB MOTOR OPER- LIMIT SMB-COO-2 H-2263 E-149 A/18 RSA R.8. N/A A EX M-57 EOO3 ATED VALVE E-1483 570 SC 1C41-FOO4A EXPLOSIVE CONAX 1832-159- H-2210 B/19 RSA R.B. A EX M-57 EOO3 VALVE 01 567 SC 1C41-FOO4B EXPLOSIVE CONAX 1832-159- H-2210 B/19 RSA R.S. A EX M-57 EOO3 VALVE 01 567 4 l SC 1C41-FOO8 LIMIT SWITCH NAMCO EA-170 H-2852 C/21 C1 DRYWEL N/A P EX M-57 EOO3 46302 540 . t
$PAGE 10 0F 78 m
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SARGENTtdUNDY eNetNEERS . i l 1 i a
05/09/82 CIACI.11ATI gad & ELECTRIC COMPANY PAGE 350 ID: SC-1 WM. H. ZI9mER fiUCLEAR P0kER STATIO.A UNIT 1 REV A
.STIFICATI0ti FOR IhTERIM GPERATION OF: 1C41-C001A LOCATION:p-5A DESCRIPTION: PUMP MOTOR SYSTEM: STANDBY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTION:EMEFGENCY REACTOR SHUTDOWN STAhDSY LIOUID PUMP MOTOR EXECUTE FEATURE DIV:I . -------EvFflT------- ---------DEVICE STAIUS--------- ---ESTIMATED TIME---
TO FAILURE NOR!iAL OFF A LOCA 0FF 6 hBS B MSL/FW BBEAK OFF > 1 DAY C RCIC BPEAK OFF > 1 DAY D PWCU BREAK OFF > 1 DAY
--------- ----------- -------QUALIFICATIOt: SU34 MARY-----------------------------
P AR AliETER -----DEM0nSTBATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVEr:T C EVENT D TEMPERATURE, DEG F 355 45-129 219 190 170
- SSURE, INCH-H2O NONE -0.25 16.5 PSIA 15 PSIA 15 PSIA
*)MIDITX,%RH N0aE 0-90 100 100 100 ADIATION, RADS 2.2E5 5.1Eb 3.E5 3.E5 3.E5 OPERAEILITY 6 HRS o/A f/A N/A t;/A OTHER:
------- - - ------- ---------- CLASS 1E INTERFACES -----------------------------
--- ----- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: 480V,ABMCC1A,C0hPT4E MOTIVE POWER: N/A C0hTROL POWER: tJ/ A CONTPOL POWER: t4 / A SENSIfiG SIGid AL: N/A EXECUTE SIGNAL: N/A COFMAhD SIGt4AL: /ts/A It.HIBIT SIG.'GL: N/A PROCESS SIG.'4 AL : N/A PERx1SSIVE SIGNAL: N/A [-u )I * * **
- CInCIt;U ATI G AS & ELECTRIC PROPRIETARY INFORMATION *****
- - + = =
- _ . > . . . . ~ me=e* **eee . +--.mee =
-es== + = em.o e.. ...we.,
05/09/62 CI.NCI4fsATI GAS & ELECTHIC COMPANY PAGE 351 ids SC-1 a%. H. ZIdrER NUCLEA8 POWEH STATIOri UrJIT 1 REV A 3
.TENIIAL FAILURE FAILURE ISOLATION INTERFACE: POTOR TERMINALS DEVICE: Ji/ A CAUSE: U P E t. CIRCUIT;3PH,2PH BASIS: NON-PROPAGATING F AILURE .40DE': DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM. SLC PUMP A UNAVAILABLE.
POTEUTIAT, FAILURE FAILURE ISOLATION INTERFACE: MOTOR TERMINALS DEVICE: CIRCUIT BREAKER CAUSE: OPEN CIRCUIT; iPH 9 ASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILURE MODE: DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEli. SLC PUMP A UWAVAILABLE. . POTENTIAL FAILUPE FAILURE ISOLATION I t.TEF F A CE : HOTOR TERMINALS DEVICE: CIRCUIT BREAKER
')CAUSE: SHI CRCT/SHT TO GRND BASIS: NOT SUBJECTED TO HAFSH ENVIRONMENT aILURE MODE: DE-ENERGIZED FAILUPE EFFECT! FAILURE LIMITED TO SLC SYSTE". SLC PUMP UNAVAILABLE.
BASIS: FAILUPE DOES NOT PROPAGATE BEYOND SLC SYSTEM. ATWS NOT CONSIDERED. l BEFERENCES: l P&ID, FSAP FIG. 4.2-24 ! E1010/PG. SC01 PEV. J EO D.S. C412 AITIGATION EVENI CAPABILITY A B C D ADEOUATE N d N N l l INADEQUATE
05/09/82 CI.NC Ire n A TI GAS & ELECTPIC COMPAJY PAGE 352 ID: SC-2 he. H. ZI "ER WUCLEAR PJnER STAII0ti UNIT 1 REV A S a;
/
9JTIFICATIOt.FOR INTERIM OPERATION OF: 1C41-C001B LOCATION P-5A DESCRIPTION PUMP MOTOR SYSTEM: STANDBY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTIOh EMERGENCY BEACTOR SHUTDOWri STAT.DBY LIQUID PUMP t40 TOR EXECUTE FEATURE DIV:II
--- - - - E V E ta T - - - ---- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
- TO FAILURE N0ld M AL OFF A LOCA 0FF 6 HRS B MSL/FW RBEAK OFF > 1 DAY C RCIC BREAK OFF > 1 DAY D RWCU BBEAK OFF > 1 DAY
--------- --------- ---------QUALIFICATIOd SUMVARY-----------------------------
PARAMETEP -----DEMONSTRATED--~~- ----------------REQUIRED---------------- EVENI A EVENT B EVENT C EVENT D TE.v.P E R A TUR E , DEG F 355 45-129 218 190 170
'SSURE, INCH-H2O NONE =0.25 16.5 PSIA 15 PSIA 15 PSIA lh' )$1DITY , %BH t: ode 0-90 100 100 100 *m0IATION, RADS 2.2E5 5.1E6 3.E5 3.E5 3.E5 OPERABILITY 6 HRS N/A h/A N/A N/A OThER: --------- ----------- -------- CLASS 1E INTERFACES ----------------------------- --- - - - ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: 480V,ABMCC1B,CMPT12D MOTIVE POWER: N/A CONTROL F0WER': N/A N/A CONTROL POWER: set 3 SING SIGN AL: h/A EXECUTE SIGNAL: N/A COMMAND SIGhAL: N/A IEHIBIT SIGNAL: I!/A PRCCESS SIGNAL: t;/ A PERMISSIVE SIGNAL: N/A i ***** CINCINNATI GAS & ELECT'IC PROPRIETARY INFORMATION *****
i l 05/09/82 CIhCINhATI GAS & ELECTRIC COMPANY PAGE 353 ' ID: SC-2 'eM. n. ZIV.kER HUCLEAR P0kER STATION UNIT 1 REV A (")]TEhTIALFAILUPE IiiTERFACE: HOTUR TERMINALS FAILdRE ISOLATION DEVICE: N/A CAUSE: OPEN CISCUIT13PH,2PH BASIS: 'NON-PROPAGATING FAILURE MdDE: DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM. SLC PUMP B UNAVAILABLE. POTENTIAL FAILUPE FAILURE ISOLATION INTERTACE: HOTOR , TERMINALS DEVICE: CIRCUIT BREAKER CAUSE: OPEN CIRCUIT; 1PH BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILURE MODE: DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM. SLC PUMP B UbAVAILABLE. , , POTENTIAL FAILUPE FAILURE ISOLATION IhTERFACE: MOTOR TERMINALS DEVICE: CIRCUIT BREAKER
' 3CAUSE: SHT CRCT/SHT TO GRND BASIS: NOT SUSJECTED TO
(+,,s) )ILURE MbOE: DE-ENERGIZED HARSH ENVIRONMENT FAILURE EFFECT: FAILUPE LIMITED TO SLC SYSTEM. SLC PUMP B UNAVAILABLE. BASIS: FAILURE DOES t40T PROPAGATE BEYOND SLC SYSTEM. ATdS NOT CONSIDERED. PEFERENCES: P&IC, FSAR FIG. 4.2-24 E1010/PG. SC02 REV. J EQ D.S. C412 MITIGATIdti EVE:4r CAPABILITY A B C D ADE00 ATE h N N fi {'x. ' IdADEQUATE _, , ,, ,, , .wm - * - * * * "' *'
- - - - - - - - , - ~ '
05/09/E2 CINCINNATI GAS & ELECTFIC CO<iPANY PAGE 354 ID: SC-3 aN. H. ZIPNEF NUCLEAH POWEB STAII0t! UNIT 1 PEV A
- 3 y TIFICATION F0h I'NTEdIM OPERATION OF: 1C41-f001A LOCATION: R-5A DESCRIPTION: VALVE MOTOR OPERATOR SYSTEM: STANDBY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTION:EMEFGENCY REACTOR SHUTDOWN STOPAGE TANK OUTLET VALVE EXECUTE FEATURE DIV:I
-------EVEt:T------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
. TO FAILURE N O RP. AL CLOSED POSITION A LOCA CLOSED POSITION > 100 DAYS B MSL/FW BREAK CLOSED POSITION > 1 DAY C FCIC BREAK CLOSED POSITION > 1 DAY D EWCU BREAK CLOSED POSITION > 1 DAY
--------- -------------------QUALIFICATION
SUMMARY
PARAMETEF -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENI D TEMPERATURE,-DEG F 250 45-129 218 190 170
)SSURE, IHCH-H2O 25 PSIG -0.25 16.5 PSIA 15 PSIA 15 PSIA
%RH 100 0-90 100 100 100
[\;[91DITY,
.JIATIon, RADS 2.E7 5.1E6 3.E5 3.E5 3.E5 OPERABILITY 16 DAYS h/A N/A N/A N/A OTHER: --------- ----------- -------- CLASS 1E INTERFACES ---------------------~~~----- --------- - --- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: HOTIVE POWER: CONTROL 50AER: CDlTROL POWER: SENSING SIGNAL: EXECUTE SIGNAL: ! COMMAND SIGNAL: IriHISII SIGN AL: PROCESS SIGNAL: r PEFMISSIVE SIGMAL: (' ***** CINCINNATI GAS & ELECTRIC PROPRIETARY INFORMATION *****
~0$/09/G2 CII;CINNATI GAS & ELECTPIC COMPAhY. PAGE 355
'ID3 SC-3 ar. H. ZIPMER siUCLEAR POWER STATI0f; UFfT 1 PEV A
~
cs p. Q IEtlTIAL FAILURE F4ILURE ISOLATION INTERFACE: TERMINALS T1-T2-T3 DEVICE: N/A CAUSE: OP E.N CIRCUIT, 30, 20 BASIS: NON-PROPAGATING FAILURE MbDE: MOTOR DE-ENERGIZED FAILURE-EFFECT: FAILURE LIMITED TO SLC SYSTEh; SLC PUMP UNAVAIL-ABLE. POTENTIAL FAILURE FAILURE ISOLATION IriTERFACE: TERMI!4,ALS T1-T2-T3 DEVICE: CIRCUIT BREAKER CAUSE: OPEN CIRCUIT, 10 BASIS: NOT SUBJECTED TO FAILURE M'0DE: MOTOR ENERGIZED, 20 FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM; LOSS OF VALVE POSI-IION II.DICATION. . . POTENTIAL FAILUBE FAILURE ISOLATION INTERFACE: TERMItALS T1-T2-T3 DEVICE: CIRCUIT BREAKER SHT TO GRND/SHT CRCT BASIS: NOT SUBJECTED TO
<~])CAUSE: HARSH ENVIRONMENT k.;/.ILUREMbDE:
. MOTOR DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEp; LOSS OF VALVE POSI-TION INDICATION.
POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: TSC/LS1-1C/LS8-9C DEVICE: CIRCUIT BREAKER CAUSE: HGT SHORT/SHORT CRCT BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILURE . MODE: CLOSED CONTACTS FAILURE EFFECT: FAILUPE LIMITED TO SLC SYSTEM; MOTOR OVERLOADS. POTEteTIAL FAILUBE FAILURE ISOLATION Ie:TERF ACE: TSC/LS1-1C/LS9-SC DEVICE: N/A CAUSE: OPEa CI.RCUII PASIS: F0f*-PROPAGATING FAILURE pdDE: OPEn CONTACTS 1 . LUBE EFFECT: CLOSING FUNCTION LOST, BUI VALVE NORMALLY CLOSED; nC SAFETY IMPACT. { .
05/09/d7 CI;. cit.MATI GAS & ELECTHIC COMPANY PAGE 356 ID: SC-3 ad. H. ZInsta libCLEAR P0aER STATIUa UNIT 1 REV A fENTIAL FAILU"E FAILURE ISOLATION It4TERF AC E: TGC/LS1-1C/LSB-BC DEVICE: FUSE CAUSE: SHORT 10 GRobi.D BASIS: fl0T SUBJECTED TO HARSH ENVIRONMEhT FAILURE MODE: LOSS OF CONTROL POWR FAILURE EFFECT: SAME AS OPEN CIRCUIT (10). POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: TSO/L55-5C/LS4-4C DEVICE: N/A CAUSE: OPEli CIRCUIT BASIS: NON-PROPAGATIhG FAILURE MODE': OPEN CONTACTS FAILURE EFFECT: CLOSING FUNCTION LOST; b0 PROPAGATIOti BEYOND SCL SYSTEM. , , POTENTIAL FAILUPE FAILURE ISOLATION
, li4TERF ACE: TSO/LSS-5C/LS4-4C DEVICE: 2003, K3A, K3B
)CAUSE: HDT SHORT/SHORT CRCT BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT
.ILUBE vbDE: CLLSED CONTACTS FAILURE EFFECT: FAILURE LIhlTED TO SLC; ItiADVERTENT VALVE OPEIING.
POTENTIAL FAILUPE FAILURS ISOLATION Ir.TERFACE: TSO/LS5-5C/LS4-4C DEVICE: FUSE CAUSE: Sh0RT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILUPE iODE: LOSS OF CONTROL PowR FAILURE EFFECT: SAME AS OPEN CIRCUIT (10). POTEhTIAL FAILUFF FAILURE ISOLATION IhTERFACE: LS3-3C/LS7-7C/LS2-2C DEVICE: N/A CAUSE: OPEN CIRCUlT BASIS: NON-PROPAGATING FAILUEE MODE: OPEN CO:lTACTS ,q ILURE EFFECT: IMPFOPER/ LOST VALVE POSITION ItiDIC ATIO i. ( :.) .
^- - um ..-m. ,,..e e. _ - - - - . = . _ _ , . . . . _ _ _ _ , , , , , _ _ _ _
05/09/02 CI..CIrd.ATI GA5 & ELECTRIC COMPANY PAGE 357 ID: SC-3
**. H. ZIMAER adCLEAR P0nEF STATION UNIT 1 R E V, A i,
KfENTIAL FAILURE FAILURE ISOLATION INTERFACE: LS3-3C/LS7-7C/LS2-2C DEVICE: N/A CAUSE: HOT SHORT/SHORT CBCT BASIS: NON-PROPAGATING FAILURE MODE: CLOSED CONTACTS FAILURE EFFECT: IMPROPER / LOST- VALVE POSITION INDICATION. POTENTIAL FAILURE FAILURE ISOLATION IfiTERF ACE: LS3-3C./LS7-7C/LS2-2C DEVICE: FUSE CAUSE': SHORT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILURE MdDE: LOSS OF CONTROL POWR FAILURE EFFECT: SAME AS OPEN CIRCUIT (10). BASIS: ~ FAILURE DdES h0T PROPAGATE BEYOND SLC SYSTEP. VALVES FAIL AS IS.
,ATWS NOT CONSIDERED.
REFERENCES:
P&ID,.FSAR FIG. 4.2-24 EIU10/PG. SCO3 REV. G EQ D.S. X010 l MITIGATION EVENT CAPABILITY A B C D l ADEOUATE N N N N INADEQUATE l l l u
\ I
-* h e-w . . . ..- 2 --es. - . -e===- *< -me -
*==ee g - *-
05/09/02 CI':C I m h A TI GAS & ELECTFIC CO.iPANY PAGE 358 ID8 SC-4 66 H. ZI9:tER NUCLEAR P0wiB STATION UNIT 1 REV A
\c dSTIFICATION FOR IlTERIM OPERATION OF: 1C41-F001B LOCATION: P-5A DiSCRIPTION: VALVE MOTOR OPERATOR SYSTEM: STANDBY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTION:EAEHGENCY REACTOR SHUTDOWN STORAGE TANK OUTLET VALVE EXECUTE FEAIURE DIy:II
-------EVENT------- ---- ---DEVICE STATUS--------- ---ESTIMATED TIME---
- . TO FAILURE NOFMAL CLOSED POSITION A LOCA CLOSED POSITION > 100 DAYS B MSL/F4 BREAK CLOSED POSITION > 1 DAY C RCIC BBEAK CLOSED POSITION >1 DAY D RWCU BREAK CLOSED POSITION > 1 DAY
--- ----- -------------------QUALIFICATION
SUMMARY
PARAMETEP -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F 250 45-129 218 190 170 iSSURE, IdCH-H2O 25 PSIG -0.25 16.5 PSIA 15 PSIA 15 PSIA (^)MI DITY , %RH 100 0-90 100 100 100
\ct.DIATIOu, RADS 2.E7 5.1E6 3.E5 3.E5 3.E5 OPEPABILITY 16 DAYS N/A N/A N/A N/A OTHER:
--------- --------- - -------- CLASS 1E I.4TERFACES -----------------------------
--------- ----- Inputs ---------------
----------------- OUTPUTS --------------
MOTIVE P0XEN: MOTIVE PubER: , -CONTROL POWER: C0i4 TROL POWER: SENSING SIGNAL: EXECUTE SIGNAL: COMMAND SIGNAL: INHIBIT SIGNAL: PROCESS SIGNAL: PERMISSIVE SIGNAL: T 1 f'T ***** CILCI?*bATI GAS & ELECTRIC PROPFIETARY INF0hMATION *****
\.f, e
m = * . - . . . .w.. -- = ,,,%.. _m _ w- p-- -i-,y. - .--. , -w-., .--y - - - - +
05/09/92 CliiC I h t' ATI GAS & ELECTRIC COMF AliY PAGE 359 ids SC-4 tn. H. ZIMMER NUCLEAR P0aEh STATION Ui?IT 1 REV A EhTIAL FAILURE FAILURE ISOLATION INTERFACE: TERMINALS T1-T2-T3 DEVICE: N/A CAUSE: OPEN CIRCUIT, 30, 20 BASIS: NON-PROPAGATING FAILURE M'0E: 0 MOTOR DE-ENERGZED 20 FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM; SLC PUMP UNAVAIL-ABLE. POTEi4TI AL FAILURE FAILURE ISOLATION INTERFACE: TERMINALS T1-T2=T3 DEVICE: CIRCUIT BREAKER CAUSE: OPEN CIRCUIT, 10 BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILURd M'DE': 0 HOTOR ENERGIZED, 20 FAILUPE EFFECT: FAILURE LIMITED TO SLC SYSTEM; LOSS OF VALVE POSITION INDICATION. , , i POTEtTIAL FAILURE FAILURE ISOLATION
, INTERFACE: TERMIhALS T1-T2-T3 DEVICE: CIRCUIT BREAKER ICAUSE: SFT TO GRhD/SHT CRCT BASIS: NOT SUBJECTED TO .
HARSH ENVIRONMENT ILURE MODE: h0 TOR DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM; LOSS OF VALVE POSITION INDICATION. POTENTIAL FAILURE FAILURE ISOLATION IhTEPFACE: TSC/LS1-1C/LS8-8C DEVICE: CIRCUIT BREAKER CAUSE': HOT SHORT/SHORT CRCT BASIS: HOT SUBJECTED TO HARSH ENVIRONMENT FAILURE iODE: CLOSED CONTACTS FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM; MOTOR OVERLCADS. FOTENTIAL FAILUPE FAILURE ISOLATION I.'4TEFF A CE : TSC/LS1-1C/LSB-8C DEVICE: N/A CAUSE: OPEh CIRCUIT HASIS: NON-PROPAGATIt.G FAILURE P'0E:0 OPEN CONTACTS ILUPE EFFECT: CLOSING FUNCTION LOST, BUT VALVE NORMALLY CLOSED; JO SAFETY IMPACT. (u .
s 05/09/62 CI;CI;bATI GAS &. ELECTRIC CO*PANY PAGE 360 ID: SC-4 eM. H. ZIMPEP NUCLEAR P0wER STATION UNIT 1 REV A ($
\4/ ENTIAL FAILURE FAILUPS ISOLATION IhTEFFACE: TRSC/LS1-1C/LSB-8C DEVICE: FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONSENT FAILURE M0'DE: LOSS OF CONTROL P0dR FAILURE EFFECT: SAME AS OPEN CIRCUIT (10).
POTEhTIAL FAILURE FAILURE ISOLATION IhTERFACE: TSO/LSS-SC/LS4-4C DEVICE: N/A CAUSE': OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE MbOEg OPEN CONTACTS FAILURE EFFECT: CLOSING FUNCTION LOST; N PROPAGATION. POTENTIAL FAILUPE FAILURE ISOLATION INTERFACE: TSO/LS5-5C/LS4-4C DEVICE: S003, K3A, K3B
/ '.CAUSE:
HOI SHORT/SHORT CRCT BASIS: NOT SUBJECTED TO
\ HARSH ENVIRONMENT I'/ILURE k MODE:CLOSED CONTACTS FAILURE EFFECT: FAILURE LIMITED TO SLC; IDADVERTENT VALVE OPENING.
POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: TSO/LS5-5C/LS4-4C DEVICE: FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT I FAILUEE MODE: LOSS OF CONTROL POnP FAILURE EFFECT: SAME AS OPEN CIRCUIT (10). POTERTIAL FAILUPE FAILURE ISOLATION I4TERFACE: LS3-3C/LS7-7C/LS2-2C DEVICE: N/A CAUSE: OPEh CIRCUIT BASIS: N0h-PROPAGATING FAILURE M'DE: 0 OPEN CONTACTS E.~. LUBE EFFECT: IMPROPER / LOST VALVE POSITION INDICATION. U
- h -me se ~ -e.,ms.-., =w. .,
, _ _ _ - , e-- ,, - - - y. _ - , _ _ - . - . . - - - _ - - - . - . - - , .-
05/09/H2 CINCIhNA11 GAS & ELECTPIC CD'4P ANY PAGE 351 ids SC-4 An. H. ZIMnER r4UCLEAR P0nER STATION UNIT 1 PEV A a EDTIAL FAILURE FAILUPE ISOLATION INTERFACE: LS3-3C/LS7-7C/LS2-2C DEVICE: N/A CAUSE: HOT SHORT/SHORT CRCT BASIS: NON-PROPAGATING FAILURE MODE: CLOSED CONTACTS FAILURE EFFECT: IMPROPER / LOST VALVE. POSITION INDICATION. POTEUTIAL FAILURE FAILURE ISOLATION IbTERFACE: LS3-3C/LS7-7C/LS2-2C DEVICE: FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECTED TO FAILURE MbDE: LOSS bF CONTROL POWR FAILURE EFFECT: SAME AS OPEN CIRCUIT (10). BASIS: FAILURE DOES NOT PROPAGATE BEYOND SLC SYSTEM. VALVES FAIL AS IS. ATa5 NOT C0i451DERED. Q.]
\;/
REFEREtaCES: P&ID, FSAR FIG. 4.2-24 ' E1010/PG. SCO3 REY. G EQ D.S. X010 MITIGATION EVENT CAPABILITY A B C D i ADE00 ATE N N N N INADEQUATE l l l (v Y l l l l , ( l
05/09/B2 CIhCINr! ATI GAS & ELECTRIC CO*PANY PAGE 3o2 ID: SC-5 ha. n. ZI.e1EP. NUCLEAR POWER STATION Ut3II 1 REV A k[JSTIFICATION FOR INTERIk OPERATION OF: 1C41-F004A LOCATION'R-5A: DESCRIPTIONEXPLOSIVE VALVE SYSTEM: STANDBY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTION': EMERGENCY REACTOR SHUTDOWN BORON INJECTION VALVE EXECUTE FEATURE DIV:I
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL CLOSED A LOCA CLOSED 1 HR B MSL/FW BREAK CLOSED 100 DAYS C RCIC BREAK CLOSED 100 DAYS D RUCU BREAK CLOSED 100 DAYS
--------- -------------------QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEtiPERATURE, DEG F 185 45-129 218 190 '170
"'SSSURE, I!JC H-h 20 NONE -0.25 -
16.5 PSIA 15 PSIA 15 PSIA
.MIDITY, %PH 100 0-90 100 100 100 ADIATION, RADS 2.2E4 5.1E6 3.E5 3.E5 3.E5 OPERABILITY 1 HRS /100 DAYS N/A N/A N/A N/A OTHER: --------- - ------- ---------- CLASS 1E INTERFACES ----------------------------- --------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE PohER: 400V,ABMCC1A, COMPT 4E MOTIVE POWER: . N/A CONTROL POWER: FUSES CONTROL POWER: N/A SENSING SIGNAL: N/A EXECUTE SIGNAL: N/A COMMAND SIGNAL: h2A l K28 INHISIT SIGNAL: N/A l PROCESS SIGNAL: N/A 1 PEMPISSIVE SIGNAL: N/A i
*** ** CI.7CINNATI GAS & ELECTRIC PROPRIETARY INFORMATION *****
s
, _ -. ...-e.--- -e-- **u==** # "" * * * * ' * *
- 05/09/82 cit CIN. ATI GAS & ELECTFIC C0"PAJY PAGE 363 ID: SC.5 a'. H. Zli'4Eh NUCLEAR POWER STATI0h UllIT 1 REV A L'IEllTIAL FAILURE FAILURE ISOLATION INTERFACE: CONTACTS A1,82,C3,D4 DEVICE: .N/A CAUSE: OPEN CIRCUIT BASIS: NON.rROPAGATING FAILURE MbDE: DE. ENERGIZE.D FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM; EXPLOSIVE VALVE A UNAVAILABLE.
POTENTIAL FAILUFE FAILURE ISOLATION INTERFACE: CO!4 TACTS A1,82,C3,D4 DEVICE: FUSES CAUSE: SHORT CIRCUIT BASIS: NOT SUBJECTED TO FAILURE M'DE: 0 ENERGIZED FAILUPE EFFECT: NONE. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: CONTACTS A1,82,C3,D4 DEVICE: FUSES
'CAUSE: SHORT TO GPUUND BASIS: NOT SUBJECTED TO
'l ' , HARSH ENVIRONMENT edILURE MODE: DE. ENERGIZED FAILUPE EFFECT: SANE AS OPEN CIRCUIT.
BASIS: FAILURE DOES NOT PPOPAGATE BEYOND SLC SYSTEM. ATdS NbT CONSIDERED.
REFERENCES:
P&ID FSAR FIG. 4.2 24 E1010/PG. SC01 REV. J EQ D.S. C411 MITIGATION EVENT CAPABILITY A B C D i ADEOUATE 4 N N 4 () INADEQUAIE t . M + ,g --_-,,,,,p,- .e - ,,- w
- + - - . - + e ,,,,,_3
05/09/92 CII6CIdNATI GAS & ELECTRIC COMPANY PAGE 364 ID: SC-6 h .c . H. IIviEF NUCLEAR PO4ER STATI0h UNIT 1 REV A
\sdSTIFICATION FOR INTEbIM OPERATION OF: 1C41-F004B LOCATION ': R-5 A DESCRIPTION: EXPLOSIVE VALVE SYSTEM: STANDBY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTIdN': EMERGENCY REACTOR SHUTDOWN BURON IliJECTION VALVE EXECUTE FEATURE DIV:II
--- ---EVENT------- -
-------DEVICE STATUS--------- ---ESTIMATED TIME---
T3 FAILURE NORMAL CLOSED A LOCA CLOSED 1 HR B MSL/FW BREAK CLOSCD 100 DAYS C RCIC BREAK CLOSED 100 DAYS D RWCU BREAK CLOSED 100 DAYS
------- - --------- ---------0UALIFICATIOd
SUMMARY
PARAMETER -----CEMONSTRATED----- ----------------REQUIRED---------------- EVENI A EVENT B EVENT C EVENT D TEMPERATURE, DEG F 185 45-129 218 190 170
'ISSURE, INCH-H2O NONE -0.25 16.5 PSIA 15 PSIA 15 P.SIA MIDITY, %RH 100 0-90 100 100 100 DIATION, RADS 2.2E4 5.1E6 3.E5 3.E5 3.E5 OPERABILITY 1 HRS /100 DAYS N/A N/A N/A N/A OTHER:
------- - --------- ---------- CLASS 1E INTERFACES -----------------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE PdWER: 480V,ABMCC1B,CMPT120 MOTIVE POWER: N/A CONTROL P'WER: 0 FUSES CONTROL POWER: N/A SENSING SIGNAL: N/A EXECUTE SIGNAL: N/A COMMAhD SIGNAL: K2A K2B l INHIBIT SIGNAL: N/A PROCESS SIGNAL: N/A PERMISSIVE SIGWAL: r4 / A ( ***** CINCINNATI GAS & ELECTRIC PRCPRIETARY INFORMATION *****
**""-*h*em e- .m.- = . . - . . . . . . . _ _ , , , , , ,
05/09/82 CITCId t: AII GAS L.. ELECTRIC COMPANY, PAGE 365 i ID: SC-6 43 H. ZIMMER NUCLEAR POWER STATION U!.IT 1 REV A l NIUTEt1TIAL FAILURE FAILUPE ISOLATION It.TER F ACE : CONTACTS A1,B2,C3,D4 DEVICE: .N/A CAUSE: OPEN CIRCUIT BASIS: h0h-PROPAGATING FAILURE MdDE: DE-ENERGIZED FAILURE EFFECT: FAILURE LIMITED TO SLC SYSTEM; EXPLOSIVE VALVE 2 UrJAVAILABLE. POTE!TIAL FAILURE FAILURE ISOLATION INTERFACE: C0!; TAC TS A1,B2,C3,D4 DEVICE: FUSES CAUSE: SHORT CIRCUIT BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILURE M'DE': 0 ENERGIZED FAILURE EFFECT: ?iONE. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: CONTACTS A1,82,C3,D4 DEVICE: FUSES 3CAUSE: SHORT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT
~AILURE MODE: DE-ENERGIZED
, FAILURE EFFECT: SAME AS OPEN CIRCUIT. BASIS: FAILUPE DOES NOT PROPAGATE BEYOND SLC SYSTEM. ATwS NOT CONSIDERED. i
REFERENCES:
l P&ID,.FSAR FIG. 4.2-24 l E1010/PG. SC02 REY J E0 D.S. C411 l MITIGATIGH EVENT CAPABILITY A B C D ADE00 ATE N N N PJ O/ INADEQUATE
. (
-- . . . . . . -.-_ . , , , . - _ . _ _n. - - . _ . , _ - . _ _ _ . . . . _ _ , _, _ .. _
-.----e.-wy-- - . - ,--_y. , . . - - , , . , , , , , ,,4,,_,,, ,,,, , , . , _ _.
l e 05/09/82 C Ir;C It. t: ATI GAS & ELECTbIC CD1PANY PAGE 366 ID: SC-7 ah. H. ZIrdMER hUCLEAR P0nER STATIUS UNIT 1 REV A G1
}uSTIFICATION FOR IhTERIM OPERATION OF: 1C41-F 00 0 LOCATIdN':C-1 DESCRIPTION: LIMIT SWITCH SYSTEM: STANDPY LIQUID CONTROL (SC) SUBSYS:NONE SAFETY FUNCTIdNtEMERGENCY REACTOR SHUTDOWN POSITION INDICATOR MAINT. VALVE SENSING FEATURE DIV:
-------EVENT------ ,
---------DEVICE STATUS--------- ---ESTIhATED TIME---
TO FAILURE N0hhAL OPEN POSITION A LOCA OPEN POSITION NOT DETERMINED B N/A OPEN POSITION NOT DETERMINED C N/A OPEN POSITION NOT DETERMINED D h/A OPEN POSITION NOT DETERMINED
--. --- - --------- - -------QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TE?PERATURE, DEG F NONE 340 N/A N/A N/A
'SSURE, INCH-H2O N0nE 40.4 PSIG N/A N/A N/A 9MIDITY, %RH N0 t:E 100 N/A N/A N/A RADIATION. RADS NONE 9.02E8 N/A N/A N/A OPEkABILITY N/A N/A N/A N/A OTHER: N/A N/A N/A
--------- -------------------- CLASS 1E INTERFACES -----------------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: 120VAC UPS/ CUB. 1FL MOTIVE P0aER: N/A CONTROL POWER: FUSE CONTPOL P0hER: N/A SEdSING SIGNAL: VALVE PCSITION EXECUTE SIGNAL: VALVE POSITION IND
~
COMMAND SIGNAL: N/A INHIBIT SIGNAL: h/A PROCESS SIGNAL: .4 / A PERMISSIVE SIGii AL: N/A (o) ,
***** CIf;CIoNATI GAS & ELECTRIC PROPRIETARY I'IFORMATION ***** ~~~~ - ~ ~ ~ - - - - - ~ - ~
__ _ ____r _7 ~ - ~ _
~ ~
05/09/82 Cli:CINhATI GAS & ELECTRIC COMPANY PAGE 367 ID: SC-7 WA. H. ZIMAER hUCLEAR PohER STATION UNIT 1 REV A i TENTIAL FAILUPE FAILURE ISOLATION INTERFACE: CONTACTS G-H,C-D DEVICE: N/A CAUSE: OPEn CIRCUIT BASIS: NON-PROPAGATING FAILURE MdDE: OPEN CONTACTS FAILURE EFFECT: LOSS OF IMDICATION DF MAINTENANCE VALVE POSITION. POTENTIAL FAILURE tAILUBE ISOLATION INTERFACE: CONTACTS G-H,C-D DEVICE: N/AE CAUSE: HOT Sh0RT/SHORT CRCT BASIS: NON-PROPAGATIhG FAILURE IODE: CLOSED CONTACTS FAILUBE EFFECT: IMPROPER IaDICATION OF MAINTENANCE TEST TANK OUTLET VALVE POSITION. l POTE$TIAL FAILURE FAILURE ISOLATION INTERFACE: C04 TACTS G-H,C-D DEVICE: FUSE I 'T SH0hT TO GROUND BASIS: NOT SUBJECTED TO h'CAUSE: , . HARSH ENVIRONMENT TAILURE t10DE: LOSS OF CONTROL POWR FAILURE EFFECT: Ii4 PROPER / LOST INDICATION OF MAINTENANCE AND TEST TANK OUTLET VALVE POSITIONS AND SQUID VALVE BEADINESS. BASIS: FAILURE IS LIhITED TO SLC SYSTEM. ATNS NOT CONSIDERED.
REFERENCES:
P&lD, _FSAP FIG. 4.2-24 E100/PG. SC04 REV. M EQ D.S. YO23 MITIGATION EVENT CAPABILITY A B C D rw ADEOUATE U tl N N {) INADECUATE t
i t l o 05/09/92 CINCIh N ATI GAS & ELECTRIC C0i'P AhY PAGE 368 ID: SC-8 t r. . h . ZIs,ER i4UCLEAR P0wER STATION UNIT 1 REV A h hsSTIFICATION FOR It4TERIM CPERATION OF: 1C41-F031 l LOCATION': R-5A DESCRIPTION LIMIT SWITCH SYSTEM: STANDBY LIQUID CONTROL (SC) SU BSYS : tJONE SAFETY FUNCTIdN EMERGENCY REACTOR SHUTDOWN POSITION INDICATOR TEST TANK OUTLET MAN. VALVE SENSING FEATUPE DIV:
---EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL CLOSED POSITION A LOC' CLOSED POSITION NOT DETERMINED B PSL/FW BREAK CLOSED POSITION NOT DETERhINED C RCIC BPEAK CLOSED POSITIO74 NOT DETERMINED D PFCU BREAK CLOSED POSITION NOT DETERMINED
--------- --------- ---------0UALIFICATION
SUMMARY
PAPAPETEP -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATUPE, DEG F NobE 45-129 218 190 170 lSSdRE, INCH-H2O Nat4E -0.25 16.5 PSIA 15 PSIA 15 PSIA nIDITY, %FH NONE 0-90 100 100 100 ADIATION. PADS NOhE 5.1E6 3.E5 3.E5 3.E5 OPERABILITY 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--- ----- -------------------- CLASS 1E IriTEPF ACES ----------------------------- --------- - --- INPUTS --------------- -------~~-------- OUTPUTS --------------
MOTIVE PbwER: 120 VAC UPS/ CUB. 1FL MOIIVE POWER: N/A CONTROL POWER: FUSE CONTPOL POWER: N/A SENSIriG SIGN AL: VALVE POSITION EXECUTE SIGNAL: VALVE POSITION IND ! COMMAND SIGhAL: N/A INHIdIT SIGi4AL: N/A PROCESS SIGNAL: N/A PERNISSIVE SIGNAL: fi/A n () ***** ClaCINNATI GAS & ELECTRIC PROPPIETARY INFORMATI0te *****
05/09/62 ..CI.JCI *.411 gad & ELECTRIC CD:4P ANY PAGE 369 Ius SC-9 M. H. ZIanER HUCLEAR P0eER SIATIOn UNIT 1 REV A lTE:fTIAL FAILUPE FAILUPE ISOLATION IhTERFACE: C0JTACTS F-E,H-G,F-E DEVICE: N/A CAUSE: OPEh CIRCUIT BASIS: NON-PROPAGATING FAILURE HbDE: OPEN CONTACTS FAILURE EFFECT: IMPROPER INDICATION OF TEST TANK OUTLET VALVE POSITION, POTE!.TIAL FAILUBE FAILURE ISOLATION INTERFACE: CONTACTS F-E,H-G,F-E DEVICE: N/AE CAUSE: HOT SHORT/SHORT CRCT BASIS: NON-PROPAGATING FAILUFE HbOE: CLOSED CONTACTS - FAILURE EFFECT: IMPPOPER IUDICATION OF TEST TANK OUTLET VALVE POSITIONS AND SQUID VALVE PEADINESS. POTEhTIAL FAILURE FAILURE ISOLATION INTERFACE: CONTACTS F-E,H-G,F-E DEVICE: FUSE
CAUSE: SHORT TO GROUND BASIS: HOT SUBJECTED TO H ARSH EN VIRON'4ENT ILURE 4dDE: LOSS OF C0dTROL POWB FAILUPE EFFECT: IMPROPER / LOST INDICATI0!4 0F MAINTENANCE AND TEST TAf4K OUTLET VALVE POSITIONS AND SQUID VALVE READ-ISESS.
BASIS: FAILUPE IS LIMITED BY SLC SYSTEM. AT4S NOT CONSIDERED. l i REFEEENCES: ! P&IO, FSAR FIG. 4.2-24 l E1010/PG. SC04 REV. i4 DC l'ITIG ATIO N EVEhT CAPAPILITY A B C D
, ADECUATE N ii N N
) li, AD E Q U A TE A.
EX. DATA SHEET: E004 fs . JUSTIFICATION FOR EXEMPTING EQUIPMENT
\ . .. FROM ENVIRONMENTAL QUALIFICATION REQUIREMENTS PR, Process Radiation SYSTEM.
EQUIPMENT TAG NUMBERS: 1D13-N003A/D 1D13-N019A/D MANUFACTURER: General Electric-HODEL NUMBER: 237X731; 194X927 POWER: 3 ' ESSENTIAL POWER C NON-ESSENTIAL POWER C ESSENTIAL POWER, NON-ESSENTIAL CABLE JUSTIFICATION: 'The Process Radiation Monitoring System is not required to support any of the required safety functions during a LOCA or HELB event. An analysis was done as part.of our JIO that determined that no failure mode exists that could propagate electrically to disable any other safety system. A PR-1,2,3,4,5,6 FAILURE MODEL EFFECTS ANALYSIS (ATTACHED): ~ % -) PREPARED BY: - 8 /rV P DATE: ~~j - / '2 -p 1
05/09/02 CINCINNATI GAS &-ELECTRIC COMPANY PAGE 47 ID: PR-1 WH. H. ZIMNER NUCLEAR POWER STATION UNIT 1' REV A b d . JUSTIFICATION FOR IDTERIM OPERATION OF: 1013-N003A,C LOCATION:R-8 DESCRIPTIdN: RADIATION DETECTOR SYSTEM: PROCESS RADIATION MOMITORING (PR) SUBSYS:MAIMSTM RAD MONITOR. SAFETY FUNCTION:EMERG RX SHUTDOWN / CONT ISOL (ERS/CI&IC) SCRAM & CLOSE MSIV'S ON HIGH RAD l SENSING FEATURE DIV:RPS-A
-EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL - SENSING A LOCA SENSING NOT DETERMINED B MSL/FW BREAK SEhSING NOT DETERMINED C RCIC BREAK SENSING NOT DETERMINED D BWCU BREAK SENSING NOT DETERMINED
------- - --------- ----~~---QUALIFICATION SUAMAPY-----~~----------------------
PARAMETER -----DEMONSIRATED----- ----------------REQUIRED---------------- EVENT A EVENT 8 EVENT C EVENT D , TEMPERATURE, DEG F 410 45-152 290 65-122 65-122 TSSUPE. INCH-H2O 184 PSIG -0.25 28.8 PSIA .16TO .25 .16TO .25 (^m'dlIDITY, %RH AONE 0-90 100 0-60 0-60 RADIATION, RADS MR/HR 2.79E4 6.32E6 1.71E6 1.71ES 1.71E6 OPERABILITY 200 HOUPS 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
------- - --------- - -------- CLASS 1E INTERFACES ----------------------------- ------- - - --- INPUTS --------------- -----~~~~-------- GUTPUTS --------------
l MOTIVE POWER: FOTIVE POWER: _ CONTROL POWEP': K610A (C) CONTROL POWEP: SENSING SIGNAL: MAIN STM LINE RAD EXECUTE SIGNAL: COMMAND SIGNAL: i INHIBIT SIGNAL: PROCESS SIGNAL: K610A (C) j PERMISSIVE SIGNAL:
/^(
* * * *
- C I N C I t ' P:ATI GAS & ELECTRIC PROPPIETARY I!FOPwATIOP: *****
l
)
05/09/92 CINCINtlATI GAS & ELECTRIC COMPANY PAGE 48
- PR-1 WM. H. ZIMt!ER NUCLEAR POWER STATION UNIT 1 REV A
)
POTEHTIAL FAILUPE FAILURE ISOLATIO!! INTEPFACE: CONNECTIONS HV-C DEVICE: N/A CAUSE: GPEN CIRCUIT BASIS: t:0:1-PROPAGATING TYPE FAILURE FAILURE 90DE: FAILS OPEN FAILURE EFFECT: INITIATES HALF SCRAM. POTENTIAL FAILURE FAILURE ISOLATI0tl ItiTERF ACE : C0t4.NECTIONS HV-C DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILURE .M'DE': 0 SHORT TO GROUtiD FAILURE EFFECT': INITIATES HALF SCRAM. BASIS: LOCA & HELB: DEVICE IS NOT REQUIFED TO HITIGATE THESE EVEtaTS AND (N FAILURE DOES NOT PROPAGATE. L:0
REFERENCES:
E1010/PG PP01 AND PRio EQ 0.S. D132 NITIGATICN EVENT CAPABILITY A B C D ADEOUATE X X X X Iri ADEQU ATE w
05/09/S2 CINCINNATI GAS ~& ELECTRIC COMPANY PAGE 49 8 PR-2 WN. H. ZIMMER NUCLEAR POWER STATIdN UNIT 1 REV A N
\) . .
JUSTIFICATION FOR IhTERIM OPERATION OF: 1D13-N003B,D L CATION'R-8 : DESCRIPTIbN: RADIATION DETECTOR SYSTEH: 5ROCESS RADIATION MONITORING (PR) SUBSYS:MAINSTM LINE RAD MON SAFETY FUNCTION:EAERG RX SHUTDOWN /C NT ISOL (ERS/CI&IC] SCRAM & CLOSE HSIV'S ON HIGH RAD SENSING FEATURE DIV:RPS-4
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL SENSING - A LOCA SENSING NOT DETERMINED B MSL/FW BREAK SENSING NOT DETERMINED C BCIC BREAK SENSING NOT DETERMINED 0 RWCU BREAK SENSING NOT DETERMINED
. --QUALIFICATION
SUMMARY
~~-----
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D MPERATURE, DEG F 410 45-152 290 65-122 65-122 JSSURE, INCH-H2O 184 -0.25 28.8 PSIA .16TO .25 .16TO .25 uMIDIfY, %RH NONE 0-90 100 0-60 0-60 RADIATION. BADS MR/HR 2.79E4 6.32E6 1.71E6 1.71ES 1.71E6 OPEPABILITY 200 HRS 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
------- - --------- ---------- CLASS 1E INTERFACES ----------------------------- ------- ,- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWEB: MOTIVE POWER: CONTROL 5bWER: K610BCD) CONTROL POWER: SENSING SIGNAL: MAIN STM LINE RAD
=
1 l EXECUTE SIGNAL: 1 COFWAND SIGNAL': IN;lIBIT SIGNAL: PROCESS SIGNAL: K6108 (D) PERMISSIVE SIGNAL: , [~) .
* * * *
- C i r. C I r:NATI GAS,& ELECTRIC PRCPRIETAPY IN FC R.x ATION *****
_ . _ _ _ . . _ _ . _ _ _ . . . _ V,y _ _ _ .. _ _ _ _ _ . _ _ . . . . . . - _ _ _ . _ _ . -
~
) L 't -
05/09/92 C1NCINNATI' GAS &^ ELECTRIC COMPANY PAGE 50
- PR-2 WM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A s
,J POTENTIAL FAILURE FAILUBE ISCLATION If!TERTACE: C0dNECTIO:43 HV-C DEVICE: to/A CAUSE: OPEN CIRCUIT s, BASIS: MON-PROPAGATING TYPE FAILURE FAILURE M'0E: 0 FAILS OPEN ,
FAILURE EFFECT: INITIATES HhLF SCRAM POTENTIAL FAILURE FAILURE ISOLATION IriTERFACE: CONNECTIONS HV-C DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: TiOT SUBJECT TO HARSH ENVIRONMENT FAILURE MODE: SHORT TO. GROUND FAILURE EFFECTi INITIATES HALF SCRAM 1 , . BASIS: LOCA & HELBi DEVICE IS NOT REQUIRED TO SITIGATE THESE EVENTS A40 g) v_FAILURE DOES tJOT PROPAGATE.
REFERENCES:
E1010/PG. PRO 1 AND PRio EQ D.S. D132 - MITIGATION EVENT CAPABILITY A B C D l I ADEOUATE X X X X INADEQUATE N 0., , a e O
i l 05/09/92 CINCINNATI GAS & ELECTRIC COMPANY PAGE Si 2 PR-3 wM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 PEV A bu'STIFICATION FOR INTERIM OPERATION OF 1013-3019A LOCATION'R-6A : DESCRIPTION 0ETECTOR SYSTEM: PROCESS RADIATION MONITORING (PR) SUBSYS:N0bE SAFETY FUNCTION CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) INTRLK TO STBY GAS SYS A PURGE & VENT VALVES OTBRD SENSING FEATURE DIV:RPS-A
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILUPE NORMAL NORMAL QUTPUT A LOCA , INCREASED OUTPUT NOT DETERMINED B MSL/FW BREAK NORMAL QUTPUT NOT DETERMINED C RCIC BREAK NORMAL QUTPUT NOT DETERMINED D RcCU BREAK NORMAL OUTPUT NOT DETERMINED
---- ,---- --------- - -------QUALIFICATION
SUMMARY
=--
PARAPETER -----DEMONSTRATED----- ==--------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D PERATURE, DEG F 212 45-129 170 . 170 172 SSURE. INCH-820 NONE -0,25 15 PSIA 15 PSIA 15.1. PSIA IDITY. %RH NONE 0-90 100 100 100 RADIATION. RADS NONE 4.65E0 2.98E2 2.98E2 2.98E2 OPERABILITY 6 HPS 100 DAYS 1 DAY 1 DAY 1 DAY OTHER: 575VDC +
--------- --------- ---------- CLASS 1E INTERFACES -----------------------------
----- --- ----- INPUTS --------------- ==--------------- OUTPUTS --------------
HOTIVE POWER: 24VDC +(-), COMMON MOTIVE PO'4ER: 575 VDC+ CONIROL 50wER: CONTROL POWER: SENSING SIGNAL: FUEL POOL VENT PLENUM RADIATI0tl EXECUTE SIGNAL: COMMAND SIGNAL: INHIBIT SIGNAL: PROCESS SIGl.AL: + SIGNAL PERMISSIVE SIGNAL: I h
***** CI9CIdNATI GAS & ELECTRIC PbOPRIETARY INFORMATION *****
~
) T 05/09/02 . CINCINNATI GAS & ELECTRIC COMPANY PAGE 52 ID: PR-3 Wh. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A
()PO'IENTIAL FAILURE FAILURE ISOLATION INTERFACE: 24VDC + DEVICE: h/A CAUSE: OPEN CIRCUIT BASIS: a0N-PROPAGATIc!G TYPE FAILURE FAILURE MbDE: FAILS OPEN FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 24VDC - DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE .
, . . FAILURE FAILURE MODE: FAILS OPEN FAILURE EFFECT: DOWhSCALE TRIP CAU4ING AN ALARM, WHEN A SECbND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN , ,
ISOLATION FUNCTION HILL BE PERFORMED. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 575VDC + DEVICE: N/A (- }' CAUSEi OPEN CIRCUIT BASIS: NO:1-PROPAGATING TYPE . FAILURE FAILUHE MdDE: FAILS OPEN FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, UHEh A SECOND CHANNEL ALSO HAS A DOWFSCALE TRIP, THE DESIGN ISOLATION FUNCTION DILL BE PERFOPMED. POTENTIAL FAILUPE FAILURE ISOLATION INTERFACE: COMMON DEVICE:.N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE MbDEi FAILS OPEN FAILURE EFFECT: 00hNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL RE PERFORMED. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: SIGNAL + DEVICE: N/A CAUSEi OPEN CIRCUIT BASIS NON-PROPAGATING TYPE FAILURE FAILURE vbOE FAILS OPEN hl(LUREEFFECT: D0dhSCALE TRIP CAIISING AN alt.PM, 4 HEP: A SECO:4D CMANMEL ALSO HAS A 004" SCALE TRIP, T'iE DESIGN ISOLATI0a FUNCTION WILL 86 PEFFORSED.
.05/09/02 CIllCINNATI GAS & ELECTRIC COMPANY PAGE 53 !
D PR=3 WM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A
')
POTENIIAL FAILURE FAILURE ISOLATION I INTERFACE: 24VDC +. DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUhD SASIS: NOT SUBJECT TO HARSH ENVIRON:4ENT FAILURE F0DE: SHORT TO GROUND FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A 004NSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 24VDC . DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILURE MbDE's SHORT TO GROUND FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARt4, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ' *
-ISOLATION FUNCTION WILL BE PERFORMED.
POTENTIAL FAILURE , FAILURE ISOLATION s INTERFACE: 575VDC + CEVICE: SUPPLY FUSE
/ CAUSE' SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILURE MdDE: SHORT TO GROUND .
FAILURE EFFECT: 00eNSCALE TRIP CAUSING AN ALARM, 4 HEN A SECCND~ CHAT 4NEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL SE PERFORMED. , POTENTIAL FAILURE , FAILURE ISOLATION INTERTACE: SIGNAL + OEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILURE iODE': SHORT TO GROUND FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN AL AR *4, WHEN A SECCND CHANNEL ALSO HAS A D04NSOALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. 4 I (b
k )
, 05/09/82 ,
CINCINNATI-GAS &" ELECTRIC COMPANY PAGE' ~5 4
. ID PR-3 hM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 Ih :
s
) SIS ,
hEV A
-3 ASIS: THE DEVICE IS DESIGNED TO MONITOR REACTIVITY ACCIDENTS IN THE FUEL PdOL AREA.
HELS, LOCa: THIS DEVICE IS NOT REQUIRED TO MITIGATE.THESE EVENTS AND ANY FAILURE ' VILL NOT PROPAGATE.
REFERENCES:
E1010/PG RP05, 06 ZIMMER FSAR TABLE 11.4 1 EQ D.S. 0131
, MITEGATIDN EVENT CAPABILITY A B C D
, ADEOUATE X X X X INADEQUATE ' ' e
\L) w 9
PAGE 55 05/09/82 CINCIN9ATI GAS & ELECTRIC CbMPANY - A REV
- PR-4 WM. H. ZIM.*ER NUCLEAR POWER STATION UNIT 1 ,
JUSTIFICATION FOR Ir=TERIM OPERATIO!! 0F: 1013-h0198 LOCATIOu:R-6A DESCRIPTIO4: DETECTOR SYSTEM: PROCESS RADIATION .MOhITORING (PR) SUBSYS NONE SAFETY FUNCTION: CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) INTRLK TO STBY GAS SYS B PURGE & VENT VALVES OTBRD SENSING FEATURE DIV:RPS-8
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL NORMAL OUTPUT INCREASED OUTPUT NOT DETERMINED A LOCA NOT DETERMINED B MSL/F'.i BRE AK NORMAL OUTPUT NORMAL OUTPUI NOT DETERMINED C PCIC BREAK NOT DETERMINED D RhCU P9EAK NORMAL QUTPUT
--------- ----- ----- -------QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED-~~-- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D MPERATURE, DEG F 212 45-129 170 170 172 NONE -0.25 15 PSIA- 15 PSIA 15.1 PSIA
}SSURE, INCH-d20 100 100 aIDITY, %RH NONE 0-90 100 RADIATION, RADS NonE 4.65E8 2.98E2 2.98E2 2.90E2 100 DAYS 1 DAY 1 DAY 1 DAY OPERABILITY 6 HRS OTHER:
--- ----- -------------------- CLASS 1E It4TERFACES -----------------------------
--- --- ,- ----- INPUTS --------------- ----------------- QUTPUTS --------------
24VDC +(-), COMMON MOTIVE POWEx: 575 VOC+ MOTIVE POWER: CONTROL PbWER: 24VDC +(-) COMMON CONTPOL POWER: ! SENSING SIGNAL: FUEL POOL VENT PLE!!UM PADIATION l EXECUTE SIGNAL: i COMMAND SIGNAL: i l INHIBIT SIGNAL: + SIGNAL l PROCESS SIGNAL: l PERMISSIVE SIGNAL: n ! i h
' ******CIaCINNATI GAS & ELECTRIC PROPPIETARY I!; FORMATION *****
i ') 05/09/82 CINCINNATI GAS & ELECTRIC COMPAtlY PAGE 56 D: PR-4 NM. H. ZI$1ER NUCLEAR POWER STATION UNIT 1 REV A T J POTENTIAL FAILURE FAILUPC ISOLATION INTEPFACE: 24VDC.+ DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE PODE: FAILS OPEN FAILURE EFFECT: D0hhSCALE TRIP CAUSING AR ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. POTEtiTIAL FAILUPE FAILURE ISOLATION INTERFACE: 2dVOC - DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: h0N-PROPAGATING TYPE FAILUPE FAILURE MbDE: FAILS OPEN FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, WHEN A SEC ND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN . . ISOLATION FUNCTION WILL BE PERFORMED. POTENTIAL FAILU9E FAILUPE ISOLATION 7 INTERFACE: 575VDC + DEVICE: N/A ( P CAUSE: OPEN CIRCUIT BASIS: .NON-PROPAGATING TYPE FAILURE FAILURE MODE: FAILS OPEN , FAILURE EFFECT: 00hNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTIO!I WILL BE PERFORNED. POTENTIAL FAILUPE FAILURE ISOLATION IllTERF ACE: C O M.VO N DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE . MODE: FAILS OPEN FAILURE EFFECT: 00WNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHAhNEL ALSO HAS A D0ddSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFCRMED. POTEt1TIAL FAILURE FAILURE ISOLATION INTERFACE: SIGNAL'+ DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE v0DE': FAILS OPEN (,wlILLRE EFFECT: 00HASCALE TRIP CAUSING AN ALARM, WHEN A SECOND ChAU!IEL ALSO HAS A DOdSSCALE TPIP, TFE DESIGN ISOLAIIUN FurtCT!0N AILL BE PERFUPMED.
- 05/09/82 CIUCINNATI GAS & ELECTRIC COMPANY PAGE 57 D PR-4 WM. H. ZIMMER NUCLEAR P0hER STATION UNIT 1 REV A
) .
POTENTIAL FAILUPE FAILURE ISOLATION INTERFACE's 24VDC + OEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HAPSH ENVIRONMENT FAILURE MODE: SHORT TO GR00reO FAILURE EFFECT: DO*hSCALE TRIP CAUSING AN ALARM, nHE4 A SECOND CHANNEL ALSO HAS A DOW4 SCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. POTEllTIAL FAILURE . FAILURE ISOLATION INTERFACE: 24VDC - DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO ' HARSH ENVIRONMENT FAILUHE M'DE: 0 SHORT TO GROUND FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWhSCALE TRIP, THE DESIGN , . ISOLATION FUNCTION WILL BE PERFOPMED. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 575VDC + DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO
't HARSH ENVIR0hMENT FAILUBE MODE: SHORT T0 GROUND FAILURE EFFECT: D0'rNSC ALE TRIP CAUSING AN ALARM, WHE'I A SECO*lD CdANNEL ALSO HAS A D0'nNSCALE TRIP, THE DESIGN ISCLATION FUNCTION WILL BE PERFORMED.
POTENTIAL FAILURE FAILURE ISOLATION IhTERFACE: SIGNAL + DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HAPSH ENVIRONMENT FAILURE M'DE': 0 SHORT TO GROUND l FAILURE EFFECT: 00WhSCALE TRIP CAUSING All ALARM, aHEN A SECOND CHAR.NEL ALSO HAS A DOANSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. O l l
I h 05/09/92 CINCI:lWATI GAS & ELECTRIC COMPANY PAGE 59 ID PR 4 '4 M . H. ZIM!1ER NUCLEAR POWER STATION UNIT 1 REV A t SIS: B AS IS ': THE DEVICE IS DESIG !ED TO MONITOR REACTIVITY ACCIDENTS IN FUEL FOOL AREA. HELA, LOCA: THIS DEVICE IS IdOT REQUIRED TO 4ITIGATE TH':SE r EVENTS AND A?!Y FAILURE WILL NOT PROPAGATE.
REFERENCES:
E101/PG. RPOS, 06 ZIMt1ER.FSAR TABLE 11.4 1 EQ D.S. D131 MITIGATIdN EVENT CAPABILITY A B C D ADEOUATE X X X X INADEQUATE , , d 9 9 0:
= . _ . ._ . .
-- . = .. .. -
05/09/92 CINCIhNATI GAS & ELECTRIC COMPANY PAGE 59 l ID: PR-5 WM. H. 4I:4.MER NUCLEAR POWER STATION UNIT 1 REV A O, JUSTIFICATION FOR INTERIM OPERATION OF: 1D13-N019C
^
LOCATION:n-6A DESCRIPTION: DETECTOR SYSTEM: PROCESS RADIATION MONITORING (PR) SUBSYS:NONE SAFETY FUNCTION' : CONT. ISOL. & INTEGRITY CflTRL. (CI&IC) INTRLK TO ST8Y GAS SYS B PURGE & VENT VALVES INBRD SENSIFG FEATURE DIV:RPS-A
==---
-EVENT------- ==-------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE fiORMAL NORMAL OUTPUT A LOCA INCREASED OUTPUT NOT DETERMINED B MSL/FW BREAK NORMAL QUTPUT NOT DETERMINED C PCIC BPEAK h0RMAL OUTPUT NOT DETERMINED D RNCU BPEAK h0RNAL OUTPUT NOT DETERMINED
------- - ----------- -------0UALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F 212 45-129 170 170 112
'5S S UB E , IliC H-H 2 O NONE -0.25 15 PSIA- 15 PSIA 15.1. PSIA
("djIDITY,
\c %PH NONE 0-90 100 .100 .100 RADIATION, RADS NONE 4.65E8 2.98E2 2.90E2 2.99E2 OPERABILITY 6 HRS .
100 DAYS 1 DAY 1 DAY 1 DAY OTHEd:
--------- - ------- ---------- CLASS 1E ItTERFACES --------------=-------------- ----- - - - --- It. PUTS --------------- ----------------- OUTPUTS ==------------
- MOTIVE power: 24VDC +(-), COMMON MOTIVE POWER: 575 VDC+
1 l CONTROL P0hER: 24VDC +(-) COMMON CONTROL POWER: SENSING SIGhAL: FUEL POOL VENT PLENUM RADIATION . EXECUTE SIGNAL: COMMAND SIGNAL: INHIBIT SIGNAL: PROCESS SIGNAL: + SIGNAL PERMISSIVE SIGNAL: i [/'))
' ***** CINCINNATI GAS & ELECTRIC PRCPBIETARY INFORMATION * **** ,
, - - ~ . , .. r - ,,-e ,e-- . + - - - <m - - - ---e-
) !
05/09/02 CINCINNATI GAS & ELECTRIC COMPANY PAGE 60
- PR-5 WM. H. ZIM:AER NUCLEAR POWER STATION UNIT 1 REV A POTENTIAL FAILUPE FAILURE ISOLATION IhTERFACE: 24VDC + DEVICE: N/A .
CAUSE: OPEt; CIBCUIT SASIS: SON-PROPAGATING TYPE FAILURE FAILURE MhDE: FAILS OPEN FAILURE EFFECT: D0ntiSC ALE TRIP CAUSItJG AN ALARM, WHEN A SECOND CHAhNEL ALSO FAS A DOWNSCALE TRIP, DESIGN ISOLATION FUtaCTIONWILL BE PERFORMED. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 24VDC - DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE MbDE: ? AILS OPEN FAILURE EFFECT: SAME AS 24VDC +. POTENTIAL FAILUPE FAILURE ISOLATION INTEPFACE: 575VDC + DEVICE: N/A OPEN CIRCUIT SASIS: NON-PROP AGATIi4G TYPE
)CAUSE: FAILURE FAILURE MdOE: FAILS OPEN FAILURE EFFECT: SAf!E AS 24VDC t.
i POTENTIAL FAILUPE FAILURE ISOLATION INTERFACE: COMMON DEVICE: N/A CAUSE: OPES CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE l FAILURE MODE: FAILS OPEN 1 FAILURE EFFECT: SAME AS 24VDC t. l l POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: SIGNAL + DEVICE: N/A CAUSE': OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILUPE FAILdRE MhDE: FAILS OPEN ILURE EFFECT: SAME AS 24VOC +. l
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- . - - - - . . . - . - - ..-~ - -- -
05/09/82 , CISCINNATI GAS & ELECTRIC. COMPANY PAGE- 61
'ID: PR-5 hM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 24VDCt DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUNO BASIS: NOT SUBJECT TO HARSH ENVIRONMENI FAILURE 800E: SHORT TO GROUND FAILUBE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED.
POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 24VDC = . DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILUBE MbDE: SHORT TO GROUND FAILURE EFFECTi SAME AS 24VDC +. POTENTIAL FAILURE FAILDRE ISOLATION
-INTERFACE: 575VDC + DEVICE: SUPPLY FUSE SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH f]/CAUSE': \r ENVIRONMENT FAILURE MbDE: SHORT TO GROUND FAILURE EFFECT': SAPE AS 24VDC +.
POTENTIAL FAILUBE FAILURE ISOLATION INTERFACE: SIGNAL + DEVICE: SUPPLY FUSE CAUSE: SFORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONME:iT FAILURE MdDE: SH0HT TO GROUND FAILUPE EFFECT: SAME AS 24VDC +. l l
) I 05/09/82 .
CINCINNATI GAS & ELECTRIC COMPANY PAGE 62 ID PR-5 WM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A~ n
'\g!)IS:
HELS: SiOT REOUIRED TO MITIGATE THIS EVENT. LOCA: DEMONSTRATED TEMP. IS IN EXCESS OF REQUIREv.ENT. RADIATIO:4 TEST DATA IS NOT AVAILABLE, HOWEVER, THE DEVICE IS DESIGriED TO DETECT RADIATION. SHOULD ANY ONE CHAivNEL F AIL, AN ALARt1 WILL SOUND. IF A SECOND SIMILAR CHAN!iEL FAILS THE DESIGN ISOLATION FUNCTIOti wILL BE PERFOR/ED AUTOMATICALLY.
REFERENCES:
E1010/PC. RP05, 06 ZIf1MER FSAR TABLE 11.4=1 EQ 3.S. D131
~
MITIGATION EVENT CAPABILITY A B C D ADEOUATE X X X X INADEQUATE . . O O l . 1 I () l
05/09/d2 CINCINNATI-GAS & ELECTRIC COMPANY PAGE 63 ID: PR-6 WM. H. ZIMMER NUCLEAR POWER STATION UMIT 1 REV A i D USTIFIC ATION FOR INTERIM GPEPATION OF: 1013-N019D LOCAfIO4 R-6A DESCRIPTION:0ETECTOR SYSTEM: PROCESS RADIATION MONITORING (PR) SUBSYS:NONE SAFETY FUNCTION: CONT. ISOL. & INTEGRITY CNTDL. (CI&IC) INTRLK TO STBY GAS SYS B PURGE & VENT VALVES INBRD SENSING FEATURE DIV:RPS-B
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE h0RMAL NORMAL OUTPUT A LOCA INCREASED OUTPUT NOT DETERMINED 8 PSL/FW BREAK NORMAL QUTPUT NOT DETERMINED C RCIC BREAK NORMAL QUTPUT NOT DETERMINED D RcCU BREAK 90R*AL QUTPUT NOT DETERMINED
----- --- -------------------QUALIFICAIION
SUMMARY
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- _ EVENT A EVENT S EVE.vT C EVENT D TE"PERATURE, DEG F 212 45-129 170 170 172
'SSURE. INCH-H2O NONE -0.25 15 PSIA. 15 PSIA 15.1 PSIA MIDITY, %RH NONE 0 90 100 100 100 ADIATION. RADS NONE 4.65E8 2.96E2 2.90E2 2.98E2 OPERABILITY 6 HRS 100 DAYS 1 DAY 1 DAY 1 DAY OTHER: ------- - - ------- ~~~--~~--- CLASS 1E INTERFACES ----------------------------- --------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: 24VDC +(-), COMMON MOTIVE POWER: 575 VDC+ CONTPOL PdWER: 24VDC t(-) COMMON CONTROL POWER: SENSING SIGNAL: FUEL POOL VEbT PLENUM RADIATION
. EXECUTE SIGNAL:
COMMAND SIGNAL: INHIBIT SIGNAL: PROCESS SIGNAL: + SIGNAL PERMISSIVE SIGNAL:
/'T b). ***** CI4CIPINATI GAS & ELECTRIC PROPRIETARY INFORMATION *****
) I ,05/09/02 CINCINNATI. GAS & ELECTRIC COMPANY PAGE 64 10: PR-6 -
WM. H. ZIMMER NUCLEAR P0:1ER STATION UNIT 1 REV A
)
WIZfif1 AL FAILURE FAILURE ISOLATION INTERFACE: 24VDC + DEVICE: N/A CAUSE: OPE 3 CIPCUIT BASIS: N0ti-PROP AGATING TYPE FAILURE FAILURE MUDE: FAILS OPEN FAILURE EFFECT: DOWNSCALE TRIP CAUSING AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISCLATION FUNCTION AILL BE PERFORMED. POTENTIAL FAILURE FAILURE ISOLATION INTERTACE: 24VDC - DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: WON-PROPAGATING TYPE FAILURE
~
FAILURE MbDE: FAILS OPEN s FAILURE EFFECT: SAME AS 24VDC +. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: 575VDC + DEVICE: N/A OPE:4 CIRCUIT BASIS: h0N-PROPAGATING TYPE (^j}CAUSE: FAILURE i/ m FAILURE MdOE: FAILS OPEN FAILURE EFFECT: SAME AS 24VDC +. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: COMMON DEVICE: N/A CAUSE': OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE PUDE': FAILS OPEN FAILUR.E EFFECT: SAME AS 24VDC t. POTENTIAL FAILURE FAILURE ISOLATIO'N I!!TERF ACE: SIGNAL + DEVICE: N/A CAUSE: OPEN CIRCUIT SASIS: NON-PROPAGATING TYPE FAILURE FAILURE MODE: FAILS OPEN (^S; Luke EFFECT: SAME AS 24VDC +. l \af l
05/09/82 CI.NCINNATI GAS & ELECTRIC C0\lPANY PAGE 65 ID: PR-6 FM. H. ZIMMER NUCLEAR PuhER STATION UNIT 1 REV A IENTIAL FAILURE FAILURE ISOLATIdN INTERFACE: 24VDC + DEVICE: SUPPLY FUSE CAbSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HAPSH ENVIRONMENT FAILURE MODE: SHORT TO GROUND FAILUBE EFFECT: DOWHSCALE TRIP CAUSIbG AN ALARM, WHEN A SECOND CHANNEL ALSO HAS A DOWNSCALE TRIP, THE DESIGN ISOLATION FUNCTION WILL BE PERFORMED. POTENTIAL FAILURE FAILUBE ISOLATION INTEPFACE: 24VDC - DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUND BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILURE MODE: SHORT TO GROUND FAILURE EFFECT: SAME AS 24VDC +. POTESTIAL FAILURE FAILURE ISOLATION I4TERFACE: 575VDC + DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROU;40 BASIS: NOT SUBJECT TO HARSH EUVIRONMENT AILURE MdDE: SHORT TO GROUND FAILURE EFFECT: SAME AS 24VDC +. POTEhTIAL FAILURE FAILURE ISOLATION INTERFACE: SIGNAL + DEVICE: SUPPLY FUSE CAUSE: SHORT TO GROUJD BASIS: NOT SUBJECT TO HARSH ENVIRONMENT FAILORE MdDE: SHORT TO GROUND FAILUR.E EFFECT: SAME AS 24V,0C +. llI .
we
)
05/09/82 . CINCINNATI GAS.& ELECTRIC CO'1PANY PAGE 66 ID: PR.6. WM. H. ZIMt1ER NUCLEAR POWER STATION UNIT 1 REV A
/IS:
DASIS': THE DEVICE IS DESIGilED 70 adf4ITOR REACTIVITY ACCIDENTS Ih THE.FilEL FOOL AREA. HELB, LOCA: T915 DEVICE IS NOT ACQUIRED T MITIGATE THESE EVENIS AND A.it FAILURE NILL NOT PROPAGATE.
REFERENCES:
E1010/pG. RP05, 06 ZIRMER FSAR TABLE 11.4 1 EQ D.S. D131 MITIGATI N EVENT CAPABILITY A , 8 C D ADEOUATE X X X X INADEQUATE l l I r%'
EX DATA SHEET: E005 JUSTIFICATION FOR EXEMPTING EQUIPMENT y FROM ENVIRONMENTAL OUALIFICATION REQUIRE"ENTS . SYSTEM: HP.LP,RH.RI EQUIPMENT TAG NUMBERS: Limit switches and solenoid valve for testable feature on the , following valves: 1E22-F005,1E21-F006,1E12-F041 A/C, IE12-F050 A/B, 1E51-F066 MANUFACTURER: Namco; Asco MODEL NUMBER: EA 74010000; WPHTX 834472
~
POWER: b ESSENTIAL POWER C NON-ESSENTIAL POWER ESSENTIAL POWER' NON-ESSENTIAL CABLE JUSTIFICATION: The above referenced pilot solenoid valves and limit switches provide no safety function to mitigate the postulated HELB and LOCA conditions. They are however powered from an essential power division. Review of the circuit shows that failure of these devices will'not affect plant safety. - 1 FAILURE MODEL EFFECTS ANALYSIS (ATTACHED): JIO to include r$' PREPARED BY: //. M - ,1
\"-J' DATE: 7 - / t
.r"?-
*****wN**~W*a-e y ew w +-m em.- =ce- emee =ms. **m-e- e ' * - * * + - = * * = - - * *-****-a * * * ' ~ * - * - -
05/09/A2 CINCIm,ATI GAS & ELECIRIC COMPANY PAGE 185 ID: HP-5 ^M. H. ZINSEP f.UCLEAH P0 HEM STATION UNIT 1 REV A
.dTIFICATION FOR Il#TERIM OPERATION OF: 1E22-F005 LOCATION'C-1 DESCRIPTION:LINIT SWITCH SYSTEM: HIGH PRESSURE CORE SPRAY CHP) SUBSYS NONE SAFETY FUNCTI'N: O REACTOR CORE COOLING (RCC)
POSITION SWITCH FOR TESTABLE CHECK VALVE SEFSING FEATURE DIV:III
-------EVENT------- *
---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL CONTACTS OPEN/ VALVE CLOSED A LOCA CONTACTS CLOSED / VALVE OPEN NOT DETERMINED B N/A N/A N/A C N/A N/A N/A D N/A N/A N/A
------- - --------- ---------QUALIFICATION
SUMMARY
PAHAMETER -----DEMONSTRATED----- ===-------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F NONE 340 N/A N/A N/A SSURE. INCH-H2O NONE 40.4 PSIG N/A N/A N/A IIDITY. %RF NONE 100 N/A N/A N/A nDIATION, RADS NONE 9.02E8 N/A N/A h/A OPERABILITY NOhE 100 DAYS N/A N/A N/A OTHER: N/A N/A N/A
------- ;;----------- -------- CLASS 1E INTERFACES ----------------------------- ----- --- ----- INPUTS --------------- ----------------- OUTPUTS --------------
[ HOTIVE POWER: N/A MOTIVE POWER: N/A 1 l CONTROL POWER: FUSE, 1H13-P601 . CONTROL POWER: K20 SENSING SIGt.AL: DISK POSITION EXECUTE SIGNAL: N/A 1 COMMAND SIGNAL; N/A INHIBIT SIGNAL: h/A PRCCESS SIGNAL: N/A PERMISSIVE SIGNAL: N/A
05/09/92 Cr.Cla.ATI GAS & ELECTRIC CO'1PANY PAGE 1P6 ID: nF-5 'a " . n.'Z1*MER NUCLEAR PO'ER
- STATION UNIT 1 REV A ENTIAL FAILURE FAILURE ISOLATION INTERFACE: MAGNETIC SWITCH DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE MODE: O P E!* CONTACTS FAILURE EFFECT: IMPROPER / LOST INDICATION OF DISK POSITION.
POTENTIAL FAILURE FAILURE Is0LATION IhTERFACE: MAGNETIC SWITCH DEVICE: N/A CAUSE': SHORT CIRCUII BASIS: NON-PROPAGATING FAILURE MGDE: CLOSED CONTACTS FAILUBE EFFECT: IMPROPER / LOST INDICATION OF DISK POSITION, POTEaTIAL FAILURE FAILURE ISOLATION INTERFACE: MAGNETIC SWITCH DEVICE: FUSE
]CAUSE: SHORT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT AILURE PODE: LOSS OF COHTROL POWR FAILUPE EFFECT: LOST INDICATION OF DISK AND ACTUATOR POSITIONS.
BASIS: CHECK VALVE 13 Si'ILL OPERATIONAL. OPERATOR HAS ADDITIONAL INFORMA-TION OF HPCS OPERATION, FAILURE IS NON= PROPAGATING. l REFEREtcEs: l PSID M 49 EEV. T E1010/pG. HPC6 HEV. K EQ 0.S. Y011 t1ITIGATION EVENT CAPAaILITY A B C D rN ADE00 ATE X N 1 N (_/ INADECUATE I (
05/09/82 -CINCIhhATI GAS & ELECTRIC COMPANY PAGE 324 ID: LP-4 Wk. H. ZI,%=LR NUCLEAR PLWER STATIch Ut1IT 1 REV A
]
OSTIFICATION F0H INTEHIM OPERATION OF: 1E21-F006 LOCATION':C-1 DESCRIPTION POSITION SWITCH SYSTEM: LOW PRESSUBE CORE SPRAY (LP) SUBSYS:NONE SAFETY FUNCTIOh NOhE (TESTABILITY) POSITION SWITCH FOR TESTABLE CHECK VALVE SENSING FEATURE DIV:I
EVENT------ ,
---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL CohTACTS OPEN A LOCA CONTACTS CLOSED NOT DETERMINED B N/A N/A N/A C N/A N/A N/A D N/A N/A N/A
-------------------QUALIFICATION
SUMMARY
P'ARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TE,MPERATURE, DEG F NONE 340 N/A N/A N/A
!SSURE, INCH-H2O NONE 40.4 PSIG N/A N/A N/A MIDITY, %RH dOhE 100 N/A N/A N/A ADIATIDH, RADS NONE 9.02E8 N/A N/A N/A OPERABILITY N0dE 100 DAYS N/A N/A N/A OTHER: N/A N/A N/A
-------------------- CLASS 1E INTERFACES -----------------------------
--- --- - ----- I.NPUTS --------------- ----------------- GUTPUTS -------------- MOTIVE POWER: N/A MOTIVE POWER: N/A CONTROI f0WER': E21A-F4,PNL1H13-P601 CONTROL P0 DER: KiB SENSING SIGNAL: DISK POSITION EXECUTE SIGNAL: N/A COMMAND SIGNAL: h/A INHIBIT SIGdAL: N/A PROCESS SIGNAL: N/A PEBMISSIVE SIGNAL: N/A
***=* CINCINNATI GAS & ELECTRIC PPOPRIETARY INFORMATION *****
-. . . - , . - - . - - , - - , - _ . - - - _w%-..w. - . - - . -- -.
l 05/09/82 CI!iCluN ATI G AS - & ELECIFIC COMPANY PAGE 325
ids LP.4 'a M . H. ZI.v.AER-NUCLEAR P0sER STATION UhlT 1 REV A l
]
YUTENTIAL FAILUPE FAILbRE ISOLATION INTERFACE: MAGNETIC SWITCH DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON= PROPAGATING i
. FAILURE M'DE: 0 OPEN CONTACTS FAILURE EFFECT': IMPROPER INDICATION OF DISK POSITION.
1 POTENTIAL FAILURE FAILUPE ISOLATION INTERFACE: MAGhETIC SWITCH DEVICE: b/A CAUSE': SHORT CIRCUIT BASIS: NON= PROPAGATING FAILURE MODE: CLOSED CONTACTS FAILURE EFFECT: IMPROPER IIIDICATION OF DISK POSITION. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: NAGNETIC SWITCH DEVICE: FUSE E21-F6 CAUSE: SHORT CIRCUIT BASIS: NOT SUBJECTED TO MARSH ENVIRON.iENT
'AILURE HODE: LOSS OF CONTFDL PORR FAILURE EFFECT: LOST INDICATION OF DISK AND ACTUATOR POSITIONS.
BASIS: . . . CHECK VALVE IS STILL OPERATIONAL. OPERATOR HAS ADDITIONAL INFORMATION OF LPCS OPERATIch.
REFERENCES:
E1010/PG. LP01 REV. S P&ID p.50 REY. U EU D.S. YO10 etITIGATION EVE *4T CAPABILITY A B C D
& ADEOUATE X N N N Q INADEQUATE
. - = + emee.--- . , - . . -
a=* * -Mae em w w w- -w a + .e .w w- - e m . g--
05/09/s2 CIsCI.r.ATI GAS'& ELECTPIC COMPANY PAGE 111 ids HH-23 nM. H. II/*LF t4UCLEAR POwEh STATIOh UNIT 1 REV A 1 JUSTIFICATIUh FOR INTERI:t OPERATION OF 1E12-F041A&B LOCATION'C-1 DESCRIPTION: POSITION SWITCH SYSTEM RESIOUAL HEAT REMOVAL (RH) SUBSYS:NONE SAFETY FUNCTION'NONE : (TESTABILITY) POSITION SWITCH FOR TESTABLE CHECK VALVE SEleSIl4G FEATURE DIV:I
--- ---EVEST------ ,
---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL DE-ENERGIZED & CONTACTS OPEN A LOCA DE-ENERGIZED & CONTACTS OPEN h0T DETERMIhED 8 N/A N/A N/A C M/A N/A ^ N/A D h/A h/A h/A
--------- --------- - -------0UALIFICATIOi
SUMMARY
PARAMETER ---- = D EM 0li S IR A TED ----- ----------------REQUIRED-----~~--------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F NONE 340 N/A N/A N/A
)SSURE, IUCH-H2O NONE 40.4 PSIG N/A N/A N/A 9JhIDITY,%RH N0!!E 100 N/A N/A N/A BADIATION, FADS tiONE 9.02E8 N/A N/A N/A OPERABILITY N0dE 100 DAYS N/A N/A N/A OTHEh N/A N/A N/A
--- ----- ----------- -------- CLASS 1E INTERFACES -----------------------------
--- --- - ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE P'0WER: N/A MOTIVE POWER: N/A CONTROL E0WER: INST BUS A ' & B CONTROL PO'eER: K51ALB SENSli4G SIGNAL: DISK POSITION EXECUTE SIGNAL: N/A COMMAND SIGWAL: H/A l l INHIBIT SIGNAL: a/a PROCESS SIGNAL: N/A PERMISSIVE SIGNAL: N/A (p_f . ***** CINCINNATI GAS & ELECTRIC PROPRIETARY INFORMATION ***** - ( (
CI'.CI'.r4ATI GAS & ELECTRIC COMPANY PAGE 112 05/09/02 II*tER 10CLFAR PO'nER STATION UdIT 1 REV A ID: RH.23 Ar. n. POTESTIAL FAILURE FAILURE ISOLATION INTERFACE: MAGNETIC SWITCH DEVICE: N/A , CAUSE: OPEN CIRCUIT BASIS: NOiJ-PROPAGATING FAILURE HODE: OPEN CONTACTS , FAILURE EFFECT: IMPROPER INDICATION OF DISK POSITION. POTENTIAL FAILUPE FAILURE ISOLATION DEVICE: N/A INTERFACE: NAGNETIC SWITCH CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE PODE: CLOSED CONTACTS FAILURE EFFECT: IMPROPER I6DICATION OF DISK POSITIOh. POTENTIAL FAILURE FAILURE ISOLATION DEVICE: FUSE 3 INTERFACE: NAGhETIC SWITCH BASIS: HOT SUBJECTED TO SHORT TO GROUtID 9,C AUSE: HARSH ENVIRONMENT FAILURE M'0DE: LOSS OF C0hTPOL FAILURE EFFECT: LOST Ir.DICATION OF DISK At4D ACTUATON POSITIONS. BASIS: CHECK VALVE IS STILL OPERAfIONAL. OPERATOR HAS ADDITIONAL INFORMATION OF SYSTEM OPERATION.
REFERENCES:
E1010/PG. RH13 REV. H P&ID P.51 REV. AF D.S. RH03 HITIGATION EVENT CAPARILITY A B C D X N N N
/~ - ADEQUATE 's / INADEQUATE
05/09/h2 - -
' CINC1bNATI GAS & ELECTRIC COMPAfiY PAGE 113 n9 H. ZIMMER HUCLEAR PO'ER e SIATION UNIT 1 REV A ID: Ph-24 JUSTIFICATIO!; F0F II.TERIM OPEPATION OF: 1E12-F041C LOCATION:C-1 DESCRIPTION POSITIGP SWITCH SYSTEM PESIDUAL HEAT REMOVAL (RH) SUBSYSINONE SAFETY FUNCTION N0aE (TESTABILITY)
POSITION SWITCH FOR TESTABLE CHECK VALVE SEftSING FEATURE DIV:1
-------EVENT------ ,
==-------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE 140RMAL DE-ENERGIZED & CONIACTS OPEN A LOCA DE-ENERGIZED & CONTACTS OPEN NOT DETERMINED B N/A N/A N/A C N/A N/A N/A D N/A f3 / A N/A
------- - -------------------QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTPATED----- ----------------REQUIRED---------------- EVENT A EVElli B EVENT C EVENT D
MPERATURE, DEG F h0i4E 340 N/A N/A N/A 5SSUPE, INCH-H2O NONE 40.4 PSIG r!/A N/A N/A 9JHIDITY, %RH f:OtJE 100 N/A N/A N/A R ADI ATIU!!, RADS !.ONE 9.02E6 N/A N/A N/A OPERABILITY NONE 100 DAYS N/A ti/ A h/A N/A N/A N/A OTHER: --- ----- -------------------- C L A S S 1 E IrlTE R F AC E S ----------------------------- --------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
N/A MOTIVE PO' DER: N/A MOTIVE PodER: CONTROL f0aER': INST BUS B CONTROL POWER: K52 SENSING SIGiAL: DISK POSITION EXECUTE SIGi1AL: N/A COMMAND SIG:!AL: N/A ItHIBIT SIGdAL: !!/ A PROCESS SIGfiAL: !1/ A PERMISSIVE SIGNAL: d/A ,x (sl ***** cit;CINf1ATI GAS & ELECTRIC PROPRIETARY IhFORMATION i (
05/09/G2 CINCIN4ATI GAS & ELECTFIC COAPA.'.Y PAGE 114 ID: Rd.24 C'. n. ZI,36EP NUCLEAR PObt'R STATION U.IT N 1 REV A
)
TEiTIAI. FAILURL FAILURE ISOLATION INTEPFACE: MAGNETIC SdITCH DEVICE: N/A CAUSE: OPD. CIHCUIT BASIS NON-PROPAGATING FAILURE MbDE: OPEh CONTACTS FAILURE EFFECT: IMPPOPER INDICATION OF DISK POSITION. POTENTIAL FAILUBE FAILURE ISOLATION ItiTERF ACE : M AGt; ETIC SWITCH DEVICE: N/A CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILUBE M'DE: 0 CLOSED CONTACTS FAILURE EFFECT: IMPROPER INDICATION OF DISK POSITION. POTE!.TIAL FAILUBE FAILURE ISOLATION s, INTERFACE: MAGNETIC SWITCH DEVICE: FUSE
,CAUSE: SHORT TO GROUND BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT AILURE M'0DE: LOSS OF CONTROL FAILURE EFFECT: LOST INDICATION OF DISK AND ACTUATOR POSITIONS.
BASIS: CHECK ' VALVE IS STILL OPERATIONAL. OPERATOR HAS ADDITIONAL INFORMATION OF SYSTEM OPERATION. REFEREf3CES: E1010/pf. PH 13 KEV. H P&ID M 51 REV. AF D.S. RH03 FITIGATIbN EVENT CAPABILITY A B C D I X N N N rN ADE00 ATE l C/ IMADEQUATE
9 05/09/b2 cit.CIhNATI GAS & ELECTRIC COMPAdY PAGE 118 ID:'hn-29 *M. H. ZIMhER NUCLEAR P0eER SIATION UNIT 1 REV A TIFICATION FOR INTEBIM OPERATION OF: 1E12-F050A LOCATIdN'C-1 : DESCRIPTION: POSITIO.i SWITCH SYSTEM: PESIDUAL HEAT PEMOVAL tRH) SUBSYS:NONE SAFETY FUNCTIUN:h0NE (TESTABILITY) POSITION SWITCH FOR TESTABLE CHECK VALVE SEhSING FEATURE DIV:I
-------EVENT---- -- ---------DEVICE STATUS--------- ---ESTIMATED TIPE---
~
TO FAILURE NORMAL DE-ENERGIZED & CONTACTS OPEN A LOCA DE-ENERGIZED & CONTACTS OPEh NOT CETERMINED B n/A N/A N/A C N/A N/A N/A D N/A N/A N/A
------- - -------------------QUALIFICATI0ii SUM.ARY----------------------------- A PARAMETER -----DEMONSTRATED----- ----------------REQUIRED----------------
EVENI A EVENT D EVENT C EVENT D TEMPEBATURE, DEG F NotlE 340 N/A N/A N/A lSSURE, INCH-H2O NONE 40.4 PSIG N/A N/A N/A MIDITY, %FH NONE 100 N/A N/A N/A ADIATION, RADS ?J0h8 9.02E8 N/A N/A N/A OPERASILITY NobE 100 DAYS N/A N/A N/A OTHER: N/A N/A N/A
--------- ----------- -------- CLASS 1E INTERFACES -----------------------------
--- --- - ----- INPUTS --------------- ----------e------ OUTPUTS --------------
MOTIVE PdWEP: N/A MOTIVE POWER: , N/A CUNTROL PbWER: If1ST BUS'A CONTROL POWER: K50A SENSING SIGNAL: DISK POSITION EXECUTE SIGNAL: N/A COMMAND SIGhAL: N/A INHIBIT SIGdAL: h/A PROCESS SIGNAL: N/A PERMISSIVE SIGNAL: N/A N
,m)
(,) ***** CI:JCIhhATI GAS & ELECTRIC PROPRIETABY INFORMATION *****
05/09/02 CINClanATI GAS & ELECT 81C COMPANY PAGE 119 ID: Ad=29 a ti . H. ZI t.'4ER NUCLE A R P0hER STATION UNIT 1 REV A T
)
rvTENTIAL FAILUPE FAILUPE ISOLATION INTERFACE: MAGhETIC SWITCH DEVICE: h/A CAUSE: OPEn CIPCUIT BASIS: NON-PROPAGATING FAILURE MbDE: OPEN CONTACTS FAILURE EFFECT': IhPROPER INDICATION bF DISK POSITION. POTEATIAL FAILUPE FAILURE ISOLATION INTEPFACE: MAGNETIC SWITCH DEVICE: N/A CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE MbDE: CLOSED CONTACTS FAILURE EFFECT: IMPROPER INDICATION OF DISK POSITION. POTENTIAL FAILURE FAILURE ISOLATION INTEPFACE: MAGNETIC ShITCH CEVICE: FUSE
;CAUSE: SFOPT TO GROUND BASIS: NOT SUBJECTED TO HAPSH ENVIRONMENT AILURE MODE: LOSS OF CONTROL FAILURE EFFECT: LOST INDICATION OF DISK AiiD ACTUATOR POSITIONS.
BASIS: , l CHECK VALVE IS STILL OPERATIONAL. OPERATOR HAS ADDITIONAL INFORMATION OF SYSTEM OPERATION. l l l PEFE8ENCES: 1 E1010/PG. PH 16 REV. M l P&ID M-51 PEV. AF D.S. RH03 l MITIGATIO!i EVENT l CAPABILITY A B C D
-m e ADEOUATE X N N N (j INADEQUATE
, t (
l l 05/09/62 C I LC I'4 N ATI GAS & ELECIFIC COPPANY PAGE 123 ID: Ph-30 ap. .h. ZIAMCH NUCLEAR PJhER STATION UbII 1 REV A
] ,
tabIIFICATIDh FdR INTERI!! OPERATION OF: 1E12-F0508 , LOCATI0td C-1 DESCRIPTION POSITION SWlTCH SYSTEM: RESIDUAL' HEAT' REMOVAL ,(RH) SUBSYS NOME SAFETY FUNCTION:N0hE (TESTABINITY) POSITIOrt SWITCH FOR TESTABLE CHECK VALVE SES SING: FEATURE T lf DIV :i'
--- ,--EVENT------- ---------DEVICE STATUS--------- '---ESTIMATED TIME---
. . TO FAILURE NOPHAL DE-ENERGIZED & CONTACTS OPEN A LOCA DE-ENERGIZED & CONTACTS OPEN NOT DETERMINED 8 N/A N/A. .
N/A C N/A N/A N/A D 6/A N/A N/A
--------- -------------------00ALIFICATION
SUMMARY
PARAMETEP ----- D E M 0 ii S T R AI SL ----- ----------------REQUIRED----------------
, i EVENT'A EVENT B EVENT C EVENT D TEMPERATURE, DEG F NO1E '
340 N/A N/A N/A
~
ISSURE, INCH-H2O NChE 40.4 PSIG N/A N/A N/A hMIDITY,%RH NONE , 100 N/A N/A N/A BADIATION, RADS . NONE ,, 9.02FP. K/A N/A'. N/A OPERABILITY ' NONE ?i 100 DA'15 h/A N/A N/A OTHER: ' ' N/A' N/A N/A
. 1
[ ,
~ ------- - ----------- -------- CLASS 1E INTERFi.CES - - - - - ~ ~ ~ - - = - - - - - - - - - - - - - - - - - - ------- - ----- ItiPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: N/A . ') 'S. MOTIyE PGAER: N/A CONTROL fowEP: INST SUS B. / 'I
, CONTRCL' POWER 4 . KE0B DISK POSITION SENSING SIGNAL: '
~
EXECUTE SIGNAL; N/A COMMA:D SIGhAL: N/A , ,j i INHIBIT SIGSAL: 1/A , PRC ESS SIGii AL: N/A PbFMISSIVE SIGNAL: N/A s
***=* CIhCItir;ATI GAS & ELECTRIC PROPRIETAF It. FORM ATION *****
(a~'l 4 e
+ q 0 4
i
. . - _ . . . . _ . . - , . . _ . - --- .. - - . . .. .- . . ~ - - - - - _ . .
05/09/82 CINCIr.NATI GAS & ELECTPIC COMPAi4Y PAGE 124 ID3 Rd.30 kh. d. ZIMMER NUCLEAR P0.sER STATIO. Uh1T 1 REV A IEr.TIAL FAILUPE FAILURE ISQLATION INTERFACE: MAGNETIC SWITCH DEVICE: N/A CAUSE: OPEa CIRCUIT BASIS: NON-PROPAGATING FAILURE P'DE: 0 OPEN CONTACTS FAILURE EFFECT: IMPROPER INDICATION OF DISK POSITION. POTENTIAL FAILUPE FAILUPE ISOLATION IhTERFACE: HAGilETIC SWITCH DEVICE: N/A CAUSE's SHORT CIRCUIT BASIS: NON. PROPAGATING FAILURE M6DE: CLOSED CONTACTS FAILURE EFFECT: IMPROPER INDICATION OF DISK POSITION. POTENTIAL FAILURE FAILUPE ISOLATION INTERFACE: M AGNETIC Sn' ITCH DEVICE: FUSE SCAUSE: SHORT TO GROUND BASIS: h07 SUBJECTED TO HARSH ENVIRONMENT aILUBE. MODE: LOSS OF CONTROL FAILURE EFFECT: LOST INDICATION OF DISK AND ACTUATOR POSITIONS. BASIS: _ CHECK VALVE IS STILL OPERATIONAL. OPERATOR HAS ADDITIONAL INFORMATION OF SYSTEM OPEPATION.
REFERENCES:
E1010/PG. PH P&ID M-51 FEV. AF D.S. PH03 MITIGATION EVENT CAPABILITY A B C D ADEOUATE X N h N INADECUATE {}
i 05/v9/o2 CI: cit... ATI. GAS- & ELEC1FIC COMPA4,Y PAGE 214 ID: FI-1 WM. H. ZIONEP .40 CLEAR P0aFR STATION UNIT 1 REV A L,dTIFICATIOh FOR ILTERIM OPEPATIO.4 0F: 1E51-F066 LOCATION:C-1 DESCRIPTION:LIf4IT SWITCH SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SUBSYS SENSING FEATURE SAFETY FUNCTION h0NE (TESTABILITY) LIMIT SW IS ON IND LIGHT CKT FOR TESTABLE CHK VLV SEhSING FEATURE DIV:I
----- -EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIVE---
TO FAILURE NORMAL DE-ENERGIZED A LOCA DE-Et4ERGIZED NOT DETERMINED B h/A DEuZNERGIZED NOT DETERMINED C N/A DE-ENERGIZED NOT DETERMINED D U/ A DE-ENERGIZED NOT DETERMINED
--------- -------------------QUALIFICATION Sur.HARY-----------------------------
PAhAMETEP -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F N0hE 340 N/A N/A N/A
~
':S SU RE , IhCH-H2O N0nE 40.4 PSIG N/A N/A h/A MIDITY, %RH NONE 100 N/A N/A N/A
, ADIATION, RADS NONE 9.02E8 N/A N/A N/A OPERABILITY NONE 100 DAYS N/A N/A N/A OTHER: NONE N/A N/A ri/A
--------- - ------------------ CLASS 1E INTERFACES -----------------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: N/A MOTIVE POWER: CONTROL POKER: FUSE F33 CONTROL POWER: SENSING SIGt=AL: ACTUATOR POSITION EXECUIE SIGNAL: l COMtiAliD SIGNAL: 1 INHIBIT SIGNAL: PROCESS SIGNAL: LIGHT (RED) LIGHT (GPEEN) PEPnISSIVE SIGNAL:
~
()s ***** CINCInbATI GAS & ELECTRIC PROPhIETARY INFORMATION *****
v5/C9/92 C I'!C I M:ATI GAS & ELECTRIC COMPAhY PAGE 215 ID: PI-1 *i. n. ZIsnEF aVCLEAD POWER STATION UhIT 1 REV A (sTENTIAL FAILURE FAILURE ISOLATION INTERFACE: SWITCH CONTCT (OPEN) DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILUPE MODE: FAILED OPEh FAILURE EFFECT: LOST / IMPROPER INDICATION. POTENTIAL FAILbR"E FAILURE ISOLATION INTERFACE: DEVICE: N/A CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE MODE: FAILED CLOSED FAILURE EFFECT: LOST /IMPROPEP INDICATI N.- POTESTIAL FAILUBE FAILURE ISOLATION INTERFACE: DEVICE: FUSE
~~' BASIS: DEVICE NOT SUBJECT SHORT TO GROUND .
h'j C AUSE: TO HARSH ENVIR04t4ENT NAILUME M'DE:0 SHORT TO GROUND FAILURE EFFECT: LOST /IMPPOPER INDICATION. POTENTIAL FAILUBE FAILURE ISOLATION INTERFACE: SW CONTACTS (CLOSED) DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE M'DE: 0 FAILED OPEN FAILURE EFFECT: LOST / IMPROPER INDICATION. POTEdTIAL FAILURE FAILURE ISOLATION INTERFACE: DEVICE: N/A CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE MbOE: FAILED CLOSED
,L ILUPF EFFECT: LOST /IHPRCPER INDICATION.
! T \al ( I
05/09/82 CINCli.!*ATI GAS & ELECTRIC COMPANY PAGE 216 ID: FI.1 , hM. H. ZIMhER NUCLEAR POWER STATION Uf'IT 1 REV A sp - FAILURE ISOLATIOh A IEr.TIAL FAILURE INTERFACE: DEVICE: FUSE CAUSE: SHORT CIRCUIT BASIS: NOT SUBJECTED TO HARSH ENVIRONMENT FAILUPE MbDE: SHORT TO GROUND FAILURE EFFECT: LOST / IMPROPER INDICATION. BASIS:. THIS LIMIT SWITCH PROVIDES INFORMATION ONLY. THE TESTABLE CHECK VA6VE db kHICH IT IS INSTALLED IS NORMALLY CLOSED AND ANY FAILURE OF THE LIMIT Sh1TCH JILL NOT DEGPADE THE SAFETY FUhCTION OF THE SYSTEM, NOR WILL ANY FAILORE PROPAGATE TO OTHER 1E DEVICES.
REFERENCES:
E1010/PG. RI12 EQ D.S. Y006, YO10, i'011, Y012
/
MITIGATION EVENT (d) CAPABILITY A B C D ADEOUATE X X X X INADEQUATE O G O (~'T . t/
EX DATA SHEET: E006 JUSTIFICATION FOR EXEMPTING EQUIPMENT FROM ENVIRONMENTAL QUALIFICATION REQUIREMENTS SYSTEM: PC; VG EQUIPMENT TAG NUMBERS: '12 -PC 001,2,4,5,7,8,10,11,13,14,16,17,19,20,22,23 1EL-VG 084 A/C, IEL-VG 085 A/C MANUFACTURER: Genern1 Floctric MODEL NUMBER: ET-16 POWER: C ESSENTIAL POWER C NON-ESSENTIAL POWER ESSENTIAL POWER, NON-ESSENTIAL CABLE JUSTIFICATION: Indication lights on local control panels in the Reactor Building perform no safety function to mitigate a postulated HELB or LOCA event. Failure of an indicating light will not propagate beyond indicating circuit. lEL-VG084A/C and lELVG085A/C will be fused separate from MCC control fuse
] prior to fuel load.
FAILURE MODEL EFFECTS ANALYSIS (ATTACHED): To be supplied with JIO PREPARED BY: 5 [] /Wl_ DATE: 7-t2 ,7 L I
"'N '=+-3 we. w e ee+ -em.
05/09/92 CINCINNATI GAS & ELF.CTRIC COMP AN'Y PAGE 36 ID: PC-9 aM. H. ZP-ME8 NUCLEAR PO*ER STATIOh UNIT 1 REV A ISTIFIC ATIOli FOR INTERI?. OPER ATION OF: 1ZL-PC001,07,13,19 LOCATIONiR-4A DESCRIPTION: INDICATING LIGHT SYSTEM: PRESSURE SUPPRESSION (PC) SUBSYS:DRYWELL VAC REL VLVS SAFETY FUNCTIdN:NONE (TESTABILITY) VACUUM BREAKER POSITION INDICATION COMbAND FEATURE DIV:I
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE h0RMAL OFF A LOCA ON (PERIODICALLY) NOT DETERMINED B MSL/Fh BREAK OFF NOT DETERMINED C RCIC BREAK OFF NOT DETERMINED D RWCU BREAK OFF NOT DETERMINED
--------- -------------------QUALIFICATIDH
SUMMARY
PARAhETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEhPERATURE, DEG F 110NE 45-129 125 213 160 INCH-H2O N0dE -0.25 15 PSIA 15.7 PSIA 16 PSIA h)'SSURE.
!IDITY. %RH N.ADIATIUM. RADS NONE NONE 0-60 6.32E6 100 1.71E6 100 1.71E6 100 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER: AGING NONE 40 YEAPS 40 YEARS 40 YEARS 40 YEARS --- ----- ----------- -------- CLASS 1E INTERFACES ------------------~~--------- ------- ,- ----- INPUTS --------------- -----------------OUTPUTS--------------
MOTIVE POWER: N/A MOTIVE POWER: N/A CONTROL PbWERi FU1 (MCC1A) CONTROL PONER: N/A SEiiSIliG SIGNAL: N/A EXECUTE SIGNAL: N/A COMMAND SIGNAL: G/A INHIBIT SIGNAL: AUXILIARY RELAYS E80 CESS SIGNAL: N/A LIMIT SWITCHES PERMISSIVE SIGNAL: N/A f ***** CINCINNATI GAS & ELECTRIC PRCPRIETA?Y INFORMATION *****
05/09/82 CI.1CI h N ATI GAS & ELECTPIC COMPANY PAGE 37 ID: PC-9 he. H. ZIM.*EP tlVCLEAk P0xER STATION UbIT 1 REV A m , I a tENTIAL FAILUPE FAILUHE ISOLATION INTERFACE: 1HY-PC500,02,04,06/ DEVICE: N/A CAUSE: Sh0RT TO GROUND BASIS: NON-PROPAGATING TYPE FAILURE FAILURE M'DE: 0 IMPROPER INDICATION FAILURE EFFECT: LOST INDICATION POTENTIAL FAILURE FAILURE ISOLATI0tl INTERFACE: 1PC005A.D DEVICE: N/A CAUSE: OPE 3 CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE F0DE': I!4 PROPER INDIC ATION FAILURE EFFECT: LOST INDICATION. BASIS: SINCE THE_SYSTE:4 IS USED FOR TESTING AIB CHECK VALVES PERIODICALLY, s THE LOSS OF INDICATION IS OF NO CONSEQUENCE TO THE SAFE OPERATION OF rsjTHE PLANT. f -
REFERENCES:
(1) COMPONENT EVALUATION DATA SHEET (2) I!!STRUMENT LIST S & L 3306 (3) DWG. E1010/PG01/02 & M-48 l l HITIGATION EVE tJT l CAPABILIT) A B C D l l ADE00 ATE X X X X IMADEQUATE i 1 V ( t
05/09/82 CIICI.NNATI GAS & ELECTB1C COdPAbi FAGE 5
- PC-10 sh. n. ZI.d.4ER NUCLEAR POWER STATION UNIT 1 REV A
')
JOITIFICATIOf; FOR IirtE RIM OPERATION OF: 1ZL-PC002,08,14,20
~
LOCATION:R-4A DESCRIPTION:It;DICATING LIGHT SYSTEM: PRESSURE SUPPRESSION (PC) SUBSYS:DRYWELL VAC REL VLVS SAFETY FUNCTION:NONE (TESTABILITY) VACUUM BREAKER POSITION It<DICATION COMMAND FEATURE DIV:II
---- L-EVENT ==--"-- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NOBHAL OFF A LOCA ON (PERIODICALLY) NOT DETERMINED B MSL/FW BREAK OFF NOT DETERMINED C RCIC BREAK OFF NOT DETERMINED D RWCU BREAK OFF NOT DETEPHINED
--------- ------- --- -------QUALIFICATION
SUMMARY
l PART.METEp -----DEMONSTRATED----- ----------------REQUIRED---------------- ! EVENT A EVENT B EVENT C EVENT D l _PERATURE, DEG F NONE 45-129 125 213 160 JSSURE, INCH-H2O N0iiE =0.25 15 PSIA ~ 15.7 PSIA 16 PSIA sMIDITY, %RH NOr1E 0-60 100 100 100 RADIATION, FADS NoaE 6.32E6 1.71E6 1.71E6 1.71E6 OPEHABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER: AGING NONE 40 YEARS 40 YEARS 40 YEARS 40 YEARS l l l --------- -------------------- CLASS 1E INTERFACES -----------------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: N/A MOTIVE POWER: N/A CONTROL 60WER': FU2 (PCC13) CONTROL POWER: N/A SENSItJG SIGr: AL: N/A EXECUTE SIGNAL: N/A COMl1AND SIGNAL: N/A l Il4HIBIT SIGNAL: AUXILIABY RELAYS PROCESS SIGNAL: N/A LIP.IT SWITCHES , PERMISSIVE SIGNAL: N/A ( ** * *
- CINCI!;N ATI GAS & ELECTRIC PROPRIETARY INFORhATION *****
( (
05/09/02 C I PC I'.'4 A T I GAS & ELECTPlC COMPALY PAGE 6 PC-10~ ^%. H. ZIM*ER HUCLEAP POWER STAT 10f, UNIT 1 HEV A s POIENIIALFAILURE FAILURE ISOLATION Il3TERFACE: 1HY-PC501,03,05,07 DEVICE: h/A CAUSE's SHORI CIRCUIT BASIS: il0N-PROP AG ATIN G FAILURE MbDE: IMPROPER INDICATION FAILURE EFFECT: LOST INDICATIdN POTENT'IAL FAILURE FAILUBE ISOLATION INTERFACE: 1PC005A.D DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE MbDE': IMPROPER INDIC ATION FAILUBE EFFECT: LOST INDICATION. BASI 5: SINCE THE SYSTEM IS USED FOR TESTING AIR CHECK VALVES PERIODICALLY, ! g THE LOSS OF INDICATION IS OF NO CONSEQUENCES TO THE SAFE OPEPATION T oF THE PLANT. gj REFEREf4CES: COMPONENT EVALUATION DATA SHEET INSTRUMENT LISI S&L 3306 DWG. E1010/PG. 01, 02 AND H-48 - MITIGATIdN EVENT CAPABILITY A B C D ADEOUATE X X X X IdADEQUATE l } ,-.
,l '
1
05/09/82 CINCINhATI GAS &~ ELECTRIC COMPAFY PAGE 7
- PC-11 45 H. ZI"ER N UCLEAR 901ER SIA1104 UNIT 1 REV A
'/. 'l JUSTIFICATION FOR I.5 TERIM OPERATION OF: 12L-PC004,10,16,22 LOCATION': Re4A DESCRIPTION: INDICATING LIGHT SYSTEM: PRESSURE SUPPRESSION (PC) SUBSYS DRYWELL VAC REL VLVS SAFETY FUNCTION':NONE (TESTABILITY)
VACUUM BREAKER POSITION INDICATION COMMAND FEATURE DIV:1
--- - -EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE h0RMAL OFF A LOCA DN (PERIODICALLY) NOT DETERMINED B MSL/FW BREAK OFF NOT DETEPHINED C RCIC BREAK OFF NOT DETERMINED D RWCU BREAK OFF NOT DETERMINED
------- - --------- ---=-----QUALIFICATION
SUMMARY
PARAMETER -----DE"nNSTPATED----- ----------------REQUIRED---------------- EVENT A EVENT D EVENT C EVENT D MPERATUFE, DEG F NONE 45-129 125 213 160 JSSURE. INCH-H2O ADHE -0.25 15 PSIA ~ 15.7 PSIA 16 PSIA l UMIDITY. %RH NONE 0-60 100 100 100 l RADIATION. RADS N0nE 6.32E6 1.71E6 1.71E6 1.71E6
- OPERABILITY FORE 100 DAYS 1 DAY 1 DAY 1 DAY
! OTHER: AGING HONE 40 YEARS 40 YEARS 40 YEARS 40 YEARS
--- ----- - --------- -------- CLASS 1E INTERFACES ---~~------------------------ ------- - ----- INPUTS --------------- ------~~--------- OUTPUTS --------------
1 MOTIVE POWER: N/A MCTIVE POWER: N/A l l CONTROL P'OhER: FU1 (MCC1A) . , CONTROL POWER: N/A l SENSING SIGNAL N/A EXECUTE SIGNAL: N/A l COMMAND SIGNAL: N/A INHIBIT SIGLAL: AUAILIAFY RELAYS PROCESS SIGNAL: N/A LIMIT. SWITCHES PERMISSIVE SIGNAL: N/A
/A'
( l
***** CINCINhATI GAS & ELECTRIC PROPRIETARY INFORMATIOW *****
l (
'05/09/82
~
CInCIra t: ATI GAS & ELECTRIC COMPA:4Y PAGE 6
- PC-11 A li . H. ZI * '4 F P NUCLEAR POWER STATION UNIT 1 REV A
' )
POTEtTIAL FAILbPE FAILURE ISCLATION INTERFACE: 1HY-PC508,10,12,16 DEVICE: N/A CAUSE: SHOFI CIRCUIT BASIS: NON-PROPAGATING FAILURE M DE: IMPROPEH INDICATION FAILURE EFFECT: LOST INDICATI0tl. POTENTIAL FAILURE FAILURE ISOLATION It1TERTACE: 1PC006A.D DEVICE: NA CAUSE: OPEh CIRCUIT BASIS: NON-PRdPAGATING FAILURE MbDE: IMPPOPER INDICATION FAILURE EFFECT: LOST INDICATION. BASIS: SINCE.THE SYSTEM IS USED FOP TESTING ".iR CHECK VALVES PERIODICALLY,
' INDICATION IS OF NO CONSEOUENCE TO THE SAFE OPERATICt-(NTHELOSSOF[OFTHEPLANT.
REFER'ErjCES: COMPONENT EVALUATION DATA SHEET INSTRUMENT LIST S&L 3306 DWG. E1010/PG. 01, 02 MITICATIUf! EVENT CAPABILITY A B C D ADE00 ATE X X X X INADEQUATE I e-s
~
l
05/09/82 CI' CI'.a A TI G AS & ELECTRIC CuiiP At:f PAGE 9 r PC-12 hb. n. ZIveEH NUCLEAR PONEH STATION UdiT 1 REV A l JUSTIFICATION FOR INTERIr4 OPEPATION OF: 1ZL-PC005,11,17,23 LOCATION':R-4A DESCRIPTION: INDICATING LIGHT SYSTEM: PRESSURE SUPPRESSION (PC) SUBSYS:DRYWELL VAC REL VLYS SAFETY FUNCTION:NONE (TESTABILITY) VACUUM BREAKER POSITION INDICATION
-COMMAND FEATURE DIV:II
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL OFF A LOCA Oti (PERIODICALLY) NOT DETERMINED B MSL/FW BREAK OFF NOT DETERMINED C RCIC BREAK OF NOT DETERMINED D RECU BREAK OFF NOT DETERMINED
--------- - -----------------oUALIFICATION
SUMMARY
PAR bSTEg -----DEMGNSTRATED----- ----------------REQUIRED----------------
. EVENT A EVENT B EVENT C EVENT D t MPERATURE, DEG F NONE 45-129 125 213 160 JSSURE. IUCH-H2O h0NE -0.25 15 PSIA 15.7 PSIA 16 PSIA uMIDITY. %FH NOrJE 0-60 100 100 100 RADIATION. RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OThER: AGING N0hE 40 YEARS 40 YEARS 40 YEARS 40 YEARS ------- - - ------------------ CLASS 1E INTERFACES ----------------------------- --- ----- - --- INPUTS --------------- ----------------- GUTPUTS --------------
MOTIVE POWER: N/A MOTIVE POWER: N/A l CONTROL POWEP': FU2 (MCC1B) CONTROL POWER: N/A SENSING SIGhAL: N/A EXECUTE SIGNAL: N/A CDPMAND SIGbAL: N/A INHI6IT SIG:i AL: AUXILIARY RELAYS PROCESS SIGNAL: N/A LIli1T SWIICHES PERNISSIVE SIGNAL: N/A (a l
***** CIbCIhNATI GAS & ELECTRIC PROPRIETARY INFORMATION *****
(
05/09/82 CIriCINN ATI GAS & ELI.CTRIC COMP A'JY PAGE 10 he. H. ZIHMEP NUCLEAR POWER STATION UNIT 1 REV A g: PC-17 i PdTEl.TIAL FAILUPE FAILURE ISOLATION INTERFACE: 1HY.PC509,11,13,15 DEVICE: N/A CAUSE: SHORT CIRCUIT BASIS: Not.-PROPAGATING FAILURE MUDE': IMPROPER IllDICATION FAILURE EFFECT: LOST It4DICATION. POTE!#TIAL FAILURE FAILURE ISOLATION ItiTEPFACE: 1PC006A.D DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE M'DE': 0 IMPROPER INDICATION FAILUPE EFFECT: LOST INDICATION. . . BASIS: t SINCE THE SYSTEM IS USED FOR TESTING AIR CHECK VALVES PERIODICALLY, fN THE LbSS OF INDICATION IS OF NO CONSEQUEbCE TO THE SAFE OPERATION (Ch0FTHEPLANT. REFEFENCES:~ ! COMPONENT EVALUATIOid DATA SHEET I'JSTRUMENT LIST S&L 3306 DWG. E1010/PG. 01, 02 AND M-48 l MITIGATION EVENT CAPABILITY A B C D ADEOUATE X X X X I:iADEQUATE l l I l i
EX DATA SHEET: E007 JUSTIFICATION FOR ENE"PTING EQUIPMENT REVISED: 12/27/83 FRO 31 ENVIRONMENTAL OUALIFICATION REQUIREMENTS SYE!D:: Reactor Core Isolation Cooling EQUIP}?.NT TAG KUMBERS: See att.:hed EQIL MANEFACT3 ER: See attached EQEL MODII, .T:GER: See attached EQEL POrr.a: b ESSENTIAL POWER l I NON-ESSENTIAL POWER ESSENTIAL POWER, NON-ESSENTIAL CABLE JUSTIFICATION: The Reactar Core Isolation Cooling (RCIC) Systen is primarily designed to provide makeup water to the reactor in case of loss of access to the Turbine / Condenser ( (i.e., plant isolation event). It also has a safety function in providing makeup ( vater af ter a Eod Drop Accident. The only safety function required to mitigate a LCCA or HEL3 is to detect and isolate an RCIC high energy line break. Failure cde effect analysis shows that no failure mode of these components exists that cra propagate to affect safety function of other safety related components of thic system or other safety related syste=s. FAILURE y0LEL EFFECTS ANALYSIS (ATTACllED): RI-1,2,5 thru 26, 42, 43 il PREPARED BY: /bn N DATE:
/2/2 7// 3
. .n .
PE0 JECT NUMOEQ.413POS
. DATE 29 dun 82-REVISION 00G
.. ZIMMER EQUIPMENT OUALIFICATION 001346 e PLANT ID COMPONENT / .MODEL SPEC OR E.I. DWG COL / ROW CONTAIN 'FLO ACT/ ADO 0500 DATA' e5Y NUMBER EQUIPMENT MFR NUMBER 8/M NO. W/D No. ELEVATN IN OUT BUILD , LEV PASS REV CAI. SHT.
........ ............ 1.....................................e.....................
RI 1E51-COO 2 TURBIh;. ' TERRY GS-1 H-2210 E-142 E/15 R4D R.S. A La EOO7
. 475 RI lE51-COO 3 PUMP WEST. 74D24113 H-2135 E-142 E/16 R4D R.B. A A EX EOO7
. MOTOR 475 RI 1E51-FOO4 lit 4!T SWITCH NAMCO EA1703ttGO H-2266 E-142 F/15 R4D R.B. P EX M 52-1 EOO7
. CLOSED POSti!ON E-2908 475 CI 1 E 01 - F OO4 LIMIT SWITCH NAMCO EA17031100 H-22G6 E-142 F/15 R4D R.B. P EX M-52 1 EOO7
. OPEN POSITION E-2900 475 i
RI 1E51-FOO4 SOLENOID ASCO HT8320A175 H-2266 E-142 F/15 R4D R.B. ' P EX M-52 1 EOO7
. E-2908 475 RI 1E51-FOOS LIMIT SWITCH NAMCO EA17031100 H-2266 E-142 F/15 R4D R.B. P EX M 52-1 EOO7
. CLOSED POSITION 475 O! IE5t-FOOS LIMIT SWITCH NAMCO EA17031100 H-22GG E-142 F/15 R4D R.B. P EX M-52-1 EOO7
. OPEN POSITION 475 RI tES1-FOO5 SOLENOID ASCO HT8320A175 H-226G E-142 F/15 R4D R.B. P Ex M-52-t EOO7
. 475 RI 1 E 51 -F 010 MOTOR OPER- LIMIT SMS-OOO H-22G4 E-142 E/18 R4A R.D. A A EX M-52 2 EOO7 4 , ATED VALVE E-2322 475 3
')h.N,[RI 1E51-F045 MOTOR OPER- L'IM I T SMG-1 11-2020 E-142 E/15 R4D R.B.
- A EX M-52-1 EOO7 g-l'. ATED VALVE C-2329__ 475 s's N
. SARGENTMUNDY
> E NGINt!E f't B .
\ f 4 j .
*
- I
,, PROJECT NUMBER 4930-05 DATE 29 JUN 82 REVISION 006 ZIMMER EQUIPMENT OUALIFICATION D01346 , . PLANT ID COMPONENT / MODEL SPEC OR E.I. OWG COL / ROW CONTAIN FLD ACT/ ADD 0588 OATA I *SY NUMUER EOu!PMENI MFR NUMBER B/f4 No. W/D NO. ELEVAIN IN OUT DUILD LEV PASS REV CAT. SHl. ' ... ......... .... ......... 4............................................ ......... .... ...................., _.. .......................
RI SE51-FO12 MOTOR OPEW- LIMIT SMB-O-40 H-2264 E-142 E/I5 R4D R.B. A A EX M-52-2 EOO7 ATED VALVE E-2324 475 SI lE 51 -F O l 3 MOTOR OPER- LIMIT SMS-O-40 it-22G4 E-149 C/25 RSA R.B. A EX M-52-2 ~ EOO7 ATED VALVE E-2325 570 I RI 1 E 51 - F 02 2 MOTOR OPER- LIMIT SMB-DO H-2263 L-149 C/24 RSA R.B. A EX M-50 2 EOO7 ATED VALVE E-2323 570 GI 1E51-F025 LIMIT SWITCtl NAMCO EA17031tOO H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 OPEN POSti!ON 475 , RI 1E51-FO25 LIMIT SWITCH NAMCO EA1703ttOO H-2266 E-142 E/t5 R4D R.B. A EX M-52-1 EOO7 ! CLOSED POSITION 475 RI IESt-FO25 SOLENGID ASCO HI8320At75 H-2266 E-142 E/15 R4D R 8. A EX M-52-1 EOO7 l 475 I t RI 1E51-FO26 SOLENOID ASCO Hi8320A175 H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 ! 475 { RI IE51-FO26 LIMIT SWITCH NAMCO EA17031tOO H 2266 E-142 E/15 R4D R.8. A EX M-52-1 EOO7 l CLOSED POSITION 475 RI IE51-F026 LIMIT SWITCH NAMCO EA17031tOO H-2266 E-142 E/15 R4D R.B. A EX M-52-1 EOO7 , OPEN POSITION 475 RI IE51-F046 MOTOR OPER- LIMIT SMB-OOO-5 (1-2852 E-142 E/15 R4D R.B. A EX M-52-2 EOO7 ATED VALVE E-2324 475 RI 1E51-F059 MOTOR OPER- LIMIT SMB-OO-to H-2264 E-149 B/24 R54 R.B. A EX M-52-2 EOO7 ATED VALVE E-2326 570 RI IE51-F066 LIMIT SWITCll MAG- MPS-15 H-2267 E-147 C/22 C1 ORYWEL A EX EOO7 LOCK E-2908 593 Rt it51-NOO2 FLOW SW I T Cit BARION 145C3 OOH H-22tO E 142 E/l7 R4D R.B. A EX IH22-pot? EDO7 289A E-2848 475 RI lE51-NOO3 FLOW ROSE- 163C1561 11-2210 E-142 E/17 R4D R.B. A EX 1H22-pot 7 EOO7 TRANSMITTER MOUNT 1151DP E-2841 475 Rt IE51-NOO4 PRESS. BAILEY 163CitB6 61-2210 E-142 E/17 R4D R.O. P EX til2 2 - PO t ? EOO7 IRANSMITTER 556 E-2841 475
.PAGE lb OF 78 fl 4.0 SARGENTELUNDY
'ENOtradLnh ,
f .
,, PROJECT NUMBER 4130-05 i DATE 29 JUN 82 REVISION 006
. ZIMMER EOulPMENT OUALIFICATION 001346
. PLANT ID COMPONENT / MODEL SPEC OR E.I. DWG COL / ROW CONTAIN FLD ACT/ ADD 0588 DATA
.SY NUMBER EQUIPMENT MFR NUMBER B/M NO. W/D NO. ELEVATN IN OUT BUILD LEV PASS REV CAT. SHT.
RI IE51-NOO5 PRESS. BAILEY 163 Cit 86 H-22tO E-142 E/17 R4D R.B. P EX 1H22-pot? EOO7
. TRANSMITTER 556 E-2841 475 RI tE51-NOO6 PRESS. STATIC 145C30tt H-22tO E-142 E/17 R4D R.B. A EX 1H22-PO17 EOO7
. SWITCH 0-RING 6N-AA21 E-2841 475 DI 1E51 NOO7 PRESS. BAILEY 163 Cit 86 H-22tO E-142 E/17 R4D R.B. P EX tit 22 -PO t 7 EOO7 TRANSMITTER 556 E-2841 475 Rt IE59-NOO8 PRESS. ROSE- 1852 H-2280 E-142 E/97 R4D R.B. P EX 1H22-Pol 7 EOO7 TRANSMITTER MOUNT E-2848 475 RI IE51-NOO9 A PRESS. BARKS- 145C3046 H-22tO E-142 E/37 R4D R.C'. A EX 1H22-pot 7 EOO7 SWITCH DALE D2tt-M80SS E-2841 475 RI IE51-NOO9 8 PRESS. BARKS- 145C3046 H-22tO E-142 E/t? R4D R.B. A EX IH22-pol 7 EOO7
. SWITCH DALE D2H-M80SS E-2841 475 RI IESt-NOtO LEVEL MAGNET 159C4361 H-22tO E-142 D/15 R4D R.B. P EX E007 SWITCH -ROL 5.O-751 E-2906 475 RI IE51-NO2O PRESS. SWITCH BARKS- 159C4606 H-2210 E 14 2 L/16 R4D R.B. A EX IPX28J EOO7 DALE PtHM340SS-V E-2906 475 RI IE51-NO21 PRESS. SWITCH BARKS- 145C3046 H-22tO E-142 E/17 R4D R.B. P EX IH22-pot 7 EOO7 DALE D2H-M80SS E-2848 475 RI 1E51-NO34 PRESS. SWliCH ROBERT 163C1185 H-22tO E-142 E/17 R4U R.B. P EX fH22-pot 7 E007
-SHAW ,SP-222C 475 RI 1SC-R17tt H-22tO E-142 E/16 R4D R.B. A EX E007 E-2422 475 RI ISE-Rt7tt H-22tO E-142 E/t6 R4D R.B. A EX EOO7 E-2422 475 RI ISE-RI714 H-22to E-142 E/16 R4D R.B. A EX EOO7 E-2422 475 RI tGYS-RI711 H-2210 E - 14 2 E/16 R 4 D -R . B . A EX EOO7 E-2422 475 Rt ISYS-R1714 H-22tO E-142 E/16 R4D R.B. A EX EOO7 E-2422 475
.PAGE 16 0F 7e u)
O n . n SAHGENTaLUNDY ommo
05/09/92 CItaCI'.N ATI G AS & ELECTRIC COMPA'JY PAGE 269 RI-42 a r. . H. ZInMER hUCLEAR P0hER STATI0re Uh1T 1 REV A T
..)
JUSTIFICATION FOR INTERIF OPERATION OF: 1E51-C002 .. LOCATION':R-4D DESCRIPTION: TURBINE SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SUBSYS:N0hE SAFETY FUNCTION:NONE'FOR EVENTS CONSIDERED TURBINE & ASSOCIATED CONTROLS EXECUTE FEATURE DIV:I
~ -------EVENT------- ==-------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL ENERGIZED A LOCA ENERGIZED NOT DETERMINED B MSL/FW BREAK ENERGIZED NOT DETERMINED C RCIC BREAK ENERGIZED NOT DETERMINED D RWCU BREAK ENERGIZED NOT DETERMINED
--------- -------------------00ALIFICATION
SUMMARY
PARA' METER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D
.PERATUPE, DEG F NONE 45-148 125 218 160
)SURE, INCH-h20 hohE -0.25 15 PSIA 16.5 PSIA 16 PSIA MIDITY, %RH NONE 0-60 100 100 100 RADIATION, RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY N0hE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--------- -------------------- CLASS 1E INTERFACES -----------------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE PO'6ER: 250VDCBXMCC1A CNPTSC HOTIVE POWER: CONTROL POWER: 125VDC DIST PNLIA CONTROL POWER: SENSING SIGhAL: VARIOUS
~
EXECUTE SIGNAL: VARIOUS COMMADD SIGNAL: VARIOUS INHIBIT SIGbAL: PROCESS SIGNAL: VARIO,US PERMISSIVE SIGNAL: VARIOUS
/~N'
( A
***** CINCINHATI GAS & ELECTRIC PPOPRIETAPY Ihf0RMATION ***** .
I k
.-05/09/02 CIhC14NATI GAS & ELECTRIC COMPANY PAGE 270
- RI-47 Wh. H. ZIM'tER NUCLEAR POWER STATION UNIT 1 REV A PbTENTIAL FAILUPE FAILURE ISOLATION INTERFACE: 125VDC PNL1A COMPT 5C DEVICE: FUSES CAUSE: VARIOUS BASIS: NON-PROPAGATING /IN NON-HARSH EdVIRON FAILURE MbDE: VARIOUS ,
FAILURE EFFECT . LOSS OF TURBINE CONTROL AND INFO LIGHTS AND ANNUNCIATOR BUS. POTENT'IAL FAILURE FAILURE ISOLATION INTERFACE: 250VDC RX DEVICE: CAUSE: BASIS: FAILURE MbDE: FAILURE EFFECT: POTEBTIAL FAILUPE FAILURE ISOLATION
, INTERFACE: MCCIA COFPTSC DEVICE: FUSES ~
,JAUSE: VARIOUS BASIS: NDH-PROPAGATING /IN NON-HARSH ENVIRON FAILURE FODE: VARIOUS FAILURE EFFECT: LOSS OF TURBINE CONTROL AND INFO LIGHTS AND ANNUNCIATOR BUS.
l l POTENTIAL FAILURE FAILURE ISOLATION l INTERFACE: 125VDC DIST PNLIA DEVICE: BASIS: CAUSE: l FAILURE MODE: FAILURE EFFECT: l l ! POTENTIAL FAILURE FAILURE ISOLATION l INTERFACE: CONPI3BL DEVICE: FUSES CAUSE: VAPIOUS RASIS: NON-PROPAGATING /I!! NON-HARSH ENVIRON i FAILUBE MbDE: VARIOUS ( LURE EFFECT: LOSS OF TURBINE CONTROL AND INFO LIGHTS AND AkDUNCIATOP BUS. l
05/09/82 CINCIhNATI GAS & ELECTRIC CD/ pat.Y PAGE 271 RI-42 WF. H. ZIMMER NUCLEAR P0hEB STATION UNIT 1 REV A
..b ~
POTENTIAL FAILURL FAILURE ISOLATION INTERFACE: ANNUNCIATOR BUS DEVICE: FUSES CAUSE: VARIOUS BASIS: NON-PROPAGATING /IN NON-HARSH ENVIRON FAILURE M'DE': 0 VARIOUS FAILURE EFFECT: LOSS OF TURBINE CONTROL AND INFO LIGHTS AND ANNUNCIATOR BUS. POTENTIAL FAILUPE FAILURE ISOLATION INTERFACE: 125VDC MAIN DIST DEVICE: CAUSE: BASIS: FAILURE M'0DE: FAILURE EFFECT: i POTENTIAL FAILUBE FAILURE ISOLATIbN I INTERFACE: PNL1A COMPT 3EB DEVICE: FUSES j bAUSE: VARICUS BASIS: NON-PROPAGATING /IM i NON-HARSH ENVIRON FAILUBE MbDE: VARIOUS FAILURE EFFECT: LOSS OF TURBINE CONTROL AND INFO LIGHTS AND ANNUNCIATOR BUS. BASIS: ALL CIPCUITS ARE FUSED, AND LOSS OF CIRCUITS WILL NOT PROPAGATE TO SAFETY RELATED FUNCTIONS. NONE OF THE DEVICES ARE REQUIRED TO MITIGATE ANY LOCA CR HELB EVENT. REFEP Ei4CES : E1010/pG. RIO6, 07, 14, 15 AND M-52 SHEET owe tiITIGATIch EVENT CAPABILITY A B C D X X X l ("J' ADEOUATE INADEQUATE X I 2
t 05/09/82 CINCIhNAf1 GAS & ELECTPIC CONPANY PAGE 272 hl-43 *M. H. ZINMER NUCLEAR POWER STATION UNIT 1 REV A
)
/
JUSTIFICATION FOR INTERIM OPERATION OF: 1E51-C003 LOCATIOh R-4D DESCRIPTIdN: MOTOR SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SUBSYS:NONE SAFETY FUNCTIdN:NONE MOTOR FOR WATER LEG PUMP EXECUTE FEATURE DIV:I
~
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL DE-ENERGIZED A LOCA DE-ENERGIZED NOT DETERMINED B MSL/FW BREAK DE-ENERGIZED NOT DETERMINED C RCIC BREAK DE-ENERGIZED NOT DETERMINED D RWCU BREAK DE-ENERGIZED NOT DETERMINED
--- - --- -------------------QUALIFICATION
SUMMARY
PA8A' HETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D PERATURE, DEG F 230 45-148 125 218 160
.SSURE, INCH-h20 h0HE -0.25 15 PSIA 16.5 PSIA 16 PSIA MIDITY, %RH NONE 0-60 100 100 100 RADIATION, RADS 2.0E6 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER: AGING 175 FOR 2 WKS
--------- -------------------- CLASS 1E INTERFACES -----------------------------
--, ----- ----- INPUTS --------------- =~--------------- OUTPUTS --------------
MOTIVE PbwER: ABMCC 1A COMPT 2D MOTIVE POWER: WATER LEG PUMP C NTROL P'0WER: CONTROL TRANSFORMER CONTPOL POWER: SENSING SIGNAL: EXECUTE SIGNAL: COMMAND SIGNAL: INHIBIT SIGNAL: PROCESS SIGNAL: PERMISSIVE SIGNAL: i
* * * *
- ClaCIi.b ATI GAS & ELECTRIC PRCPRIETARY INFORMATION *****
. _ - - . _ _ _ . _ _ . . _ _ . . . _ . . _ _ . _ _ . . . _ _ _ . _ _ _ _ _ _ _ ____.__._ _ __._ . .._____ l 05/09/82 ClNCIh4ATI GAS'& ELECTRIC CohPANY PAGE 273 "a RI-43 FM. H. IIPMER NUCLEAR POWER STATION UNIT 1 REV A POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: MOTOR CONTACTORS DEVICE: NONE CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING TYPE FAILURE FAILURE [0DE: FAILS OPEN FAILUkE EFFECT: PUMP DOES NOT MOVE WATER. POTENT'IAL FAILURE FAILURE ISOLATION INTEPFACE: DEVICE: NONE C AU S E': CLOSED CIRCUIT BASIS: N N-PROPAGATING TYPE FAILURE FAILURE MbDE: FAILS CLOSED FAILURE EFFECT: PUMP DOES NOT STOP RUNNING. POTENTIAL FAILUPE FAILURE ISOLATION DEVICE: CIRCUIT BREAKER h.IflTERFACE:
,CAUSE's SHORT TO GPOuliD BASIS: ISO DEVICE IS QUALI- .
FIED FOR EVENT FAILURE MODE: SHORT TO GROUND FAILURE EFFECT: SYSTEM INOPERATIVE. POTENTIAL FAILURE FAILURE ISOLATIbN INTERFACE: CONTROL CRCT TRANSF DEVICE: NONE CAUSE: OPEd CIRCUIT BASIS: NON-FRdPAGATING TYPE FAILURE FAILURE NbDE: -FAILS OPEN FAILUR'E EFFECT: PUMP DOES NOT MOVE WATER. POTENTIAL FAILUFE FAILURE ISOLATION INTERFACE: DEVICE: FUSE CAUSE: SHORT CIRCUIT BASIS: ISO DEVICE QUALIFIED FOR THE EVENT FAILUFE vbDE: FAILS SHORTED ([ LUBE EFFECT: PUMP DOES ?!OT MOVE WATER. t
05/09/82 CIrlCI.NNATI GAS & ELECTRIC COMPANY PAGE 274 PI-43 "4
*: H. ZIMisEB NUCLEAR PohER STATION UNIT 1 REV A s s. ..AS:
LUCA AND hELB; THIS DEVICE IS NOT REQUIFED TO MITIGkTE THESE EVENTS. FAILURE WILL t.0T PROAGATE TO SAFETY EQUIPMENT.
REFERENCES:
! E1010/PG. RIOS EQ D.S. 2202 MITIGATION EVENT CAPABILITY A B C D ADE011 ATE X X X X INADEQUATE , . l Q[s) l l l l (~> l 1
05/09/82 CINCIt.ATI GAS &'ELECTPIC COMPANY PAGE 232 ID: F1-15 kP. H. ZIPMER NUCLEAR POWER STATION UNIT 1 REV A STIFICATION FOR INTEPIM OPERATION OF: 1E51-F004 LOCATION'R-4D DESCRIPTION SQLEh0ID VALVE SYSTEh REACTOR CORE ISOLATION COOLING (RI) SUBSYSth0NE SAFETY FUNCTION:C0hT. ISOL. & INTEGRITY CNTRL. (CILIC) INbFD CONDENSATE PUMP DISCHARGE ISOLATION VALVE EXECUTE FEATURE DIV:I
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL CLOSED DE-ENERGIZED A LOCA N/A NOT DETERMINED B MSL/FW BREAK N/A NOT DETERMINED C RCIC BREAK CLOSED DE-ENERGIZED NOT DETERMIhED D RFCU BREAF. N/A NOT DETERMINED
------- - ----------- -------QUALIFICATIOh
SUMMARY
---~~------------------------ PARAT1ETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENI B EVENT C EVENT D l T MPERATURE, DEG F N0hE 45-140 125 218 160 l )SSURE. INCH-620 N0iiE =0.25 15 PSIA 16.5 PSIA 16 PSIA MIDITY. %BH NONE 0-60 100 100 100 RADIATION, RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 OPEPABILITY NOhE 100 DAYS 1 DAY '1 DAY 1 DAY OTHER:
--------- --------- - ------a- CLASS 1E INTERFACES ----------------------------- --------- ----- IhPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: 125VDC MANDIST PNLIA MOTIVE POWER: N/A CCNTROL f0*iEP: N/A CONTROL POWER: N/A SEhSING SIGNAL: h/A EXECUTE SIGNAL: LS-ID LS-IC COMMAPD SIGNAL: 1E51-K22 OPEN 1E51-K40 CLOSED INHIBIT SIGNAL: 1E51-K40 OPE.1 PPCCESS SIGNAL: N/A PEFt4ISSIVE SIGNAL: N/A 4)
-[ ***** cit.CINt;ATI GAS & ELECTRIC PROPRIETARY INFORMATION *****
05/09/82 CIFCIfdN ATI GAS & ELECTRIC COMPANY PAGE 233 I : HI-15 dh. H. ZIC4ER NUCLEAR power STATION UhlT 1 REV A A .) POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: E51A-F18 , DEVICE: NONE CAUSE: FUSE (F-6 10A) FAILS BASIS: NON-PROPAGATING FAILURE M'0 dei FAILS CLOSED FAILURE EFFECT: VALVE OPERATION AND POSITIOh INDICATION LOST = VALVE FAILS CLOSED. POTENTIAL FAILURE FAILURE ISOLATION INTEPFACE: LIGHT G-2 DEVICE: NONE CAUSE: BULB FAILS BASIS: NON-PROPAGATING FAILUBE MbDE: hu EFFECT FAILUPE EFFECT: VALVE POSITION INDICATION ONLY IS LOST. , POTENTIAL FAILURE FAILURE ISOLATION l INTEPFACE: LIGHT P-2 DEVICE: NONE AUSE: BULB FAILS BASIS: NON-PROPAGATING l FAILURE MbDE': do EFFECT FAILURE EFFECT: VALVE POSITION INDICATION ONLY IS LOST. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: K-40 CONTACTS 7, 8 DEVICE: NONE CAUSE': SHORT TO GROUND BASIS: UNGROUNDED DC SYSTEM IS UNAFFECTED FAILURE N'DE: 0 .NO EFFECT FAILURE EFFECT: NCNE. POTENTIAL FAILUF6 FAILUPE ISOLATION INIERFACE: DEVICE: NOGE CAUSEi CPE:4 CIRCUIT BASIS: .NON-PPOPAGATING FAILURE MODE: FAILS CLOSED (K/'bubEEFFECT: VALVE LOSES OPEN PER:4ISSIVE SIGH AL FROM K-40 REL AY
- VALUE WILL CLOSE.
(
~.
l
. . . - ~ .
05/09/82 CINCIt.NATI GAS & ELECTRIC COMPANY PAdE 234
*M. H. ZIMMER huCLEAR PO*CH STATION UNIT 1 BEV A I t hl.15
)
P0iENTIAL FAILURE FAILUPE ISCLATION INTERFACE: DEVICE: NONE CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE v0DE: FAILS AS IS FAILURE EFFECT: VALVE HAS CONSTANTO' PEN PERMISSIVE SIGNAL WILL NOT CLOSE WHEh K 40 RELAY DE-ENERGIZES. BASIS: THIS DEVICE IS NOT ItiVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY F U t1 C T I O N , AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT. REFEFENCES: ' M-52 SHEET ONE OF T'40 REV. W, E1010/PG. 5101 REV. AB, E1010/PG. RIO7 REV.h. E1010/PG. RIl0 PEV. K EQ'D.S. X510, X520, X530, X540, X550 l $) MITIGATION A EVENT B D l CAPABILITY C ! ADEOUATE N f* X N l INADEQUATE l I 4 c: U.
05/09/d2 CIhCINNATI GAS & ELECTRIC COMPANY PAGE 244 ID. RI-19 WP. H. ZI.dMER tiUCLEAR POWER STATION UNIT 1 REV A A> JUSTIFICATIOh FOR INTEHIM OPERATION OF 1E51-F004 LOCATIbN R-4D DESCRIPTIbN: LIMIT SWITCH LS/ID
~
SYSTEM: REACTOR CORE ISOLATI0h COOLING (RI) SUBSYS:NO'NE . SAFETY FUNCTIbN: CbNT. ISOL. & INTEGRITY CNTRL. (CI&IC) INBOARD COr.0EtiSATE PUMP DISCHAPGE ISOLATION VALVE SENSING FEATURE DIV:I
--- - ~-EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL DE-ENERGIZED A LOCA W/A NOT DETERMINED B MSL/FW BREAK N/A NOT DETERMINED C RCIC BREAK DE-ENERGIZED NOT DETERMINED D RtCU BREAK N/A NOT DETERMINED
--------- -------------------QUALIFICATICM
SUMMARY
a-e----------
PARAMETEp -----DEMONSTkATED----- ----------------REQUIRED---------------- i EVENT A EVENT B EVENT C EVENT D l PER?TURE, DEG F NOhE 45-148 125 218 160 l ' SURE, INCH-H2O NONE -0.25 15 PSIA 16.5 PSIA 16 PSIA IDITY, %RH NOME 0-60 100 100 100 RADIATIO!J. RADS NCNE 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--- ----- --------- - -------- CLASS 1E INTERFACES ----------------------------- --------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE P'WER: 0 N/A MOTIVE POWER: N/A l CONTROL PbWER: 125VDC MAINDST PNL1A CChTRdb P0hER: N/A SENSING SIGNAL: VALVE POSITION EXECUTE SIGNAL: ESERGIZE OPEN LIGHT l COMHAND SIGNAL: h/A INHISIT SIGNAL: N/A-PRCCESS SIGNAL: N/A PEERISSIVE SIGNAL: N/A k' ***** CIdCIONATI GAS & ELECTRIC Pb PRIETARY INFORMATION *****
.. .E I
0$/09/82 CINCIhNATI GAS & ELECTRIC COMPANY PAGE 245 .) 4 ID: BI-19 'hA.yh. ZIMdEH tlUCLEAR PUnER STATIO!! UNIT 1 REV A j 9)POTEaTIAL FAILUbE FAILURE ISOLATION INTERFACE: LE.IO CONTACT DEVICE: N0hE CAUSE: SHORT TO GROUND BASIS UNGROUNDED DC SYSTEM NO EFFECTED FAILUBE M6DE: NO EFFECT FAILURE EFFECT: NONE. PDTENTIAL FAILURE . FAILURE ISOLATION INTERFACE: DEVICE: t10NE CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE PbDE: CONTACTS FAIL CLOSED FAILUPE EFFECT: VALVE INDICATES OPEN AT ALL TIMES. POTEhTIAL FAILURE FAILURE ISOLATION
,_ INTERFACE: .
DEVICE: NONE ( ss),CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGA*ING v
- FAILURE P'0DE'
- CONTACTS FAIL OPEN ,
FAILURE EFFECT: LOSS OF OPEN VALVE POSITON INDICATION. BASIS: THIS DEVICE IS NOT INVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY FUNCTION, AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTI'ON CIRCUIT. REFEPENCES: M-52 SHEET ONE OF Ta0 REV. W, E1010/PG. RIO7 PEV. M E0 D.S'. X520, X530, X540, X550, X560 1 MITIGATfGil EVENI CAPABILITY A B C D l I'l.' ADEOUATE 6 h X N
'd
' INADEQUATE
( (
t . 05/09/92 . cit:CINiiATI GAS & ELECTAIC CDPPANY PAGE 248 PI-20 w !* . H. ZIPMER NUCLEAR POnER STATION UNIT 1 REV A l s
)
JUSTIFICATION FOR INTERIM OPERATIOri 0F: 1E51-F004 LOCATION'9-4D DESCRIPTION:LIftIT SWITCH LS/IC SYSTE4 REACTOR CORE ISOLATION COOLING (RI) SUBSYS:NONE SAFETY FUNCTION: CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) . INBOARD C0tvDENSATE PUMP DISCHARGE ISOLATI0fi VALVE SENSING FEATURE DIV:1
-------EVENT------- . ==-------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NOHMAL EtiERGIZED A LOCA N/A NOT DETERMINED B HSL/FW BREAK N/A fl0T DETERMINED C PCIC BREAK ENERGIZED NOT DETERMIllED D RUCU BREAK h/A NOT DETERMINED
--- ----- ----------- -------0UALIFICATION
SUMMARY
a-------------------
P AR A'P.ETER -----DEh0NSTBATED----- ----------------REQUIRED---------------- EVEhT A EVENT b EVENT C EVENT D MPERATURE, DEG F NONE 45-148 125 218 160
,'S S U R E , IliCH-H2O N 0ivE -0.25 15 PSIA 16.5 PSIA 16 PSIA l MIDITY, %QH NO JE 0-60 100 100 100 RADIATION, RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY t.0iiE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--------- --------- ---------- CLASS 1E INTERFACES -----------------------------
--------- ----- It4 PUTS --------------- ----------------- OUTPUTS --------------
MOTIVE PdWER: MOTI)E POWER: N/A CONTROL PbWEP: 125VDC MAINDST PNLIA C0flTROL POWER: N/A SElvSING SIGNAL: VALVE POSITION EXECUTE SIGNAL: ENERGIZE CLSD LIGHT COMMAND SIGNAL: N/A INHJ. BIT SIGri AL: N/A. PROCESS SIGNAL: N/A PEPHISSIVE SIGNAL: N/A ("1
'/
'- ***** CINCINNATI GAS & ELECTRIC PROPPIETARY INFORMATION *****
. . . - .. --4. ._--e. ...
4.= - .
05/09/82 cit.CINHATI GAS & ELEC1RIC CUFPANY PAGE 249 in' HI-20 hh. H. ZIdMER NUCLEAR PO4EP STATIOb UNIT 1 REV A POTENTIAL FAILUPE FAILURE ISOLATION INTERFACE: LS-IC DEVICE: NONE CAUSE: SHORT TO GROUND BASIS: UNGROUNDED DC SYSTEM IS UNAFFECTED FAILURE 80DE: NO EFFECT FAILURE EFFECT: NONE. POTENTIAL FAILUPE - FAILURE ISOLATION INTERFACE: DEVICE: NONE CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE P' ODE: C0tTACTS FAIL CLOSED FAILURE EFFECT: VALVE INDICATES CLOSED AT ALL TIMES. POTEhTIAL FAILUBE FAILUPE ISOLATION OPEt1 CIRCUIT DEVICE: NONE
,EAUSE: CONTACTS FAIL OPEN BASIS: il0N-PROPAGATING 9sINTERFACE:
FAILUhE MdDE: CONTACTS FAIL OPEN FAILdPE EFFECT: LOSS OF CLOSED VALVE POSITION INDICATIOri. BASIS: THIS DEVICE IS h0T IhVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY FUNCTION, AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT. REFEPEMCES: M-52 SHEET OnE OF T'.10 REV. h, E1010/PG. RIO7 REV. M EQ D.S. X520, X530, X540, X550, X560 MITIGATION EVE!!T CAP 3PILITY A B C D i f ALEOdATE N t8 X U INADEQUATE (
05/09/82 CloCIN.ATI GAS & ELECTRIC COMPANY PAGE 235 HEV A 10: RI-16 nM. H. IIr.MER NUCLEAR PO'eER STATION UNIT 1 JUSTIFICATION FOR INTERIM OPEBATION OF 1ES-F005 LOCATION R-4D DESCRIPTION:50LENDIC VALVE SYSTEh! PEACTOR COPE ISOLATION COOLING (RI) SUBSYS:NONE SAFETY FUNCTION CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) 00TBRD CONDENSATE PUMP OISCHARGE ISOLATION VALVE EXECUTE FEATUPE DIV:II
--- --eEVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL OPEN EhERGIZED N/A NOT DETERMINED A LOCA B MSL/F'd BREAK N/A NOT DETERMINED C RCIC BREAK OPEi4 ENERGIZED NOT DETERMINED D RWCU BREAK N/A NOT DETERMINED
-------- l----- -------------QUALIFICATION SUM *ARY-----------------------------
PARAMETEn -- --DEMONSTRATED----- ==--------------REQUIRED---------------- EVEbT A EVENT B EVENT C EVENT D TEMPEPATUPE, DEG F NONE 45-148 125 218 160 g3SURE, INCH-H2O NONE -0.25 15 PSIA 16.5 PSIA 16 PS.IA NOME 0-60 100 100 100 K.4IDITY. %PH 1.71E6 RADIATION, RADS NONE 6.32E6 1.71E6 1.71E6 OPERABILITY NOME 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
------- ; ----- -------------- CLASS 1E INTERFACES ----------------------------- --------- ----- INPUTS --------------- ===-----a-------- OUTPUTS --------------
l MOTIVE P'0WER': 125VDC MANDIST PNL1B MOTIVE POWER: N/A l CONTROL POWER: N/A CONTROL POWER: N/A i SEhSING SIGNAL: N/A l '
- EXECUTE SIGNAL: LS/IO LS/IC COMMAND SIGNAL: 1E51-K35 CLOSED l INHIBIT SIGJAL: 1E51-K35 OPE:I PROCESS SIGNAL: N/A PERMISSIVE SIGNAL: N/A 1
(^/ s ***** CISCINhATI GAS & ELECTRIC PROPRIETARY INFORMATION *****
. (
05/09/82 CIr:CII..J ATI G AS & ELECTRIC CO.MPANY PAGE 236 kh. H. ZIrhER hUCLEAR POWER STATION UNIT 1 REV A RI-16 ' POTENTIAL FAILURE . FAILUPE ISOLATION IhTEHFACE: K-35 CONTACTS 2, 8 DEVICE: NONE - CAUSE's SHORT TO GROUND BASIS: UNGROUNDED DC SYSTEM NOT AFFECTED FAILURE MbDE: NO EFFECT FAILURE EFFECT: NONE. POTENT'IAL FAILURE FAILURE ISOLATION INTERFACE: DEVICE: h0HE CAUSE': - OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE PdDE: FAILS CLOSED FAILUPE EFFECT: VALVE LOSES OPEh PERMISSIVE SIGNAL FRdM K-35 RELAY - VALVE WILL CLOSE. . . POTEbTIAL FAILUPE FAILURE ISOLATION I.* T ERF ACE : DEVICE: NONE AUSE: 5110RT CIRCUII BASIS: NON-PROPAGATING FAILURE ydDE: FAILS AS IS FAILURE EFFECT: VALVE HAS C0isSTANT OPEN PERdISSIVE SIGNAL - WILL NOT CLOSE hMEN K-35 RELAY DE-ENERGIZES. POTENTIAL FAILURE FAILURE ISOLATIdN INTERFACE: E51A-F30 DEVICE: NONE CAUSE: FUSE (F-6 10A) FAILS BASIS: NON-PROPAGATING FAILUPE MODE: FAILS CLOSED FAILURE EFFECT: VALVE OPERATIch IS LdST, VALVE FAILS CLOSED. POTENTIAL FAILURE FAILUPE ISOLATI0rt INTERFACE: G-2 DEVICE: NOME CAUSE: BULB FAILS BASIS: NON-PROLAGATING FAILUFE MbOE: LO EFFECT ILUPE EFFECT: VALVE POSITION INDICATION ONLY, IS LOST.
05/09/02 cit Clr.ie Ala GAS & ' ELECTRIC C0r4PANY PAGE 237 ID: PI-16 WM. h. ZI"MEP. huCLEAR POWER STATION UNIT 1 REV A POTEdTIAL FAILUPE FAILURE ISOLATION ' INTERFACE: P.2 DEVICE: NONE CAUSE: BULB FAILS BASIS: h0N-PROPAGATING FAILURE P'DE: 0 NO EFFECI
~
FAILURE EFFECT: VALVE POSITION INDICATION ONLY IS LOST. BASIS: THIS DEVICE IS NOT INVOLVED IN THE CIRCUIT USED FOR THE SYSIEe, SAFETY FUNCTION AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT.
REFERENCES:
M-52 SHEET ONE OF TWO REV. W, E1010/PG. RIO7 REY.M, E1010/PG. RIO2 ' REV.N, E1010/PG. RIl0, REV. K s' MITIGATIbt: EVENT CAPABILITY .A D C D ADEOUATE N N X N INADEQUATE e O
, t
) J 05/09/02 CINCINNATI GAS & ELECTRIC COMPANY PAGE 250
- PI-21 WM. H. ZIMMER NUCLEAR P0eER STATION UNIT 1 REV A
)
JUSTIFICATION FOR INTERIM GPERATION OF: 1E51-F005 LOCATION:5-40 DESCRIPTION: LIMIT SWITCH LS/IO SYSTEM: PEACTOR COPE ISOLATI0h COOLING (PI) SUBSYS:NOhE SAFETY FUNCTIO (:C0hT. ISOL. & INTEGRITY CNTRL. (CI&IC) OU1 BOARD CONDENSATE PUMP DISCHABGE ISOLATION VALVE SEDSING FEATURE DIV:II
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIltE---
TO FAILURE h0R9AL EMEPGIZED A LOCA N/A NOT DETERMINED B MSL/FW BHEAK N/A NOT DETERMINED C RCIC BREAK ENERGIZED DOT DETERMINED D RWCU BREAK N/A h0T DETERFINED
--------- ----------- -------QUALIFICATION
SUMMARY
PAPAMETER -----DEM0dSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D MPERATUPE, CEG F N0 tie 45-148 125 218 160 ASSUPE, INCH-H2O N0 rlE -0.25 15 PSIA 16.5 PSIA 16 P.SIA
.UHIDITY. %RH t10NE 0-60 100 100 100 RADIATION. RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--------- ----------- -------- CLASS 1E INTERFACES -----------------------------
--- --- - ----- INPUTS --------------- ----------------- OUTPUTS ----------~---
MOTIVE power: N/A MOTIVE POWER: N/A COPTROL FOiEP: 12SVDC MAINDST PNL18 CONTROL PodER: N/A SESSING SIGilAL: VALVE POSITION
~
EXECUTE SIGNAL: ENERGIZE OPEN LIGHT l COMPAND SIGNAL: N/A INHIBIT SIGNAL's N/A PRCCESS SIGNAL: N/A PERMISSIVE SIGNAL: N/A
~ /N
('" J'
***** CINCI:nJ ATI G AS & ELECTRIC PRCPRIET ARY I A FORb' ATION *****
05/.09/82 CII:CIONATI GAS & ELECTAIC COMPANY PAGE 251 ID: BI-21 WM. H. ZIMMER NUCLEAR PONER STATION UNIT 1 REV A T P TE4TIAL FAILURE FAILURE ISOLATION I f.TER F ACE : LS-IC DEVICE: .401E CAUSE: $RORT TO GROUND BASIS: 01 GROUNDED DC SYSTEM IS UNAFFECTED FAILUME ybOE: 40 EFFECT FAILURE EFFECT: NONE. POTEtiTIAL FAILURE FAILURE ISOLATI0ri INTERFACE: DEVICE: NONE CAUSE: SJGPT CIRCUIT BASIS: NON-PROPAGATING FAILURE i ODE: CONTACTS FAIL CLOSED FAILURE EFFECT: VALVE It!DICATES OPEN AT ALL TI?iES. POTENTIAL FAILUBE FAILURE ISOLATION INTEPFACE: DEVICE: fl0NE OPEN CIBCUIT RASIS: NON-PROPAGATING {}CAUSE: FAILURE yhDE: CouTACTS FAIL OPEN FAILURE EFFECT: LCSS OF OPEN VALVE POSITION I h 0 IC AT I O'I . . BASIS: THIS DEVICE IS NOT IhVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY FUNCTION, AND FAILUBE WILL NOT PROPAGATE TO THE SAFETY FUNCTIdN CIRCUIT.
REFERENCES:
.t-52 SPEET ONE OF TWO FEV. W, E1010/PG. RIO7 REV.9 EQ D.S. X520, X530, X540, X550, X560 MITIGATION EVENT CAPn81LITY B C 0 ACE 0 HATE N 4 X N
@.- I'4 ADEQU ATE
_ _ . _ _ . . _ . - _ - _ . . . . - . . _ _ _ _ _ _ . _ . _ . _ _ _ _ . . . _ _ _ _ _ . _ _ . . 1
) '
l 1 05/09/82 CINCINNATI GAS & ELECTRIC COMPANY PAGE 252:) ID: RI-22 WM. H. ZINMER NUCLEAR P0nER STATION UNIT 1 REV A ' JUSTIFICATIQU FOR IPTERIM OPERATION OF: 1E51-F005 LOCATIOt!':R-40 DESCFIPTION:LINIT SWITCH LS/IC SYST E.% : PEACTOR CORE ISOLATION COOLING (RI) SUBSYS:NONE SAFETY FUNCTION:C0 tit. ISOL. & INTEGRITY CNTRL. (CI&IC) OUTBOARD CONDEMSATE PUMP DISCHAr.GE ISOLATION VALVE SENSING FEATURE DIVIII
--=----EVEhT------- ---o-----DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE NORMAL DE-ENERGIZED A LOCA N/A NOT DETERMINED B MSL/FW BREAK N/A HOT DETERMINED C RCIC BREAK DE-ENERGIZED NOT DETERMINED 0 RbCU BREAK N/A tiOT DETERMINED
------- ----------- -------QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F tJONE 45-148 125 218 160
,ESSb8E. INCH-H2O NONE -0.25 15 PSIA 16.5 PSIA 16 PSIA
("[dMIDITY. (s %RH NotlE 0-60 100 100 100 RADIATION. RADS t.O N E 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 OAY 1 DAY OTHER:
- - -- - - - - - - - - - - - - - - - - - - ~ ~ ~ - - - C L A S S 1 E I ri T E R F A C E S - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
--------- ----- ItiPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: MOTIVE POWER N/A CouTROL POWER: 125VDC MAINDST PNL1B CONTROL POWER: h/A SEhSING SIGNAL: VALVE POSITION EXECUTE SIGNAL: ENERGIZE CLOSE LIGHT LIGHT CorMAND SIGNAL: N/A l INHIBIT SiGtJ AL: N/A PROCESS SIGNAL: N/A PERMISSIVE SIGNAL: N/A (~~) , ke' ***** CINCI4NATI GAS & ELF.CTRIC PDCPWIETARY IHFOR.v ATIO:4 *****
- + -
05/09/82 CINCIslNATI GAS & ELECTRIC C0tiPANY PAGE 253, ID: 8I-22 aM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A r'} I TENTIAL FAILURE FAILURE ISOLATION INTERFACE: LS-IC . DEVICE: NOME CACSE: SHORI TO GROUND BASIS: UNGROUNDED CC SYSTEM IS UNAFFECIED FAILURE F0DE: f40 EFFECT s FAILUPE EFFECT: Not!E. POTENTIAL FAILURE FAILURE ISOLATIOt! It;TERFACE: DFVTFE: N0dE CAUSE: SHORT* CIRCUIT BASIS: NON-PROGATING FAILURE MODE: Cor4 TACTS FAIL CLOSED FAILURE EFFECT: VALVE INDICATES CLOSED AT ALL TIMES. POTENTIAL FAILUPE FAILURE ISOLATION INTEFFACE: DEVICE: N0?iE
. .N CAUSE: OPEd CIRCUIT BASIS: NO:I-PROPAGATING ILURE MODS: CONTACTS FAIL OPEd FAILUPE EFFECT: LOSS OF CLOSED VALVE POSITION INDICATION.
BASIS: THIS DEVICE ISNOT INVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY FuaCTION, AND FAILURE WILL NOT PPOPAGATE TO THE SAFETY FUNCTIOff CIBCUIT.
REFERENCES:
d-52 SHEET ONE OF Tho 8EV. W, E1010/PG. RIO7 BEV.M EQ D.S. Xb20, X530, X540, X550, X560 MITIGATION EVENT CAPAPILITY A B C D
.j ADEOUATE N N X tJ INAnrQUATE f
,-*\e-m.m -m e e-- .- .o .n. c e ,em - .x+-- - -
05/09/82 CINCIbNATI GAS & ELECTPZC COMPANY PAGE 438 ID: RI-17 he. H. ZINFER NUCLEAR POWEP STATION UNIT 1 REV A JTIFICATION FOR Ir4ERIM OPERATION OF 1E51-F025 L CATIONiP-4D DESCRIPTION:50LEFOID VALVE SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SUBSYS NONE SAFETY FUNCTIdN CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) STEAM LINE DRAIN INBOARD ISOLATION VALVE EXECUTE FEATURE DIV:I
---EVENT---==-- ==-------DEVICE STATUS--------- ---ESTIMATED TIME---
- TO FAILURE NdRMAL OPEN ENERGIZED A LOCA h/A NOT DETERMINED B HSL/FW BREAK h/A NOT DETERMINED C RCIC BREAK CLOSED DE-ENERGIZED NOT DETERMINED D RdCU BPEAK h/A NOT DETERMINED
..........-.......--...-..---QUALIFICATION SUMAARY-----------------------------
PARAhETEp -----DEMONSTRATED----- ----------------REQUIhED---------------- EVEhT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F NONE 45-148 125 218 160 lSSURE, INCH-H2O NONE -0.25 15 PSIA 16.5 PSIA 16 PSIA MIDITY, %BH NOhE 0-60 100 100 100
.0 A1 TI0t , RADS NOt?E 6.32E6 1.71E6 1.71E6 1.71E6 OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
____-.............-...-------- CLASS 1E INTERFACES -----------------------------
------- - ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTI's E POWER: 125VDC MAINDST PNL1A HOTIVE POWER: N/A CONTBOL EbHEpi CONTPOL POWEF: N/A SENSIDG SIGNAL: N/A EXECUTE SIGNAL: LS/IC LS/ID COMP Ai4D SIGN AL: 1E51-K40 CLOSED INHISIT SIGr.AL: 1E51 .<40 OPEN PROCESS SIGNAL: N/A PEPFISSIVE SIGNAL: N/A
***** CI'iCI!;NATI GAS & ELECTRIC PROFBIETARY INFORF.ATI0tl *****
mm -mm.- e
- w*==~-w <>e -
e o m- ma m m- - - -
05/09/82 - CINCINNATI GAS & ELECTFIC CuaPAt1Y PAGE 239 l ID: hI-17 wh. H. ZIMMER tJUCLEAR P0hER STATION UNIT 1 REV A
)
.' E 4TIAL FAILUPE FAILUPE ISOLATION I'1TEPF ACE : K-40 CONTACT 5, 6 DEVICE: NONE CAUSE' SHORT TO GROUND BASIS: UNGROUNDED DC SYSTEM FAILURE MbDE': NO EFFECT FAILURE EFFECT: NONE.
POTENTIAL FAILURE FAILURE ISOLATION IhTERFACE: , DEVICE: NONE CAUSE': OPEu CIRCUIT BASIS: NON-PROPAGATING FAILURE M'0DE: FAILS CLbSED FAILURE EFFECT: VALVE LOSES OPEh PEPMISSIVE SIGNAL FROM K-40 VALVE FAILS CLOSED. . . POTENTIAL FAILURE FAILURE ISOLATION
.3 IhTERTACE:
DEVICE: "ONE i
;CAUSE: SH0hT CIRCUIT BASIS: NON-PROPAGATING i ILURE MbDE: FAILS AS IS FAILURE EFFECT: VALVE HAS CONSTANT OPEN PERMISSIVE SIGNAL - WILL NOT CLOSE WHEN K-40 RELAY IS DE-ENERGIZED.
POTENTIAL FAILUPE FAILURE ISOLATION If;TERF ACE: E51A-F12 DEVICE: NONE CAUSE': FUSE (F-4 10A) FAILS BASIS: NON-PROPAGATING FAILURE MbOE': FAILS SHUT FAILURE EFFECT: VALVE OPEPATION IS LOST, VALVE FAILS CLOSED. POTEbTIAL FAILUPE FAILURE ISOLATI0a IhTERFACE: G-2 DEVICE: NONE CAUSE: BULB FAILS BASIS: NON-PROPAGATIAG FAILUPE MbDF: no EFFECT
) 2 LURE EFFECT: VALVE POSITIOf; INDICATICN ONLY, IS LOST.
]
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05/09/52 cit 1CIhNATI GAS & ELECTPIC COMPANY PAGE 240 ID: F.I-17 ab. H. IIPER t>UCLE AR P0h EF STATION U?'Il i REV A
,3 NTIAL FAILURE FAILURF, ISOLATION INTERFACE: P-2 DEVICE: NONE CAUSE: BULB FAILS BASIS: h0N-PROPAGATING FAILURE MdDE's NO EFFECT .
FAILURE EFFECT: VALVE POSITION INDICATION OfiLY, IS LOST. BASIS: THIS DEVICE IS h0T INVOLVED Ii1 THE CIRCUIT USED FOR THE SAFETY SYSTEM FUhCTION A?.'D FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT.
REFERENCES:
N-52 SHEET OnE OF T*40 REV. h, E1010/PG. FIO1 REY. AB, E1010/PG. RIO7 RFV. M, E1010/PG. RIl0 REV. K EQ D.S. X510, X520, X530, X540, X550 ( MITIGATION EVENT
. CAPABILITY A B C D ADEOUATE N N X N INADEOUATE O .
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05/09/92 CIllCINNATI GAS & ELECTRIC COMPANY PAGE 254 ID: RI-23 WM. H. ZIMMER NUCLEAR POWER STATI0fl UNIT 1 REY A (lDISTIFICATIOf; FOR INTERIM DPERATION OF: 1E51-F025 LOCATIdt.:g-4D DESCRIPTION:LII-IT SdITCH LS/IO SYSTEM: REACT R CORE ISOLATI0h COOLING (RI) SUBSYS:NONE SAFETY.FUNCTIdN': CONT. ISCL & INTEGRITY CNTRL. (CI&IC) INBOARD STEAM LINE DPAIN ISOLATION VALVE SENSING FEATURE DIV:I
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
TO FAILURE h0RMAL ENERGIZED A LOCA N/A NOT DETERMINED B MSL/FW BBEAK N/A NOT DETERMINED C PCIC BPEAK ENERGIZED NOT DETERMINED D RWCU BPEAK N/A NOT DETERMINED
--------- -------------------00ALIFICATION SUaMARY-----------------------------
PARAMETFR -----DEMOWSTRATED----- ==--------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D T E.d P E R A T U R E , DEG F NONE 45-148 125 218 160
, ESSURE, INCH-H2O NONE -0.25 15 PSIA 16.5 PSIA 16 PSIA (3'JMIDITY. %RH NO sE 0-60 100 100 100' g jiDIATION, RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 UPERABILITY N ote E 100 DAYS 1 DAY 1 DAY 1 DAY OTHEF:
--------- -------------------- CLASS 1E INTEPFACES -----------------------------
--------- - --- INPUTS --------------- ----------------- OUTPUTS --------------
NOTIVE P'0WER: N/A MOTIVE PdWER: N/A C0hTPOL 50WER: 12SVOC MAINDST PNL1A
~El4 SING SIGNAL: VALVE POSITION i
EXECUTE SIGNAL: ENERGIZE OPEN LIGHT COMMA!!D SIGNAL: N/A INHIBIT SIGNAL': N/A l PRCCESS SIGNAL: N/A ! PERMISSIVE SIGNAL: N/A
***** CINCINNATI GAS & ELECTRIC PPOPPIETARY INFORMATI0h *****
i _. _ - __ _ _ __ _ .__. _ . . _ _ -- - - - - .- - -- --
I 05/09/02 - CINCINNATI-GAS & ELECTRIC COMPA!!Y PAGE 255 ID: RI.23 WM. H. ZIMMER NUCLEAR F0WER STATI0rl UNIT 1 'R E V A T6hTIAL FAILURE FAILURE ISOLATION INTERFACE: LS.IO DEVICE: NONE CAUSE: SHORT TO GROUND PASIS: UNGROUNDED DC SYSTEM IS UNAFFECTED FAILURE vbOE: NO EFFECT FAILURE EFFECT: NONE. POTEriTIAL FAILURc rAILUPE ISOLATION INTERFACE: , DEVICE: NONE CAUSE: SHORT CIRCUIT SASIS: tiart= PROPAGATING FAILURE MhDE': ColiTACTS FAIL CLOSED . FAILURE EFFECT: VALVE INDICATES OPEN AT ALL TIMES. POTENTIAL FAILURE FAILURE ISOLATION
~ INTERFACE: DEVICE: Il0NE
[ 'i C AUSE's OPEfJ CIRCUIT BASIS: +104. PROPAGATING
'( LILUBE MODE: CONTACTS FAIL OPEN FAILURE EFFECT: LOSS OF OPEN VALVE POSITION INDICATION.
BASIS: TilIS DEVICE IS Iv0T INVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY FUNCTION, AND FAILURE wILL NOT PROPAGATE TO THE SAFETY l FUNCTIhN CIRCUIT.
REFERENCES:
M.52 SHEET OME OF ToO REV. W, E1010/PG. PIO7 REV. M EQ D.S. X520, X530, X540, X550, X560 MITIGATIhN EVENT CAPABILITY A B C 0 _f ADEOUATE N N X N
,- INADEQUATE m
* - - * * - - . e%* . ..=,,w . - - .
t --< . ,, - _ . . . , ,_._,-..,.m7 ,, - - , . - . ~ . _ ,..._.c..,,,,-._w , -,_ .c.,.m _, ,
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05/09/82 CINCINNATI GAS & ELECTRIC COMPANY ' PAGE 256 ID: BI-24 WM. H. ZIMMER NUCLEAR POWER STATION UlfIT 1 REV A f( jfSTIFICATION h]' . FOR ItiTERIH OPERATION OF: 1E51-F025 LOCATION':R-4D DESCRIPTION LIMIT SWITCH LS/IC SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SU6SYS:hoteE - SAFETY FUNCTION: CONT. ISOL. & INTEGRITY CNTPL. (CI&IC) INBOARD STEAM LINE DRAIN ISOLATION VALVE SENSING FEATURE DIV:I
-------EVENT------- ---- -----D EV IC E ST A T U S --------- ---ESTIMATED TIME---
TO FAILURE NORMAL DE-ENERGIZED A LOCA N/A NOT DETERMINED B MSL/FW BREAK h/A , NOT DETERMINED C PCIC BREAK DE-ENERGIZED NOT DETERMINED D RFCU BPEAK h/A NOT DETERMINED
------- - -----------.-------0UALIFICATIOh
SUMMARY
~~---------
PARAMETER ==---DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT S EVENT C EVENT D TEuPERATURE, DEG F NONE 45-148 125 218 160 i ' ESSURE. IPCH-H2O NONE -0.25 15 PSIA 16.5 PSIA 16 PSIA 91DITY. %RH NONE 0-60 100 100 100'
%DIATION. RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6 PEPABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OThER:
--- - --- ----------- -------- CLASS 1 E Ill T E R F AC ES -----------------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER': N/A MOTIVE POWER: N/A CONTROL POWER: 125VDC MAINDST PNL1A
- CCNTROL POWER: h/A SENSING SIGhAL: VALVE POSITION EXECUTE SIGNAL: ENERGIZE CLSD LIGHT COMMAND SIGNAL: N/A INHIBIT SIGNAL: N/A PROCESS SIGNAL: N/A I
l PERMISSIVE SIGNAL: N/A
/~ ***** CINCIt4hATI GAS.& ELECIRIC PROPRIETARY INFORPATION *****
i
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05/09/02 CINCINNATI GAS &' ELECTRIC COMPANY PAGE 257 ID: RI 24 WH. H. ZIMMER NUCLEAR POWER STATIOil UNIT 1 REV A r}
'TENTIAL FAILURE FAILURE ISOLATION If4TERFACE: LS.IC DEVICE: NONE CAUSEi SHORT TO GROUND BASIS: Ut; GROUNDED DC SYSTEM IS UNAFFECTED FAILURE .4h0E h0 EFFECT FAILURE EFFECTi NONE.
POTEtiTIAL FAILURE FAILURE ISOLATION INTERFACE: , DEVICE: NONE CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE NhDE: C0f* TACTS FAIL CLOSED . FAILURE EFFECT: VALVE INDICATES CLOSED AT ALL TIMES. POTEteTIAL FAILUBE FAILURE ISOLATION II;TERF ACE: DEVICE: NONE CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING
.ILURE MdDEi CONTACTS FAIL OPEN FAILURE EFFECT: LOSS OF CLOSED VALVE POSITION INDICATION.
BASIS: THIS DEVICE IS NOT' INVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY FUNCTION, AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTIdN CISCUIT. l R EFEREtlCES : I 8-52 SHEET ONE OF TWO REY. n, E1010/PG. RIO7 REV. M l EQ D.S. X520, X530, X540, X550, X560 MITIGATION EVENT CAPABILITY A B C D
, .......... .............v
, ) ADE00 ATE N N X i. l INADr0UATE (J~l
\
l l
05/09/62 CluCINNATI GAS &-ELECTRIC COMPANY PAGE 241 ID: PI-19 aM. H. ZI ~.4 E R NUCLEAR POWER STATION UNIT 1 REV A fl) I IFICATION T FOR INTERIM OPEFATION OF: 1E51-F026 , LOCAIIci:P-4D DESCRIPTION:SQLENCID VALVE SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SUBSYS:NONE SAFETY FUNCTION: CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) STEAM LIhE DRAIh OUTBOARD ISOLATION VALVE EXECUTE FEATURE DIV II
-------EVENT------- ---------DEVICE STATUS--------- ---ESTIMATED TIME---
NORMAL OPEN ENERGIZED A LOCA N/A NOT DETERMIhED B MSL/FW BREAK N/A . NOT DETERMINED C RCIC BPEAK CLOSED DE-ENERGIZED NOT DETERMINED D PWCU BPEAK N/A NOT ' ~~RMINED
--------- -------------------QUALIFICATION SUMMAFY-----------------------------
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F NOHE 45-140 125 218 160 P 3 SUPE, INCH-H2O N0bE -0.25 15 PSIA 16.5 PSIA 16 PSIA ' i %BH NONE 0-60 100 100 100 G'lDITY, IATION. PADS NCNE 6.32E6 1.71E6 1.71E6 1.71E6 OPERASILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--------- -------------------- CLASS 1E INTERFACES ----------------------------- --------- - --- INPUTS --------------- ==--------------- OUTPUTS --------------
MOTIVE POWER: 125VDC MAINDST PNL1B NOTIVE POWER: N/A CONTROL POWER': h/A CONTROL POWER: N/A SENSIhG SIGNAL: N/A EXECUTE SIGNAL: LS/IC l LS/IO COMPAND SIGNAL: 1E51-K35 CLOSED AhhlBIT SIGNAL: 1E51-K35 OPEN PRGCESS SIGNAL: W/A PERMISSIVE SIGNAL: N/A s I ***** CINCItanATI GAS & ELECTRIC PROPPIETARY INFORMATI0A ***** (~'/
\_
i (_
05/09/02 CIACINHATI GAS 4 ELECTRIC COMPANY PAGE 242 ID2 PI-18 be. H. ZIHMER NUCLEAk POWER STATION UNIT 1 REV A CNTIAL FAILURE FAILURE ISOL ATIOt1 INTERFACE: K-35 CONTACTS 1, 7 DEVICE: NONE CAUSE: SHORT TO GROUND BASIS: UNGROUNDED DC SYSTEM IS UhAFFECTED FAILU21E M0'DE: NO EFFECT FAILURE EFFECT: NONE. POTESTIAL FAILURE FAILURE ISCLATION INTERFACE: , DEVICE: NONE CAUSE: OPEN CIRCUIT BASIS: fl04-PROPAGATING FAILURE M"DE': 0 FAILS CLOSED - FAILURE EFFECT': VALVE LOSES OPEN PERMISSIVE SIGNAL FROM K-35 RELAY
- VALVE WILL CLOSE. , ,
POTENTIAL FAILURE FAILURE ISOLATION DEVICE: NONE l,sINTERFACE: SHORT CIRCUIT BASIS: Nah-PROPAGATING
)CAUSE:
iLUBE MODEi FAILS AS IS FAILURE EFFECT: VALVE HAS C0t.STANT OPEN PEFNISSIVE SIGNAL - hlLL NOT CLOSE WHEN K-35 RELAY DE-ENERGIZES. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: E51A-F29 DEVICE: DONE CAUSE: FUSE (F-4 10A) FAILS BASIS: NON-PROPAGATING FAILURE uoDEA FAILS CLOSED FAILURE EFFECTA VALVE OPERATION IS LOST, VALVE FAILS CLOSED. POTENTIAL FAILUPE FAILUPE ISOLATION I:4TEPFACE: G-2 DEVICE: NONE CAUSE: BULB FAILS BASIS: N 0 e!-P RO P A G ATI N G FAILURE N0pEi t.0 EFFECT 2 LUBE EFFECT: VALVE POSITION INDICATI0tl DNLY, IS LOST.
05/09/92 CIhCINelATI CAS & ELECTRIC COMPANY PAGE 243 ID: RI 19 NM, H. ZI"MER NilCLEAR POWER STATIUN UNIT 1 REV A E .ENTIAL FAILURE FAILURE ISOLATION IhTERFACE: P.2 DEVICE: NONE CAUSE: BULB FAILS BASIS: NON-PROPAGATING FAILURE M'0DE's ho EFFECT FAILURE EFFECT: VALVE POSITION INDICATION ONLY, IS LOST. BASIS: THIS DEVICE IS h0T INVOLVED IN THE CIFCUIT USED FOR THE SYSTE% SAFETY FUNCTION AND FAILUPE WILL h0T PROPAGATE TO THE SAFETY FUNCTION CIRCllIT. BEFEHENCES: ' M-52 SHEET ONE OF TWO REV. W, E1010/PG. RIO7 REV. M, E1010/PG. RIO2' REV. F. E1010/PG. RIl0 REV. K E0 D.S. X510, X520, X530, X540 i 9 NITIGATIch EVENT CAPABILITY A B C D ADE00 ATE N h X N INADEQUATE
,r
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I , 05/00/92 CINCINNATI GAS & ELECTRIC COMPANY PAGE 25,8 ID: RI-25 MM. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A' [L ) s )ISTIFICATION FOR INTERIM OPERATIO:1 0F:. 1E51-F026 m LOCATION:P-4D DESCRIPTIO4: LIPIT SWITCH LS/IO SYSTEM: REACTOR CORE ISOLATI0h COOLING (RI) SUBSYS NONE , SAFETY FUNCTION': CONT. ISOL. & INTEGRITY CNTRL. (CI&IC) STEAM LINE DRAIN OUTBOARD ISOLATION VALVE SENSING FEATURE DIV:II
-------EVENT------- -
--~~~~--DEVICE STATUS--------- ---ESTIMATED TIME---
. TO FAILURE NORMAL ENEPGIZED A LOCA N/A NOT DETERMINED B 11SL/FW BREAK N/A NOT DETERMINED C RCIC BREAK EhERGIZED NOT DETERMINED D RUCU BREAK N/A h0T DETERMINED
------- - -------------------QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMP'ERATURE, DEG F NONE 45-148 125 218 160 (3 ESSURE. NONE -0.25 15 PSIA 16.5 PSIA 16 PSIA H.IDITY, INCH-H2O
%RH h0NE 0-60 100 100 100'
\CIATION, RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6
.oERABILITY N0hE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER:
--------- --------- ---------- CLASS 1E INTERFACES -----------------------------
----- - - ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE PONER: N/A MOTIVE POWER: N/A CONTROL POWER: 125VDC MAINDST PNL1B CONTROL POWER: N/A SENSING SIGNAL: VALVE POSITION EXECUTE SIGNAL: ENERGIZE OPEN LIGHT COMMAhD SIGNAL: N/A INHIBIT SIGNAL: N/A
. PROCESS SIGNAL: d/A PERMISSIVE SIGNAL: N/A s i g-g ***** CIbcli.NATI GAS & ELECTRIC PPOPRIETARY INFORMATION *****
.V w ...- ~ . . ..% . . . . . _ - - - . . ~. . . . . . . . . . - ..-e.- . -
- , . ~
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05/09/82 . CINCINNATI GAS & ELECTRIC COMPANY PAGE 259 ID: RI.25 WM. H. ZIMMER hUCLEAR POWER STATION UNIT 1 REV A g))TENTIAL FAILURE FAILURE ISOLATION INTERTACE: LS-IO DEVICE: Nor4E CAUSE: SHORT TO GROUND BASIS: Ur4GROUtiDED DC SYSTEM IS U!!AFFECTED FAILURE M'DE': 0 NO EFFECT FAILURE EFFECT: NONE. POTENTIAL FAILURE FAILURE ISOLATION IhTERFACE: DEVICE: NONE CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING FAILURE M'DE: 0 CONTACTS FAIL CLOSED FAILURE EFFECT: VALVE IllDICATES OPEN AT ALL TIMES. POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: DEVICE: NONE OPEtt CIRCUIT BASIS: NON-PROPAGATIdG ( )CAUSE:
\ILURE PODE: CONTACTS FAIL OPEN FAILURE EFFECT: LOSS OF OPEN VALVE POSITION IMDICATION.
BASIS: THIS DEVICE IS NOT INVOLVED IN THE CIRCUIT USED FOR THE SYSTEM S AFETY. FUNCTIOii, AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT.
REFERENCES:
l v-52 SHEET ONE OF TWO PEV. 4, E1010/PG. RIO7 REV. M EQ D.S. X520, X530, X540, X550, X560 MITIGATIdN EVENT CAPABILITY A- B C 0
' I ADE00 ATE N N X N INADEQUATE
(^} ss
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-yw i-, y , - -,,,p- . - . - - . - _ - g g .%_.-. __ y
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05/09/02 , CINCINNATI GAS & ELECTRIC COMPANY PAGE 260 , ID: RI-26 WH. H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A ('~ .
\m/ STIFIC ATION FOR INTERIM OPERATION OF: 1E51-F026 LOCATION'ap-40 DESCRIPTION: LIMIT SWITCH LS/IC SYSTEM: REACTOR CCRE ISOLATION COOLING (RI) SUBSYS:N0hE SAFETY FUNCTIdN: CONT. ISOL. & INTEGRITY CNTRL. (CI&IC)
STEAM LINE DBAIN OUTBOARD ISOLATION VALVE SENSIhG FEATURE DIVIII
-------EVENT------- -a-------DEVICE STATUS--------- ---ESTIMATED TIME---
- TO FAILURE ~
NORNAL DE-ENERGIZED A LOCA N/A NOT DETERMINED B NSL/Fd BREAK N/A h0T DETERMINED C FCIC BREAK- DE-ENERGIZED NOT DETERMINED D RWCU BREAK N/A NOT DETERMINED
==------- --------- ---------QUALIFICATI0t3 SUMhARY-----------------------------
PARAMETER -----DEMONSTRATED----- ----------------REQUIRED---------------- EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F NONE 45-148 125 218 160 ( 'ESSUAE, INCH-H2O NDHE -0.25 15 PSIA 16.5 PSIA 16 PSIA MIDITY, %RH NONE 0-60 100 100 100 ADIATION. RADS NONE 6.32E6 1.71E6 1.71E6 1.71E6
- OPERABILITY NONE 100 DAYS 1 DAY 1 DAY 1 DAY OTHER
l
----- --- --------- - -------- CLASS 1E INTERFACES -----------------------------
------- - ----- INPUTS --------------- ----------------- UUTPUTS --------------
MOTIVE POWER: N/A MOTIVE POWER: N/A CONTROL powEP': 125VDC MAINDST PNL18 CDtlTROL POWER: h/A SENSING SIGNAL's VALVE POSITION EXECUTE SIGNAL: ENERGIZE CLSD LIGHT COM. MAND SIGNAL: N/A INHIBIT SIGNAL': N/A PROCESS SIGNAL: h/A PEPMISSIVE SIGNAL: N/A s
***** CIhCIt4N ATI G AS & ELECTRIC PROPPIET ARY I:#FORF ATIOr. * * * * *
{ w- - - - - - - er -- -e--- .m -- ,y y-
'05/09/92 cit:CINNATI GAS 6 ELECTRIC COMPADY PAGE 261 ID: RI.26 NN. H. ZIMMER NUCLEAR P0FER STATIO!! UNIT 1 REV A
(]%TEflTIALFAILURE FAILUPE ISOLATION INTERFACE: LS-IC DEVICE: 634E CAUSE: SHORT TO GROUND BASIS: UNGROUNDED OC SYSTEM IS UNAFFECTED FAILUBE MUDE: NO EFFECT FAILUPE EFFECT: NONE. POTENTIAL FAILURE FAILURE ISOLATI0tl IhTERTACE: DEVICE: N0rdE CAUSE: SHORT CIRCUIT BASIS: NON-PROPAGATING
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FAILURE MODE: C0tlIACTS FAIL CLOSED FAILURE EFFECT: VALVE INDICATES CLOSED AT ALL TIMES. POTEpTIAL FAILUDE FAILURE ISOLATION INTERFACE: DEVICE: NONE OPEN CIRCUIT BASIS: NON-PROPAGATING' {}CAUSE: , ()ILUREMODE: CONTACTS FAIL OPEN FAILUBE EFFECT: LOSS OF CLOSED VALVE POSITI0tl INDICATION BASIS: THIS DEVICE IS tl0T INVOLVED IN THE CIRCUIT USED FOR THE SYSTEM SAFETY, FUNCTION, AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT. a REFEREllCES: i=52 SHEET ONE OF TWO REY. W E1010/PG. RIO7 REV. M EQ 0.S. X520, X530 H, X540, X550, X560 MITIGATION EVENT CAPABILITY A B C D
. ADEOUATE fl N X N IbADEQUATE O
) i 05/09/02 CIdCINNATI GAS & ELECTRIC COMPANY PAGE 286 ID: BI-7 Wii . H. ZIMMER NUCLEAR POWER STATION UNIT 1 REV A STIFICATION FOR INTERIM OPERATION OF: 1E51-N002 LOCATION: R-4D DESCRIPTIOit : PRESSURE SWITCH SYSTEM: REACTOR CORE ISOLATION COOLING (RI) SUBSYS:NONE SAFETY FUNCTION':NONE AUTO CLOSE CONTROL OF aINIMUM FLOW BYPASS VALVE SENSING FEATUPE DIV:I
-EVENT------- ---------DEVICE STATUS ~-------- ---ESTIMATED TIME---
TO FAILURE NORMAL VARIABLE A LOCA VARIABLE NOT DETERMINED B HSL/FW BREAK VARIABLE NOT DETERMINED C PCIC BREAK VARIABLE NOT DETERMINED D RXCU BREAK VARIABLE NOT DETERMINED
--........................... QUALIFICATION
SUMMARY
PARAMETER -----DEMONSTRATED-==== ================ REQUIRED-----=----------
. EVENT A EVENT B EVENT C EVENT D TEMPERATURE, DEG F 212 45-148 125 218 160
ESSURE, INCH-H2O 15 PSIA
( NONE =0.25 16.5 PSIA 16 PSIA "MIDITY, %RH 100 0-60 100 100 100 DIATION, RADS 2.2E6 6.32E6 1.71E6 1.71E6 1.71E6 PERASILITY 6 nRS 100 DAYS 1 OAY 1 DAY 1 DAY OTHER:
--------- ----------- -------- CLASS 1E INTERFACES -------~~~-------------------
--------- ----- INPUTS --------------- ----------------- OUTPUTS --------------
MOTIVE POWER: MOTIVE POWER: CONTROL POWER: FUSES C0f. TROL POWER: set.SI:#G SIGNAL: PCIC FLOW EXECUTE SIGNAL: M0/b K19 l COMMAND SIGNAL: INHIBIT SIGNAL: PROCESS SIGNAL: PERMISSIVE SIGNAL: (~(i t
***** CINCINNATI GAC & ELECTRIC PPOPkIETARY INFORMATION *****
- - - = . .. m .. = e we -,--=m . -----ee- =.-w
05/09/92 CINCINN ATI GAS L ELECTRIC C0ttPANY PAGE 297 ID: RI-7 WM. H. ZIMMER HUCLEAR POWER STATION UNIT 1 REV A l TENTIAL FAILURE FAILURE ISOLATIbN INTERFACE: SW CONTACT 9-10, 1-2 DEVICE: N/A CAUSE: OPEN CIRCUIT BASIS: NON-PROPAGATING FAILURE MDDE: FAILS OPEN FAILURE EFFECT: MINIMUM FLOW BYPASS VALVE WILL NOT AUTO-CLOSE.
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POTENTIAL FAILURE FAILURE ISOLATION INTERFACE: DEVICE: FUSE CAUSE: SHORT CIRCUIT BASIS: ISO DEVICE QUALIFIED FOR EVENT FAILURE NODE: FAILS SHORTED , FAILURE EFFECT': LOSS OF VALVE CONTROL POSITION INDICATION. POTE.NTIAL FAILURE FAILURE ISOLATION INTERFACE: DEVICE: N/A SHORT TO GROUND BASIS: OC SYSTEM HOT (}CAUSE: GROUNDED g tILURE MODE: ( f SHORT TO GROUND FAILURE EFFECT: NONE. BASIS: THIS DEVICE IS DOT INVOLVED IN fME CIRCUIT USED FOR THE SYSTEM SAFETY FUNCTION, AND FAILURE WILL NOT PROPAGATE TO THE SAFETY FUNCTION CIRCUIT.
REFERENCES:
E1010/pG. RIOS, PG. RIO1 l EQ D.S. E516, E123, E214, E224 l l MITIGATION EVENT CAPABILITY A B C 0
,j ADECUATE X X A 4 INADEQUATE
05/09/82 CINCIr4NATI GAS & ELECIPIC CONPANY PAGE 286 ID RI-9 WM. H. ZI.**ER NUCLEAR P0hER STATIOh UNIT 1 REV A
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