ML19351D825
| ML19351D825 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 11/01/1980 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML19351D808 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, NUDOCS 8011200081 | |
| Download: ML19351D825 (100) | |
Text
{{#Wiki_filter:-_ _ -- l IO I 'I i l I l I RESPONSE TO IE BULLETIN 79-01B l FOR 1 I QUAD CITIES NUCLEAR POWER STATION m UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY i DOCKET NUMBERS 50-254 AND 50-265
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i ! PREPARED BY: BECHTEL POWER CORPORATION I Preliminary Report Date: April 11, 1980 Revision 0: June 2, 1980 m Revision 1: November 1, 1980 I I
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I l E Revision 1 November J, 1980 l TABLE OF CONTENTS ! VOLUME 1 1.0 STUDY OBJECTIVES 1 2.0 STUDY RESULTS la 3.0 STUDY CONCLUSIONS AND RECOMMENDATIONS 2 4.0 DETAILED EVALUATION 3 4.1 Definition of Postulated Accidents 3 4.2 Identification of Class lE Components 4 Required to Function Under Postulated Accident Conditions (Bulletin Action Item 1) 4.3 Definition of Environmental Service 5 Conditions (Bulletin Actions Items 3 and 5) 4.1 Evaluation of Environmental Qualification 9 Data (Bulletin Action Items 2 and 4) 4.5 Class 1E Equipment Qualification Plan 10 4.6 Submittal of Licensee Event Reports 11 (Bulletin Action Item 6)
5.0 REFERENCES
11 I APPENDIXES A.1 Ouad Cities Unit 1 and Common Systems List A.2 Quad Cities Unit 2 Systems List B.1 Quad Cities Unit 1 and Common Specific and General Use Components List Sorted by System B.2 Quad Cities Unit 2 Specific and General Use Components List Sorted by System I C. Quad Cities Units 1 and 2 Key Plan Identifying Harsh Environmental Areas and Tabulation of Service Conditions I I I h ii
I Revision 1 November 1, 1980 i VOLUMES 2& 3 D.1 Quad Cities Unit I and Common Component Evaluation Worksheets Sorted by System I VOLUMES 4 & 5 lI i D.2 Quad Cities Unit 2 Component Evaluation Worksheets Sorted by System I 'i
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l W Revision 1 November 1, 1980 i 1.O STUDY OBJECTIVES I This study has been prepared in response to NRC IE Bulletin 79-01B, dated January 14, 1980. It has been prepared by Bechtel Power Corporation, Ann Arbor, Michigan, for Commonwealth I Edison Company's Quad Cities Nuclear Power Station Units 1 and 2. The scope of the study includes:
- a. Preparing a master list of all engineered safety feature (ESP) systems r.
W b. Identifying all components required to function under postulated accident conditions
- c. Defining environmental service conditions for the components identified above
- d. Establishing maximum flood elevation inside containment
- e. Evaluating qualification data for components and documenting hades of equipment qualification
- f. Recommending action to be taken where qualification I data for components does not exist or is inadequate for station service conditions 9 Where qualification data does not exist, preparing I a justification for continued station operation, or identifying those items for which a licensee event report (LER) should be prepared by Commonwealth Edison Company
- h. Preparing a report documenting the results of the i i.
study in accordance with Item 7 of NRC IE Bulletin 79-01B Preparing contract documents to specify testing and analyses where required to resolve outstanding items
- j. Preparing procurement documents for replacement equipment where existing equipment is identified for I replacement
- k. Performing engineering for equipment relocation and modification where necessary to resolve open items t
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'l Revision 1 .W November 1, 1980 I 2.0 STUDY RESULTS I The systems required to function following the postulated accidents have been identified and the essential components listed. Environmental service conditions have been established. Evaluation of environmental qualification test reports have l I been completed. Data sheets (Appendixes D.1 and D.2) are provided for essential components subject to harsh environ-mental service conditions. These data sheets document the l qualification test conditions, or document action in progress 1 to resolve the status of the component. Table 2-1 provides a tabulation of systems included in the study, percent of system
- g components with outstanding items, and percent of outstanding Data cheets for components with
'5 qualification data items. outstanding items also contain specific actions to be taken to resolve outstanding items, and justifications for continued station operation while the action items are being implemented. I
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Revision 1 November 1, 1980 l l I 3.0 STUDY CONCLUSIONS AND RECOMMENDATIONS l Investigations in response to NRC IE Bulletin 79-01B indicate that a significant number of components are either not subjected to harsh environmental service conditions or have qualification I data documented. Vendors have been contacted and confirming letters have been written to the equipment manufacturers requesting qualification data, if available, or component materials I data for analysis. Table 3-1 provides a list of letters written. Resolution of qualification status for the remaining components is being pursued by one or any combination of the following methods:
- a. Equipment will be subjected to worst case environmental service conditions and performance / function tested following exposure. A test report will be prepared for each test.
- b. Equipment will be replaced with qualified equipment.
- c. Equipment will be relocated and/or shielded.
! d. Where qualification data may exist but materials data is required to determine existence of suitable test reports, additional vendor contacts will be made and investigations performed. Contract packages for qualification testing have been prepared g and are scheduled to be issued for bids before January 1, 1981. E erocurement documents for replacement components are being prepared and are scheduled to be issued for bids during the first quarter of 1981. Vendor contacts have been made and work is in I progress where additional qualification data may be obtainable from the vendor, a I I E I ; I 2
l Revision 1 5 November 1, 1980 I Replacement components will be installed during the first refueling outage after the new components are received onsite. .I When the outstanding items identified in Appendixes D.1 and D.2 are closed out, all Class lE electrical components will be qualified and the basis of the qualification documented. It is recommended that work continue as outlined above to close out the outstanding items in Appendixes D.1 and D.2. 4.0 DETAILED EVALUATION 4.1 DEFINITION OF POSTULATED ACCIDENTS NRC IE Bulletin 79-01B defines the postulated accident conditions to be addressed as the loss-of-coolant-accident /high energy line I break (LOCA/HELB) inside the containment and the HELB outside the containment. I For the Quad Cities Nuclear Power Station (QCNPS) Units 1 and 2, the LOCA/IIELB inside the containment is discussed in FSAR Sections 5.2.3 and 6.2.7. The HELB outside the containment is discussed in Special Report No. 12, Revision 1, submitted to the I NRC in February 1975. In evaluating the effects of HELB, concurrent multiple breaks are not evaluated. For the LOCA/HELB inside the containment, worst case environ-mental conditions are established by the LOCA, resulting from a double-ended recirculation line break. The environmental I conditions which result from this accident are provided in Section 4.3 and Appetidix C. For a HELB outside the containment, Special Report No. 12
'I identifies the high energy lines and the locations of postulaced breaks. In support of the response to IE Bulletin 79-01B, studies were performed to establish equipment integrated I radiation doses as a result of the postulated accidents. These environmental conditions are discussed in Section 4.3.
The following postulated accidents were analyzed to establish the worst environmental conditions: LOCA inside drywell
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- b. Main steam line break (MSLB) in the steam tunnel
- c. Main feedwater line break l
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Revision 1 Novcmber 1, 1980 I d. Iligh-pressure coolant injection (IIPCI ) steam line break
- e. Reactor core isolation cooling (RCIC) steam line break I f. Reactor water clean up (RWCU) line break E Where components, because of their locations, could be
'E subjected to differing environments for the various accidents, the most severe environmental conditions were utilized for qualification. Components located within compartments with iI postulated IIELBs would be subjected to pressure, temperature, and humidity conditions resulting from those IIELBs, but would not be subjected to radiation doses in excess of 5 X 104 rads simultaneously. These same compone subjected to radiation doses in excess of 5 X 10gtsradscould be following a LOCA, but these doses would not be simultaneous
- g with pressure, temperature, and humidity. To simplify this
- 5 analysis, qualification data was initially sought which demonstrated operability of these components for the combi-
.g nation of all environmental conditions. Where qualification ig could not be demonstrated for the entire spectrum of conditions simultaneously, components were evaluated for the conditions associated with each individual accident. Environmental
! conditions are based on the specific accidents for which the
- components must function. Components which are exposed to harsh environments during accidents for which they are not g required to function do not require qualification for these lg environments. Where qualification testing is to be performed, testing will be performed for each postulated environment separately.
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4.2 IDENTIFICATION OF CLASS lE COMPONENTS REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS (BULLETIN ACTION ITEM 1) The OCNPS FSAR and emergency procedures were reviewed to lg identify the ESF systems which are required to mitigate the g consequences of the postulated accidents discussed in Section 4.1. l These systems are those needed to achieve reactor shutdown, containment isolation, reactor core cooling, containment and l reactor heat removal, and to prevent the release of radioactive material to the environment in excess of the guidelines of 10 CPR 100. Appendix A.1 provides the master list of Unit 1 and common systems required to function following all of the postulated I
- g accidents discussed in Section 4.1. Appendix A.2 provides '
- E the master list of Unit 2 systems required to function following all of the postulated accidents discussed in l
Section 4.1. Table A-1 identifies which systems are required to function following each of the postulated accidents. i
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Revision 0 June 2, 1980 I The station piping and instrument diagrams and electrical schematics were reviewed to determine the specific components I which must function following the postulated accidents. Based on this review, a master conOonents list has been developed for each system identified in Appendixes A.1 and I A.2. The master components list identifies each Class lE and/or essential electrical component that is required to function following the postulated accidents discussed in I Section 4.1. Appendix B.1 provides the master components list for Unit 1 and common systems. Appendix B. 2 provides the master components list for Unit 2 systems. Throughout this report, Class lE is used in reference to components I designed to Class lE, as well as components not designed to Class lE but which are essential fsllowing the postulated accidents. 4.3 DEFINITION OF ENVIRONMENTAL SERVICE CONDITIONS (BULLETIN ACTION ITEMS 3 AND 5) 4.3.1 Inside the Drywell The drywell pressure and temperature response following the postulated LOCA are provided in FSAR Figures 5.2.15 and I 5.2.16, respectively. These figures are included in Appendix C. The maximum humidity inside the drywell is defined in FSAR I Table 5. 2. 2 as 100%. Chemical sprays are not used in the QCNPS design. Demineralized water containment spray is utilized and considered in the evaluation. The QCNPS FSAR does not provide integrated radiation doses inside the I drywell. Studies were performed to establish the integrated doses inside the drywell for a postuated LOCA. The integrated doses for 1 day, 30 days, and 1 year are provided in Appendix C. I The study methodology is described in Section 4.3.5. Radiation doses are evaluated for actual equipmant operating times. Appendix C also defines the containment spray fluid and provides the maximum drywell pressure, temperature, humidity, I. and flood elevation. 4.3.2 Outside the Drywell, Subject to HELB I HELB is discussed in detail in Special Report No. 12, Revision 1, submitted to the NRC in February 1975. The _g environmental conditions (pressure, temperature, and humidity) 5 due to a pipe break in the steam tunnel, torus compartment, core spray /RCIC room, reactor water cleanup heat exchanger room and turbine building are listed in Appendix C. I Radiation doses following a HELB are less severe than the doses asso-ciated with a LOCA and are therefore not provided. Flooding does not occur outside the drywell as a result of the postu-I lated HELBs. Chemical and demineralized water spray do not exist outside the drywell. For this study, the environmental effects of a pipe break are considered only in the compart-ment in which the break occurs, as well as areas open to the I break area. l I s
Revision 1 November 1, 1980 E 4.3.3 Outside the Drywell, Post-LOCA Radiation Exposures I Integrated doses have been calculated for areas outside the drywell. Doses were established for 1 day, 30 days, and 1 year exposure. Integrated doses of less than 5 x 104 rads during a component's service life are evaluated as nonharsh I environmental conditions. Integrated doses of 5 x 104 rads and higher are evaluated as harsh environmental canditions. Appendix C provides integrated doses as a function of exposure I time for areas containing components identified in Appendixes B.1 and B.2. Section 4.3.5. The radiation study methodology is described in 4.3.4 Nonharsh Areas Plant areas which are not covered in the above referenced I Appendix C tables are considered nonharsh environmental areas with respect to HELB and post-LOCA radiation. These areas are either maintained in a suitable environmental I condition by safety-related heating, ventilating, and air conditioning (HVAC) equipment, or are considered nonharsh because they are controlled to less than 104F prior to the I postulated accidents and are relatively large open areas with no large motors or other equivalent heat sources. Where environmental conditions are maintained by safety-related I HVAC equipment, the HVAC system is provided with redundant components and/or a backup power supply for reliable operation. Safety-related HVAC systems are provided for the following areas:
- a. Control room, cable spreading room, battery rooms, computer room, and electrical equipment room
- b. Standby diesel generator room
- c. HPCI room
- d. Residual heat removal corner rooms
- e. Core spray /RCIC corner rooms 4.3.5 Radiation Study Methodology A radiation study was performed to establish integrated doses to equipment following a postulated LOCA. The core fission product inventory was based on General Electric i I document " Radiation Source Information for NUREG 0578 Imple- l mentation, Computer Run identified as SNUMB 70075" dated November 1979.
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R vision 1 November 1, 1980 I The fission products were diluted into the appropriate fluid media as follows: Fluid Noble Gases (%) Halogens (%) Other (%) Suppression pool liquid 50 - 1 Reactor coolant liquid 100 50 1 I Containment atmosphere 100 25 - Reactor steam 100 25 - Dilution of the fission products was considered using the fluid volume as the dilution media. For components located inside the drywell, only gamma doses were considered if the component was enclosed in a nonorganic I material (e.g., valve motor actuators in metal enclosures). The gamma dose was established based on immersion of the component in the gaseous drywelt atmosphere for the time I which the component must remain functional. For components enclosed in organic material (e.g., cable) beta radiation doses were calculated. Where components enclosed in organic materials are installed in metal enclosures (e.g., cable in I conduit or flex-conduit), beta radiation will be neglected. Inspections have been performed in the Quad Cities Unit 2 drywell, coriiirming that all equipment and cable is enclosed in nonorganic ma terials. Beta doses have therefore not been
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I For components located outside the drywell, source terms were established for piping systems containing reactor steam, reactor coolant liquid, suppression pool liquid, and containment atmosphere. Since the piping wall thickness is - sufficient to shield against beta radiation, only gamma radiation need be considered. Each Class 1E component was located with respect to the piping systems containing post-I LOCA radioactive fluids. The integrated dose was established based on the piping source term, distance from pipe to component, and component operating time. Where a component could receive doses from more than one pi ling system, the I doses were added to derive a total dose. .,pendix C, Table C-3, provides integrated doses as a function of time calculated 1 foot from the greatest single source in each major plant area.
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l 5 Revision 1 November 1, 1980 I 4.3.6 Aging In this study, the need to consider aging is based on the evaluation of component design and application. The effects of aging have also been considered based on Enclosure 4 to MRC Bulletin 79-01B, " Guidelines for Evaluating Environmental I Oualification of Class lE Electrical Equipment in Operating Reactors" and NUREG-0588, " Interim Staff Position on Environ-mental Qualification of Safety-Related Electrical Equipment."
- a. Components Located Inside the Drywell I The environmental conditions inside the drywell are defined as harsh (Section 4.3.1 and 4.3.4) and hence the effects of thermal and radiation aging are evaluated for all Class lE electrical components.
.I B. Components Located Outside the Drywell
- 1. Radiation aging The components which are located outside the drywell and steam tunnel are exposed to I insignificant amounts of radiation during normal operating conditions. The effects of radiation aging are therefore not considered I in the qualification evaluation of these components.
Under postulated accident conditions some compongnts may be exposed to greater than 5 x 10 rads (integrated radiation dose). I The effects of this short-term radiation exposure are considered in qualification evaluation. Components located inside the steam tunnel are evaluaced for radiation aging.
- 2. Thermal aging Most areas outside the drywell are maintained I in a suitable environmental condition by safety-related HVAC equipment. The normal maximum temperature is 104P, which in this study is defined as a nonharsh environment I (Section 4.3.4). Thermal aging for these components is not required since the normal and post-accident environments are nonharsh.
In addition, temperature extremes (up to 120F) may occur in some plant areas. However, these conditions would result only during periods of extreme outdoor temperatures. I
l R3 vision 1 E November 1, 1980 I Equipment designed and installed per industry standards would be capable of satisfactory I operation without exhibiting age-related degradation due to these temperature extremes. Therefore, the effects of thermal aging are I not considered for components located in areas where the maximum ambient temperature is maintained at 120F or below. 4.4 EVALUATION OF ENVIRONMENTAL QUALIFICATION DATA (BULLETIN ACTION ITEMS 2 AND 4) Appendixes B.1 and B.2 identify all specific components necessary following the postulated accidents. In addition, this bulletin covers general use electrical items such as I motor lubricating oil, sealants, tape, terminal blocks, gaskets, etc. Section 4.5. These general use items are discussed in For each specific component identified in Appendixes B.1 and B.2, a component evaluation worksheet was prepared. These worksheets identified the most harsh environment each I component would be subjected to following the postulated accidents. Environments were considered nonharsh when the temperature was controlled to 104F or less and the maximum I integrated radiation dose was less than 5 x 104 rads. Areas where infrequent temperature extremes up to 120F could occur, and additionally, where temperature variations are not a result of the postulated accidents are considered as I mild environments. Equipment in these areas functions normally in the same environment as postulated for post-accident conditions. For nonharsh and mild environments, qualification data is not required. Since industry standards did not exist for environmental qualification of Class lE electrical equipment during the
.I time the Quad Cities station was designed and constructed, qualification testing was not required for these components when originally purchased. However, many of these same I components were used in later designs and qualification testing data is available. Also some testing has been performed by the Nuclear Steam System Supplier in response I
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l Revision 1 5 November 1, 1980 I to NRC IE Bulletin 79-01. These qualification reports have been evaluated to determine their applicability to the components identified in Appendixes B.1 and B.2. Where applicable qualification data exists, this data has been entered on the component evaluation worksheets to document the suitability of the component. Some components will be qualified by analysis or a combi-nation of analysis and testing. In these cases, the analysis 'I and testing performed will be documented. Pinally, for those components which are exposed to harsh
- I environments and for which data is not available and qualifi-cation by analysis is not appropriate, the qualification status will be resolved by testing, replacement, or reloca-tion of the component to a nonharsh environment.
The component evaluation worksheets are provided in Appendix D.1 for Unit 1 and common components. The component evaluation .I worksheets are provided in Appendix D.2 for Unit 2 components.
, The qualification plan, which will be followed to resolve outstanding items, is discussed in Section 4.5.
4.5 CLASS lE EQUIPMENT QUALIFICATION PLAN 4.5.1 Specific Components Where it has been demonstrated that a component will not function under the postulated environment, an LER will be prepared. Where existing data is not available to demonstrate qualification of a component, one or more of the following
;$ methods will be utilized to resolve the status of the 5 component:
The component will be tested under worst case environ-I a. mental conditions
- b. An identical component from the spare parts inventory or one of the installed components will be tested.
- c. 2he component will be relocated in a nonharsh environment,
- d. The component will be replaced.
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Ravision 1 November 1, 1980 I 4.5.2 General Use Components A walkdown inspection of accessible electrical boxes and cable connections was performed in the Quad Cities Unit 2 drywell. The inspection was performed following the spring 1980 refueling outage prior to returning the station to power. The purpose of the inspection was to identify miscellaneous I general use electrical items (i .e . , gaskets, seals, grommets, terminal blocks, splices, and termination tapes) used inside the drywell. In addition, the condition of cables at the I electrical boxes and component terminations was inspected. Boxes which did not have preassigned numbers were numbered These field-assigned numbers were by the inspection team. prefixed with 79-01B. During the inspection, any gaskets I found damaged were reported to station electrical personnel for replacement. Splices and termination tapes were not The results of the I found in the electrical boxes inspected. electrical box inspection are provided in Table 4-1. Where qualificaton data is not available for existing I installed materials, procedures will be written to replace these items with qualified materials. The station inventory of lubricating oils, greases, and other general use items will include qualified materials and steps implemented so I that only these materials are utilized on Class lE components. SUBMITTAL OF LICENSEE EVENT REPORTS (BULLETIN I 4.6 ACTION ITEM 6) In the event any Class lE electrical equipment item is I determined to be not capable of meeting its required function under the established service conditions, Bechtel will advise Commonwealth Edison Company so that an LER can be LERs, when submitted, will identify the conditions I submitted. under which the component must function and the basis for the determination that it is incapable of functioning. Where justification for continued station operation exists, this I will be included in the LER. LERs will be submitted within the time frame specified by NRC IE Bulletin 79-01B. LERs will not be submitted for items previously documented as not being capable of meeting their required function in the response submitted for NRC IE Bulletin 79-01 (Refer-ence 5.0.e).
5.0 REFERENCES
- a. USNRC IE Bulletin 79-OlB, dated January 14, 1980 I
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-l Revisior. 0 . -5 June 9, 1980 I 1 I b. Quad Cities Nuclear Power Station Final Safety Analysis Report, Docket Numbers 50-254 and 50-265
- c. Analysis of Effects of Pipe Break Outside Primary Containment, Quad Cities Station, Units 1 and 2, I Special Report No. 12, Revision 1, February 1975 Quad Cities Station Emergelscy Procedures, QGA-1, d.
Loss of Coolant (Fast Leak; Large or Small Line -I Break Inside Containment), Revision 8, December 4, 1979; QGA-2, Loss of Coolant (Slow Leak), Revision 3, .g December 4, 1979; QGA-3, Major Steam Line Break 5 (Outside Drywell), Revision 3, December 4, 1979
- e. Report on Results on Qualification Data Search for lI Quad Cities Units 1 and 2, NEDO-24217, General Electric Company, November 1979 I
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I Revision 1 November 1, 1980 i I TABLE 2-1
' COMPONENT OUALIFICATION STATUS
. I Components With Outstanding i Number of Outstanding Qualification System Components Items (%) Data Items (%)
Reactor Protection 8 0 0
'I Unit 1 Unit 2 8 0 0 Core Spray I Unit 1 Unit 2 22 22 64 64 9
9 I Iligh-Pressure Coolant Injection Unit 1 61 3 2 Unit 2 57 4 3 Auto Depressurization/ Main Steam I Unit 1 Unit 2 47 47 17 17 12 12 Residual lleat Removal / I Containment Spray Unit 1 73 45 8 Unit 2 73 45 0 I Pressure Suppression Unit 1 47 26 4 Unit 2 47 26 4 Standby Gas Treatment 26 69 10 I Unit 1 Unit 2 NA NA NA Service Water I Unit 1 Unit 2 9 7 44 57 6 8 I Diesel Oil Piping Unit 1 Unit 2 7 3 0 0 0 0 l Containment Isolation Unit 21 5 3 ! Unit 2 21 5 3 1I l I
l Revision 1 5 November 1, 1980
;I TABLE 2-1 (Continued)
Components
- With Outstanding Number of Outstanding Qualification System Components _ Items (%) Data Items (%)
Control Rod Drive flydraulic lm 1,073 0 0 .g Unit 1 Unit 2 1,073 0 0 !l Reactor Recirculation
- 4 Unit 1 44 23 13 Unit 2 44 23 13 Process Radiation Monitoring Unit 1 2 0 0 Unit 2 2 0 0 Reactor Building Ventilation
.I Unit 1 Unit 2 4 4 0 0 0 0 Control Room IIVAC
; Unit 1 8 0 0 Unit 2 NA NA NA Standby AC Power Unit 1 30 23 3 Unit 2 26 27 4 Standby DC Power !g Unit 1 20 5 1 g Unit 2 19 5 1 Reactor Core Isolation Cooling lI Unit 1 30 30 3
3 3 3 Unit 2 General Use Electrical Unit 1 38 97 94 Unit 2 NA NA NA 'I Unit 1 Totals 1,570 9 4 Unit 2 Totals 1,483 6 2 l l' I
E Revision 0 5 June 2, 1980 I TABLE 3-1 I LIST OF LETTERS TO MANUFACTURERS REQUESTING QUALIFICATION DATA I Letter Manufacturer Chron Number Date Sent Automatic Switen 772 May 6, 1980 Burba:le 804 May 9, 1980 I Barton Buffalo Forge Chromalox (Dave Ray 820 883 876 May May May 9, 1980 3, 1980 22, 1980 I & Associates) Cutler Hammer Dresser Industries 836 784 May 15, 1980 May 8, 1980 Edwin L. Wiegland 87# May 22, 1980 I (Dave Ray & Associates) Penwal 785 834 May 8, 1980 May 13, 1980 Electromotive Division I G.M. General Electric (cable) General Electric (motors) 911 912 May 29, 1980 May 29, 1980 913 May 29, 1980 I GE (neutron monitoring preamplifiers) Foxboro 904 May 22, 1980 Gould 835 May 13, 1980 Harlo 877 May 22, 1980 Leeds & Northrup 893 May 22, 1980 Limitorque 914 May 29, 1980 I Magnetrol Mercoid Namco Snap-Lock 813 815 845 May May May 13, 13, 15, 1980 1980 1980 Raychem Corporation 915 May 29, 1980 I Simplex Wire & Cable Company 892 May 22, 1980 Static-O-Ring 846 May 15, 1980 I United Electric Control Versa Yarway 848 847 833 May May May 16, 15, 13, 1980 1980 1980 Temptron 842 May 13, 1980 Static-O-Ring (2) 916 May 29, 1980 Essex 917 May 29, 1980 Portor Company 918 May 29, 1980 I H.K. (Limitorque Peerless) I I I
M M M M M M M M M M M - M M Revision 1 November 1, 1980
, TABLE 4-1 TABULATION OF FIELD INSPECTION DATA FOR ELECTRICAL BOXES INSIDE THE DRYNELL QUAD CITIES UNIT 2 Box Location Component Number Type Elev Azim Terminal Block Type _
Remarks AO-2-203-1A 79-01B-2 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-1A 79-01B-7 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-1B 79-018-1 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-1B 79-018-8 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-lC 79-01B-4 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-lc 79-01B-5 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-lD 79-OlB-3 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-203-1D 79-01B-6 TB 595 0 Could not be identified, similar to Allen Bradley AO-2-220-1 None NA NA NA NA No box in drywell equip-ment located between MSIVs MO-2-1001-50 NA NA NA NA NA Could not be located MO-2-1001-63 79-018-15 PB 647 15 NA
m m M M M M M M M M M M M M Revision 1 November 1, 1980 TABLE 4-1 (Continued) Box Location Component Number Type Elev Azim Terminal Block Type Remarks 79-01B-16 PB 613 175 NA Three feet below grating, MO-2-1201-2 could not be opened MO-2-1301-16 79-01B-22 Conduit 600 0 NA Not opened pull box MO-2-1301-16 79-018-23 Conduit 600 0 NA Not opened pull box MO-2-2301-4 79-OlB-24 PB 600 110 NA Iligh location, difficult to reach MO-2-202-5A 79-01B-10 PB 595 260 IIA MO-2-202-5B 79-01B-21 PB 595 50 NA MO-2-202-6A 79-018-12 PB 615 175 NA MO-2-202-6B 79-018-11 PB 615 225 MA Two cables had plugs with four female pins, cables not continued. MO-2-202-9A NA NA NA NA NA Valve could not be located. MO-2-202-9B NA NA NA NA NA Valve cot:ld not be located. MO-2-220-4A NA NA 590 180 NA Not accessible MO-2-220-4B 79-01B-9 PB 600 30 NA One flex loose; electrical foreman notified
M M M M M M M M M Revision 0 June 2, 1980 TABLE 4-1 (Continued) Box Location Component Number Type Elev Azim Terminal Block Type Remarks POS-2-220-51 NA NA NA NA NA Valve could not be located. POS-2-220-52 NA NA NA NA NA Valve could not be located. AO-2-220-44 79-018-17 PB 618 100 NA AO-2-203-3A NA NA NA NA NA Equipment could not be located. AO-2-203-3B 79-018-14 PB 619 300 NA AO-2-203-3C 79-018-13 PB 619 260 NA PB could not be opened, air duct obstruction. AO-2-203-3D 79-018-19 PB 618 NA NA Box was not opened. AO-2-203-3E 79-01B-18 PB 618 5 NA AO-2-1001-33A 79-01B-26 PB 605 30 NA AO-2-1001-33B 79-01B-25 PB 595 220 NA Screws and connectors were found in box. Electrician cleaned the box.
_..___..____..._.___=_-._m2mmm __ -_ ._.. I l I I l i APPENDIX A.1 l l QUAD CITIES UNIT 1 AND COMMON SYSTEMS LIST I
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I Facility: Unit: Quad Cities 1 Revision 4 November 1, 1980 50-254 I Docket: QUAD CITIES 1 Systems or Portions of Systems Required Following a LOCA or Other HELB
- 1. Reactor Protection System
- 2. Core Spray System
- 3. High-Pressure Coolant Injection System
- 4. Auto Depressurization System / Main Steam System
- 5. Residual Heat Removal / Containment Spray System
- 6. Pressure Suppression System I 7. Standby Gas Treatment System
- 8. Deleted (Included with 1)
- 9. Service Water System
- 10. Diesel Oil Piping System
- 11. Containment Isolation System *
- 12. Control Rod Drive Hydraulic System
- 13. Reactor (Nuclear Boiler) Recirculation System
- 14. Process Radiation Monitoring System 15.A Reactor Building Ventilation 15.B Control Room HVAC
- 16. Standby Alternating Current Power
- 17. Standby Direct Current Power
- 18. Reactor Core Isolation Cooling System (RCIC)
- 19. General Use Electrical Equipment I
- Containment isolation includes all components in various systems performing the containment isolation function. !
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'I ,I APPENDIX A.2 l QUAD CITIES UNIT 2 SYSTEMS LIST ,l !I !I !I E I : i 4 I .I-I
l Revision 4 W Facility: Quad Cities November 1, 1980 Unit: 2 Docket: 50-265 QUAD CITIES 2 I Systems or Portions of Systems Required Following a LOCA, or Other HELB
- 1. Reactor Protection System
- 2. Core Spray System
- 3. High-Pressure Coolant Injection System
- 4. Auto Depressurization System / Main Steam System
- 5. Residual Heat Removal / Containment Spray System
- 6. Pressure Suppression System
- 7. Standby Gas Treatment System (this system is common to both units and is included with Unit 1)
- 8. Deleted (Included with 1)
- 9. Service Water System
- 10. Diesel Oil Piping System
- 11. Containment Isolation System *
- 12. Control Rod Drive Hydraulic System
- 13. Reactor (Nuclee Boiler) Recirculation System
- 14. Process Radiation Monitoring System 15.A Reactor Building Ventilation 15.B Control Room HVAC (this system is common to both units and is included with Unit 1)
- 16. Standby Alternating Current Power
- 17. Standby Direct Current Power
- 18. Reactor Core Isolation Cooling System (RCIC)
- 19. General Use Electrical Equipment (this system is common to both units and is included with Unit 1)
- Containment isolation includes all components in various i systems performing the containment isolation function.
I
W W M M M M M M M M M W M M W M- W W W l I Revision IJovember 1, 1980 TABLE A-1 SYSTEMS ( AflD ASSOCIATED COMPO?IEt1TS REFERE?!CED I?J APPEf4 DIX B) REQUIRED FOLLONIt!G EACII POSTULATED ACCIDE!JT( y ) LOCA LOCA MSLB MSLB Feedwater IIPCI RWCU RCIC Large Small Inside Outside Line Line Line Line System Break Break Drywell Drywell Break Break Break Break Reactor Protection X X X X X X Core Spray X X X X X IIPCI X X X (2) ADS /MS X X X RIIR/ Containment Spray X X X X X Pressure Suppression X X X SGTS X X X X X Service Water X X X X X Diesel Oil Piping X X X X X Containment Isolation X X X X X (3) Control Rod Drive X X X X X Process Radiation Monitoring X X X X X X X X RB IIVAC X X X X X X X X Control Room IIVAC X X X X X X X X Standby AC Power X X X X X Standby DC Power X X X X X RCIC (2) General Use Electrical X X X X X X X X (1) This table is provided to identify those systems which must be qualified for each postulated accident environment. (2) Items required are the break detection devices and isolation valves. (3) Items required are the RWCU isolation valves.
i I E I !3 I I APPENDIX B.1 QUAD CITIES UNIT 1 AND COMMON SPECIFIC AND GENERAL USE COMPONENTS LIST SORTED BY SYSTEM i I I I I I I I I I I
Facility: Quad Cities Revision 4 Unit: 1 November 1, 1980 Docket: 50-254 i MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUt1CTION UNDEh POSTULATED ACCIDENT CONDITIONS I Reactor Protection System ( } SYSTEM: SPECIFIC COMPOt1ENTS ASSOCIATED WITil ABOVE SYSTEM Location Inside Outside jW Plant Identification Primary Primary Contain- Contain-
!! umber Generic Name (**) ment ment
*LS-1-302-82A,B,C,D Level Switch (M-41) X
-PG-1-603-4rrB , C , D Pressure Switch, Low ("-li) X( }
*AO-1-203-1A,B,C,D Globe Valve, Air Operated X (M-13)
W *AO-1-203-2A,B,C,D Globe Valve, Air Operated X (M-13)
*PS-1-1001-88A,B,C,D Pressure Switch, High (M-34) X
*PS-1-263-55A,B,C,D Pressure Switch (M-35) X
*LIS-1-263-57A,B Level Indication Switch X (M-35)
*LIS-1-263-58A,B Level Indication Switch X (M-35)
RAM-1-0 7 5 2 - A ,3, C , O IPJi, Preamp 4-i44cr X(3) FrrF rGrH RAM-1-G742A rBrGrD SR", Preamplificr X(
***TE-1-1291-60A,B, Temperature Element X C,D,C,F,G,H These components are listed for information only.
. Their qualification evaluation is covered with their respective systems.
** Shows P&ID number of respective system.
*** Area Temperature Detectors for Reactor Cleanup System i
I
h Revision 4 i November 1, 1980 Page 2 SYSTEM: Reactor Protection System I I (Con.:inued) l (1) This listing includes additional miscellaneous components i required to detect or mitigate the specified accidents. l Some of these components are not part of the reactor l protection sys tem. ! (2) Thet.2 components have been deleted because, although they l initiate a scram, the scram is an anticipatory scram for i conditions not related to the postulated accidents. (3) These components have been deleted because their function is j to monitor transients not associated with the postulated ! accidents. i !I ! lI 1 1 .I 4 l
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l 4 i i il lE \ l
Facility: Quad Cities Revision 3 Unit: 1 June 2, 1980
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Docket: 50-254 1
- E
\
- MASTER LIST l
l CLASS lE ELEC';'RICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDE!!T CONDITIONS l SYSTEM: Core Spray j im SPECIFIC COMPONEf1TS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside 'g Primary Primary
,5 Plant Iaentieication Contain- Contain- i j Number Generic Name ment ment I
MO-1-1402-25A,B Gate Valve, Motor Operated X l i , MO-1-1402-24A,B Gate Valve, Motor Operated X ; a MO-1-1402-4A,B Globe Valve, Motor Operated X FT-1-1461-A,B Flow Transmitter X PT-1-1460-A,B Pressure Transmitter X l-1401A,B Core Spray Pump X J MO-1-1402-3A,B Gate Valve, Motor Operated X FS-1-1464-A,B Flow Switch X in MO-1-1402-38A,B Gate Valve, Motor Operated X i )g PS-1-1462-A,B,C,D Pressure Switch X il !I II il I it l
Facility: Quad Cities Revision 3 Unit: 1 June 2, 1980 Docket: 50-254 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REOUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: !!igh-Pressure Coolant Injection SPECIFIC COMPONENTS ASSOCI ATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary
.I Plant Identification Contain- Contain-Number Generic Name ment ment MO-1-2301-4 Gate Valve, Motor Operated X DPIS-1-2352 Differential Pressure X Indicating Switch DPIS-1-2353 Differential Pressure X Indicating Switch PS-1-2389A,3,C,D Pressure Switch (Low) X MO-1-2301-5 Gate Valve, Motor Operated X MO-1-2301-3 Gate Valve, Motor Operated X SV-12 Turbine Stop Valve X MO-1-2301-14 Globe Valve, Motor Operattd X PT-1-2359 Pressure Transmitter X FT-1-2358 Plow *ransmitter X MO-1-2301-9 Gate Valve, Motor Operated X (dc)
MO-1-2301-6 Gate Valve, Motor Operated X (de) I MO-1-2301-10 Globe Valve, Motor Operated X MO-1-2301-48 Gate Valve, Motor Operated X MO-1-2301-49 Gate Valve, Motor Operated X None Turbine Gland Seal Conden- X sate Hotwell Drain Pump , None Gland Steam Exhauster Pan X I
- Revision 4 l November 1, 1980 )
SYSTEM: liigh 'ressure Coolant Injection (Continued) Page 2 j SPECIFIC COMPONEf1TS ASSOCIATED WITH ABOVE SYSTEM l Location l Ins 1Je Outside Primary Primary Plant Identification Contain- Contain-Number Generic Name ment ment PT-1-2382 Pressure Transmitter X MO-1-2301-35 Gate Valve, Motor Operated X and Position Switch MO-1-2301-8 Gate Valve, Motor Operated X MO-1-2301-15 Gate Valve, Motor Operated X TS-1-2370A,B,C,D Temperature Switch X TS-1-2371A,B,C,D Temperature Switch X TS-1-2372A,B,C,D Temperature Switch X TS-1-2373A,B,C,D Temperature Switch X MO-1-2301-36 Gate Valve, Motor Operated X E and Position Switch
.g S0-1-2301-30 Air Operated Valve (Solenoid) X POS-1-2-M4-40 Al-r--Opecated Va1yc ( Poel-t-ton X II)
Switch) S0-1-2301-29 Air Operated Valve (Solenoid) X POS-14304-39 " E-r--Oper+te' Va1vc ( Parri-t ien
. Y II) 6 .I S0-1-2301-65 Air Operated Valve (Solenoid) X POS---1 2 3G1--6 5 Ai-r--Opeeated--Vc 1 y c ( Pae-i-t icn X II)
Swi-teld S0-1-2301-64 Air Operated Valve (Solenoid) X POS-1-3-301 -6 4 Ai-r--Oper+te' Va1vc (Pccition X III 6wi-tete LS-1/2-2350-A,B,C,D Level Switch X LS-1-2351-A,B Level Switch X X I
r Revision 4 flovember 1, 1980 SYSTEM: liigh-Pressure Coolant Injection (Continued) Page 3
- I j
SPECIFIC COMPONEt1TS ASSOCIATED WITil ABOVE SYSTEM ,E Location (elevation)
- W Inside outside Primary Primary l Plant Identification Contain- Contain-l 1; umber Generic flame ment ment PS-1-2354 Flow Switch X PS-1-2360 Pressure Switch X
, PS-1-2368A,B Pressure Switch X i tJone Motor Speed Changer X TJone Motor Gear Unit lI 11one Emergency Oil Pump X X None Auxiliary Oil Pump X l-2386 If PCI Motor Control X Signal Convertor LS-LCS-1 Level Switch X (1) This component has been deleted because it is used for position indication only and failure of the switch will not affect the associated valve control circuit.
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Facility: Ouad Cities Revision 4 Unit: 1 November 1, 1980 Docket: 50-254 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Auto Depressurization/ Main Steam SPECIFIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM I Location Inside Outside I Plant Identification Number Generic Name Primary Primary Contain- Contain-ment ment 1-203-3A Target Rock Valve and X Associated Solenoid I 1-203-3B,C,D,E Electromatic Relief Valve and Associated Solenoid Valve X AO-1-203-1A,B,C,D Main Steam Isolation X Valve with Associated Solenoid Valves POhl-2G3-1A rRrC , D Main Stcam Ico-let-ion v I } Valve, Pocition Switch MO-1-220-1 Globe Valve, Motor X Operated TS-1-261-15A,B,C,D Temperature Switch X 16A,B,C,D 17A,B,C,D 18A,B,C,D MO-1-220-2 Globe Valve, Motor X Operated AO-1-203-2A,B,C,D Main Steam Isolation X Valve with Associated I Solenoid Valve PO41-M 2 A , B , C , D "a in Steam--Isol-at-ion vIII Va1yc, "os-i-t-ion Sw i t ch DPIS-1-261-2A,B,C, Differential Pressure X I D , C , F , G , II, J , K , L, M , N,P,R,S Indication Switch P8-1-M1 A , B , C , D Pr+ssurc Switch X III I (1) Thesc components have been deleted because., although they l initiate a scram, the scram is an anticipatcry scram for conditions not related to the postulated accidents.
l Facility: Quad Cities Revision 4 Unit: 1 November 1, 1980 l Docket: 50-254 I I l MASTER LIST l CLASS lE ELECTRICAL EQUIPMEt1T REQUIRED TO FUt1CTIOt1 Ut1 DER POSTULATED ACCIDEllT cot 1DITIOt1S I SYSTEM: Residual !! eat Removal / Containment Spray SPECIFIC COMPOt1Et1TS ASSOCIATED WITli ABOVE SYSTEM Location Inside Outside Primary Primary I Plant Identification Contain- Contain-13umbe r Generic t1ame ment ment PT-1-1043A,B Pressure Transmitter X MO-1-1001-7 A,B,C,D Gate Valve, Motor Operated X I PS-1-1053 A,B,C,D,E, F , II, J Pressure Switch X MO-1-1001-18A,B Gate Valve, Motor Operated X MO-1-1001-36A,B Globe Valve, Motor Operated X
.I MO-1-1001-37A,B Globe Valve, Motor Operated X MO-1-1001-28A,B Globe Valve, Motor Operated X MO-1-1001-34A,B Gate Valve, Motor Operated X MO-l-1001-29A,B Gate Valve, Motor Operated X MO-1-1001-26A,B Gate Valve, Motor Operated X MO-1-1001-23A,B Gate Valve, Motor Operated X FT-1-1051A,B Flow Transmitter X MO-1-1001-63 Gate Valve, Motor Operated X MO-l-1001-60 Gate Valve, Motor Operated X FT-1-1049A,B Flow Transmitter X I DPIS-1-1001-81A,B Differential Pressure Indicating Switch X
I I
Revision 4 j November 1, 1980 l Page 2 SYSTEM: Residual IIcat Removal / Containment Spray (Continued)
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SPECIFIC COMPONENTS ASSOCIATED WITl! ABOVE SYSTEM _ { Location ! Inside Outside j Primary Primary
- Plant Identification Contain- Contain-j Number Generic Name ment ment MO-1-1001-50 Gate Valve, Motor Operated X i
! MO-1-1001-47 Gate Valve, Motor Operated X i 4 I MO-1-1001-19A,B Gate Valve, Motor Operated X MO-1-1001-16A,B Globe Valve, Motor Operated X MO-1-1001-5A,B Globe Valve, Motor Operated X FT-1-1042A,B Flow Transmitter X i
!g PT-1-1044A,B Pressure Transmitter X
- g Level Switch (High) i LS-1-4941-2A,B,C X l-1001-65A,B,C,D RIIR Service Water Pumps and X
- Motors 3 MO-1-1001-20,21 Gate Valve, Motor Operated X j
1-1002A,B,C,D RIIR Pump X MO-1-1001-4A,B Motor Operated Valve X MO-1-1001-185A,B Motor Operated Valve X g DPS-1-1001-78A,B Differential Pressure X i Switch 1-5745A,B,C,D RIIR Service Water Pump X . Cubical Ccolers I . I I I I
Facility: Quad Cities Revision 4 Unit: 1 November 1, 1980 Docket: 50-254 MASTER LIST I CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Pressure Suppression Piping SPECIPIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside 'I Plant Identification Number Generic Narc Primary Contain-ment Primary Contain-ment 50-1-1601-69 Solenoid Valve X g POG-1460b61 Ai-r-Oper-ated-Va 1 vc ( Posi-t-icn X III E s*-i-te' r)- S0-1-1601-68 Solenoid Valve X POB-1460b6G- Ai-r-Operated Va1vc (Pccition X I1I CWiteh) SG-1-8801A,B,C,D, Air Operated Valve (Solenoid) X II) POS-1-88&lArB rCrD "i-r-Oper-ated Va1vc
. X
-(-Posi-t-ion SuiteM SO-1-8802A,B,C,D Air Operated Valve (Solenoid) X II}
POS-1-86GGAT BrGrD Air Opcrat-ed-Vc1vc X fPo&i-t-ion SuiteM PS-1-1001-83A,B,C,D Pressure Switch X PS-1-1001-88A,B,C,D Pressure Switch X PS-1-1001-89A,B,C,D Pressure Switch X PS-1-1001-90A,B,C,D Pressure Switch X SO-1-1601-52A,B Solenoid Valve X POS-146&l-2-3r24 Ai+-Oper-ated Va1vc ( Pos-1-t-ion d1I l Swi-tom SO-1-1601-70 Solenoid Valve X POS-1-1-6Gl-G2 Ai-r-Operated Valvc (P0&ition M( I . Swi-t-eM l S; 1-1601-71 Solenoid Valve X I l
Revision 4 November 1, 1980 SYSTEM: Pressure Suppression Piping (Continued) Page 2 SPECIPIC COMPOf1EtJTS ASSOCIATED WITH ABOVE SYSTEM Location I Inside Outside Primary Primary Plant Identification Contain- Contain-Number Generic flame ment ment Pos-1-160-1 = 6 3 Ai-r-operatel-Val-vc ( POc i t-icn X(1) 6*i-t+ M PT-1-1426 Pressure-TrenemFbter X I) S0-1-1601-51A,B Solenoid Valve X POS-1-14G-1-2-1, 2 2 Ai+-Operetel Va1vc (PO3ition X( } 6*EteM S0-1-8803 Air Operated Valve X (Solenoid) S0-1-8804 Air Operated Valve X (Solenoid) I S0-1-1601-65 Solenoid Valve X POS-1-16G1-56 "i-r--Oper+ted Va1vc (Pasibien
. X II)
Gwkte M S0-1-1601-67 Solenoid Valve X POG-1-MG1 - 5 9 ^ i-r--Operated -Va1vc ( Posit-ion X I1I SwiteM SO-1-1601-66 Solenoid Valve X
.lW POG-1-MGl-68 A @ sted Valve ( Posit-ion Swi-tem X
III MO-1-1601-57 Globe Valve, Motor Operated X S0-1-1601-50A,B ~ Solenoid Valve X POS-l-MGl-20 A , B A i-r-Opera tel--Val-v e-(-Posi+ ion X III Swi-tem PS-1-1622A,B Pressure Switch X 1rT-1-M 26 Levc1 Transaibt-e- v(3) 1 AO-1-1601-55 Gate Valve, Air Operated X (Solenoid) I I
- I Revision 4 tiovember 1, 1980 Proc.sure Suppression Piping (Continued) Page 3 SYSTEM:
0'ECIPIC COMPOt1EtiTS ASSOCIATED WITH ABOVE SYSTEM Location .g Inside Outside g Primary Primary Contain- Contain-
- Plant Identification Number Generic Name ment ment GatMalNe r-Ai-r-Ope-r-at-ed X(1
. PGhl-1404-55 4-Poei+ ion Oi TOM X
TE-1-1630A,B Temperature Element X TE-1-1631A,B Temperature Element (1) This conponent has been deleted because it is used for Imsition indication only and failure of the switch will
- not affect the associated valve control circuit.
'E (2) This component has been deicted because its function is required uring normal operation only.
g
- (3) This component has been deleted because it provides indication only.
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Facility Quad Cities Revision 3 Unit: 1 June 2, 1980 Docket: 50-254 MASTER LIST I CLASS lE ELECTRICAL EQUIPMENT Rr'0UIRED TO FUNCTIO!! UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM : Standby Gas Treatment SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name Primary Contain-ment Primary Contain-ment MO-1-7503 Butterfly Valve, Motor X Operated MO-2-7503 Butterfly Valve, Motor X Operated I MO-1/2 '504A,B Butterfly Valve, Motor Operated X MO-1/2-7505A,B Butterfly Valve, Motor X I Operated TSH-1/2-7541-11A,B Temperature S itch X 1/2-A-7503 Electric Air Heater X 1/2-B-7503 Electric Air Heater X 1/2-A-7506 Pan X 1/2-B-7506 Pan X AO-1/2-7510A,B Butterfly Valve, Air X Operated (Solenoid) MO-1/2-7507A,B Butterfly Valve, Motor X Operated FT-1/2-7541-6A,B Flow Transmitter X FSL-1/2-7541-8A,B Flow Switch (Low) X FSL-1/2-7541-33A,B Flow Switch (Low) X iI PT-1/2-7541-1A,B Flow Transmitter X 2212-29A,B Local Control Panel X 1
Facility: Quad Cities Revision 3 June 2, 1980 Unit: 1 50-254 I Docket: MASTER LT.ST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Service Water I SPECIFIC COMPONEtJTS ASSOCIATED WITil ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name Primary Contain-ment Primary Contain-ment 1-5746B South RilR !!x Room X Emergency Cooler I 1-5746A North RIIR lix Room Emergency Cooler X I South Core Spray 1-5748B X Equipment Room Emer-gency Cooler I 1-5748A North Core Spray Equipment Room Emer-gency Cooler X 1-5747 IIPCI Room X Emergency Cooler 1&l/2-3903 Diesel Generator X Cooling Water Pumps I 1&l/2-5749 Diesel Generator Cooling Pump Cubicle Coolers X I 1 I I l I I I l
Facility: Quad Cities Revision 4 Unit: 1 flovember 1, 1980 l Docket: 50-254 ! MASTER LIST l l CLASS lE ELECTRICAL EQUIPMENT I REQUIRED TO FUllCTIOtl UNDER POSTULATED ACCIDENT CONDITIONS il) SYSTEM : Diesel Oil Piping j SPECIFIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM Location ' l Inside Outside l Primacy Primary Plant IJentification Contain- Contain-l Number Generic Name ment ment 1& 1/2-5203 Diesel Oil Transfer Pump X i LS II/L-1/2-5 2 41-5 Level Switch X !~ S0-1 & 1/2-5201 Solenoid Valve X LS II/L-1 & 1/2-5241-3 Level Switch X e !I II II
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!I II !I lI lI
Facility: Ouad Cities Revision 3 Unit: 1 June 2, 1980 Docket: 50-254 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUt1CTIOtl UNDER POSTULATED ACCIDENT cot 3DITIONS I SYSTEM: Containment Isolation SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name (**) Primary Contain-ment Primary Contain-ment
*AO-1-203-1A,B,C,D Globe Valve, Air Operated X (M-13)
*AO-1-203-2A,B,C,D Globe Valve, Air Operated X (M-13)
- l *MO-1-220-1 Gate Valve, Motor Operated X
- W (M-13)
*MO-1-220-2 Gate Valve, Motor Opera'ced X
.I ( ti-13 )
*AO-1-220-44 Globe Valve, Air Operated X (M-35)
*AO-1-220-45 Globe Valve, Air Operated X (M-35)
*SO-1-305-120 Solenoid Valve X
*SO-1-305-121 Solenoid Valve X
*SO-1-305-122 Solenoid Valve X
*SO-1-305-123 Solenoid Valve X
*MO-1-1031-47 Gate Valve, Motor Operated X lI (M-37)
*MO-1-1001-50 Gate * 've, Motor Operated X (M-3',
*MO-1-1001-37A,B Globe Valve, Motor Opt ated X
*MO-1-1001-26A,B, Gate Valve, Motor Operated X (M-37)
- I I
Revision 3 June 2, 1980 SYSTEM: Containment Isolation (Continued) Page 2 SPECIPIC COMPOtJEfJTS ASSOCIATED WITl! ABOVE SYSTEM Location I Plant Identification Inside Primary Outside Primary Contain- Contain-fiumber Generic flame (**) ment I *MO-1-1001-23A,B Gate Valve, Motor Operated ment X I *MO-1-1001-63 Gate Valve, Motor Operated (M-37) X
*MO-1-1001-60 Gate Valve, Motor Operated X
*MO-1-1001-36A,B Globe Valve, Motor Operated X (M-37)
*MO-1-1001-34A,B Gate Valve, Motor Operated X (M-37)
*MO-1-1001-29A,B Gate Valve, Motor Operated X (M-37)
*MO-1-1001-28A,B Globe Valve, Motor Operated X (M-37)
I *MO-1-1001-7A,B,C,D Gate Valve, Motor Operated (M-37) X I *MO-1-1001-20 Gate Valve, Motor Operated (M-37) X
*MO-1-1001-21 Gate Valve, Motor Operated X (M-37)
MO-1-1201-2 Gate Valve, Motor Operated X MO-1-1201-5 Gate Valve, Motor Operated X
*MO-1-1301-16
,I Cate Valve, Motor Operated (M-50) X )
)
*MO-1-1301-17 Gate Valve, Motor Operated X (M-50)
*AO-1-1301-12,13 Globe Valve, Air Operated X
*AO-1-1301-34,35 Globe Valve, Air Operated X (M-50)
I I !I
l m Revision 4 November 1, 1980 Containment Isolation (Continued) Page 3 SYSTEM: g SPECIFIC COMPOf1EtJTS ASSOCIATED WITH ABOVE SYSTEM Incation
- g Inside Outside Primary Primary Contain- Contain-I Plant Identification tiumber Generic tiame (**) Ire r. ; ment Gate Valve, Motor Operated X
*MO-1-1301-25 I (M-50)
Gate Valve, Motor Operated X
*MO-1-1402-24A,B I *MO-1-1402-25A,B (M-36)
Gate Valve, Motor Operated X (M-36) Globe Valve, Motor Operated X
*MO-1-1402-4A,B (M-36)
*MO-1-1402-3A,B Gate Valve, Motor Operated X (M-36)
I AO-1-2001-3,4 Air Operated Valve (Solenoid) X X II) POS-14041-1, d. ^ i-rDat+1 Va1vc (Pccitior.
'I 6+kt+M AO-1-2001-15,16 Air Operated Valve (Solenoid) X III Pos-14004-lbl4 ^ kr-Operated Va1yc ( Pos4-t4on X
6*ktoM
= *MO-1-2301-4 Gate Valve, Motor Operated X (M-46)
Gate Valve, Motor Operated X
*MO-1-2301-5 (M-46)
*AO-1-2301-29,30 Globe Valve, Air Operated X 64,65 (M-46)
I *MO-1-2301-36 Gate Valve, Motor Operated (M-46) X 1-700-736B,C,D,E,P Squib Shear Valve X l-700-733B,C,D,E,P Solenoid Ball Valve X Gate Valve, Motor Operated X MO-1-3702 (M-33) Gate Valve, Motor Operated X l MO-1-3703 (M-33)
Revision 4 November 1, 1980 SYSTEM: Containment Isolation (Continued) Page 4 SPECIPIC COMPOt1EtiTS ASSOCIATED WITil ABOVE SYSTEM Location I Inside Primary Outside Primary Plant Identification Contain- Contain-I tiumber Genoric flame (**) Gate Valve, Motor Operated ment ment X MO-1-3706 (M-33)
*AO-1-1601-21,22 Butterfly Valve, Air X Operated Butterfly Valve, Air X
*AO-1-1601-23 Operated Gate Valve, Air Operated X
*AO-1-1601-61 I *AO-1-1601-56,60,24 Butterfly Valve, Air Operated X
S0-1-4720 Air Operated Valve (Solenoid) X DOS--I -4 7 2 0 ^ 1-r-operet+4-Va 1vc ( Pcci t4cn X III 6*i-teh-)- I S0-1-4721 Air Operated Valve (Solenoid) X Pos-1--4M1 " 1-r-operat+d Va1vc ( Pasi+ier. X I1) l W 6*i-teh-)- I
- These components are listed here for information only.
Their qualification evaluation is covered with their respective systems.
** Shows P&ID number of respective system (1) This component has been deleted because it is used for position indication only and failure of the switch will not affect the associated valve control circuit.
I I lI 1 lI
W Facility: Quad Cities Revision 3 Unit: 1 June 2, 1980 50-254 I Docket: MASTER LIST
-I CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UND?.R POSTULATED ACCIDENT CONDITIONS I SYSTEM: Control Rod Drive SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name Primary ment Primary Contain- Contain-ment Solenoid Valve X
*SO-1-305-ll7
*SO-1-305-ll8 Solenoid Valve X 4
S0-1-302-20A,B Solenoid Valve X S0-1-302-19A,B Solenoid Valve X LS-1-302-82A,B,C,D, Level Switch X POS-1-302-21A,D Air Operated Valve X (Position Switch) POS-1-302-22 Air Operated Valve X (Position Switch)
*SO-1-305-120 Solenoid Valve X
*SO-1-305-121 Solenoid Valve X
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*SO-1-305-122 Solenoid Valve X
*SO-1-305-123 Solenoid Valve X
- Typical of 177 valves
Pacility: Quad Cities Revision 4 { Unit: 1 November 1, 1980 l l I Docket: 50-254 i MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor (Nuclear Boiler) Recirculation SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name Primary ment Primary Contain- Contain-ment LITS-1-263-73A,B Level Indicating X Transmitter Switch PS-1-263-lllA,B,C,D Pressure Switch X M-l = 5 4 7 A , B Precourc Trancmitter X III III LT-1-545-A,3 Level Traneeitter X PT-1---562 Prc30ure Tr-ancmitter X III PS-1-263-52A,B Pressure Switch X PS-1-263-55A,B,C,D Pressure Switch X hT-1-263 51 Level Trancmitter X(2) POS NO=51 Clcbc Valve, Air X (3) Operated (Pocition
~
I AC 1 22G-51 Clebe Valve, Air X (3) Oper-ated ( Sc1eno-id I valve) (3) Pos-1-M 0 -5 2 Clebe Valve, "ir . X Operated (Pecition Switch) (3) I s, AO-1--320 - 5 2 C1cbc valve, Air Operated (Sciencid W l-V e 4
Revision 4 November 1, 1980 Page 2 SYSTEM: Reactor (Nuclear Boiler) Recirculation (Continued) I SPECIPIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain- Contain-Number Generic Name ment ment LITS-1-263-59A,B Level Indicator X Transmitter Switch LIS-1-263-57A,B Level Indicator Switch X LIS-1-263-72A,B,C,D Level Indicator Switch X LIS-1-263-58A,B Level Indicator Switch X
" I4I POS-1-220-4* Chobe Valve, ^ br . .
Operated ( Pos itieu
-e..:
- - - us. . ,s I AO-1-220-44 Globe Valve, Air Operated (Solenoid Valve)
X PCS-1---220 45 Clobc Valve, "ir X Operated (Pocition S'JitCh) I AO-1-220-45 Globe Valve, Air Operated (Solenoid X Valve) MO-1-202-5A,B Motor Operated Valve X PS-1-261-23A,B Pressure Switch X DPIS-1-261-34A,B,C,D Differential Pressure X Switch DPIS-1-261-35A,B,C,D Differential Pressure X E,F,G,H Switch MG--l-2b 2 4 A , S "o t<>r--Oper-ated Va 1y c X (5) MO-1-202-6A,B Motor Operated Valve X MO-1-202-9A,B Motor Operated Valve X l l
Revision 4 November 1, 1980 l Page 3 i SYSTEM: Reactor (Nuclear Boiler) Recirculation (Continued) (1) This component has been deleted because it is required I for control of the feedwater regulation valve during normal operation only. ; (2) This component has been deleted because it provides indication only. l 1 I (3) This piping system does not penetrate the drywell, therefore this component is not required for containment isolation. j (4) This component has been deleted because it is used for I position indication only and failure of the switch will not affect the associated valve control circuit. (5) These valves have been deleted because they are wired out to remain inoperable, and their function is not required following an accident. I I I I I I I E I l 1 I ! I
Facility: Ouad Cities Revision 3 June 2, 1980 Unit: 1 Docket: 50-254 MASTER LIST
- E CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS ll SYSTEM
- Process Radiation Monitoring SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location 4
Inside Outside I Plant Identification Number Generic Name Ptimary Contain-ment Primary Contain-ment RE-1-1735A,B Rx Building Ventilation :: Exhaust Radiation Element I
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I I T
Facility: Quad Cities Revision 3 Unit: 1 June 2, 1980 Docket: 50-254 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS
- I SYSTEM
- Reactor Building Ventilation SPECIPIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain- Contain-Number Generic Name ment ment AO-1-5742A,B Butterfly Valve, Air X Operated (Solenoid)
AO-1-5741A,B Butterfly Valve, Air X Operated (Solenoid) I I E i I I I I ; .I I I
g Facility: Quad Cities Revision 3 Unit: 1 June 2, 1980 Docket: 50-254 I MASTER LIST I CLA~S lE ELECTRICAL EQUIPMENT REQUIRED TO FUNC'ItON UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Control Room IIVAC SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain- Contain-Number Generic Name ment ment 1/2-5795-10 Supply Air Fan X 1/2-5795-30 Return Air Fan X 1/2-9472-23 Damper X 1/2-9472-24 Damper X 1/2-5772-57 Damper X 1/2-C-5732 Water Chillers X None Chilled Water Pumps X S0-1/2-9441-003 Solenoid valve X I I I I I I I I
I Facility: Unit: Quad Cities 1 Revision 3 June 2, 1980 Docket: 50-254 MASTER LIST I CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Standby Alternating Current Power SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name Primary Contain-ment Primary Contain-ment X 1-6601 Standby Diesel Generator Standby Diesel Generator X 1/2-6601
- X SWGR 13-1 4.16 kV Switchgear SWGR 14-1 4.16 kV Switchgear X 480 V Switchgear X SWGR 18 SWGR 19 480 V Switchgear X MCC 18-1A,B 480 V Rx Building MCC X
.I MCC 18-2 480 V Turbine Building MCC X MCC 18-3 480 V Turbine Building MCC X 480 V Rx Building MCC X MCC 18/19-5 MCC 19-1 4?0 V Rx Building MCC X MCC 19-2 480 V Turbine Building MCC X MCC 19-3 480 V Rx Building MCC X MCC 19-4 480 V Rx Building MCC X MCC 19-6 480 V Rx Building MCC X I I ;
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Revision 2 June 2, 1980 SYSTEM: Standby Alternating Current Power (Continued) SPECIFIC COMPOf1ENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Cutside I Plant Identification Number Generic Name Primary ment Primary Contain- Contain-ment RPS Bus lA 120 V ac Reactor Protection X System Bus lA RPS Bus 1B 120 V ac Reactor Protection X System Bus 1B g Essential Service Bus 120/240 V ac Essential Service X -E Bus Instrument Bus 120/240 V ac Instrument Bus X Essential Bus MMG Set 120/240 V ac Essential Bus X Supply MMG Set 2251-12, 2212-46 Excitation Cabinet for X D/G l-1/2
- None Engine Control Panel for X D/G 1 2212-32X Engine Control Panel for X D/G 1/2 2251-37,45 Diesel Auxiliary Control X Panel for D/G l-1/2 None Secondary Control Panel X
- E:g D/G l-1/2 None Neutral Grounding Panel X D/G l-1/2 None 4 kV Nonsegregated Bus X
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il
- g 1 I
I Facility: Quad Cities Revision 3 June 2, 1980 I Unit: 1 Docket: 50-254 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Standby Direct Current Power SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location I Plant Identification Inside Primary Contain-Outside Primary Contain-Number Generic Name ment ment 250 V Battery Charger X 250 V Batt Chgr 1 250 V Batt Chgr 1/2 250 V Battery Charger X MCC 1 (Turb Bldg) 250 V dc Turbine Building X MCC 250 V dc Reactor Building X MCC 1A and 1B MCC 250 V Battery 250 V de Battery X
, 125 V Batt Chgr 1 125 V Battery Charger X
, 125 V Batt chgr lA 125 V Battery Charger X 125 V Battery 125 V de Battery X 125 V DCDP 1A 125 V dc Turbine Building X I and 1B Distribution Panel 125 V dc Reactor Building X 125 V DCDP 1 Distribution Panel X 48/24 V Batt 48/24 V Battery 1A and 1B 24 V Ba t t Chg r 24 V Battery Charger X 1A and 1B (+) 24 V Batt Chgr 24 V Battery Charger X 1A and 1B (-) 48/24 V DCDP 48/24 V dc Distribution X 1A and la Panel I I
Facility: Ouad Cities Revision 4 Unit: 1 November 1, 1980 Docket: 50-254 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Reactor Core Isolation Cooling I SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary I Plant Identification Number Generic Name _ _ _ Contain-ment Contain-ment MO-1-1301-17 Gate Valve, Motor Operated X MO-1-1301-16 Gate Valve, Motor Operated X TS-1-1360-14A,B,C,D Temperature Switch X 15A,B,C,D I 16A,B,C,D 17A,B,C,D X DPIS-1-1360-1A,B Differential Pressure I PS-1-1360-9A,B,C,D Indicating Switch Pressure Switch Low X AO-1-1301-34,35 Globe Valve, Air Operated X (Solenoid) III POS H01 34,35 Clebc Valvc, Ai-r-Operated X (I'caition Switch)- I AO-1-1301-12,13 Globe Valve, Air Operated (Solenoid) X III I POS--l-MGI -- 12 ,13 Globe Valve, Air Operated fPosition Switah)- X MO-1-1301-53 Motor Operated Valve X MO-1-1301-60 Motor Operated Valve X (1) These components have been deleted because they are used for I Insition indication only and failure of the switches will not affect the associated valve control circuit. I I I
- Facility
- Quad Cities Revision 4 l Unit: 1 November 1, 1980 '
Docket: 50-254
- MASTER LIST CLASS lE ELECTRICAL EQUIPMENT )
REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS !I S YS'"EM : General Use Electrical Equipment SPECIFIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM Location Inside Outside Primary Primary 4" Plant Identification Contain- Contain-Number Generic Name ment ment Cable 5 kV Power X g Cable 600 V Power and Control X X lg Cable Instruments X X l Cable Thermocouples X X l'lectrical Pene- Iligh-Voltage Power X X tration Electrical Pene- Low-Voltage Power X X tration and Control Electrical Pene- Instruments X X tration Electrical Pene- Thermocouples X X tration Terminal Blocks Terminal Blocks X X il !I lI I I I
a ---,._ .m -..a . - mg.. .a. a . 2 --- - . .a a 4 lI !I lI I II II i i !I 1l APPENDIX B.2 l5 i QUAD CITIES UNIT 2 SPECIFIC AND GENERAL lI USE COMPONENTS LIST SORTED BY SYSTEM ,I i I !I i i e I !I !I lI I I I
Fac il i?.y : Quad Cities Revision 4 Unit: 2 November 1, 1980 Docket: 50-265 MASTER LIST . CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Protection System ( } .l = SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary Contain- Contain- .I Plant Identification Number Generic Name (**) ment ment
*LS-2-302-82A,B,C,D Level Switch (M-83) X PC-2-5G3 .".,B,C,0 Preocurc Switch, Low 'M-51) -M I }
- *AO-2-203-1A,B,C,D Globe Valve, Air Operated X (M-60)
*AO-2-203-2A,B,C,D Glove Valve, Air Operated X (M-60)
*PS-2-1001-88A,B,C,D Pressure Switch, High (M-76) X
*PS-2-263-55A,B,C,D Pressure Switch (M-77) X
*LIS-2-263-57A,B Level Indication Switch X (M-77)
*LIS-2-263-58A,B Level Indication Switch X (M-77)
I RAM-2-0762A,B,C,0 FerF rGrH I-R". , Preamplifier X(3) RAM---2 0 7 5 2 A , B rC ,0 SRM d reamplifier X( }
***TE-2-1291-60A,B, Temperature Element X C ,0, E , P , G , Il I
- These components are listed for information only.
I Their qualification evaluation is covered with their respective sy.* ems.
** Shows P&ID number of respective system.
*** Area temperature detectors for react >r cleanup system I
I
Revision 4 November 1, 1980 Page 2 i [l SYSTEM: Reactor Protection System III (Continued) !I (1) This listing includes additional miscellaneous components j I jg required to detect or mitigate the specified accidents.
- g Some of these components are not part of the reactor protection system.
l (2) These components have been deleted because, although they ' l initiate a scram, the scram is an anticipatory scram for ! conditions not related to the postulated accidents. t (3) These components have been deleted becaut.e their function is i to monitor transients not associated with the postulated accidents.
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Pacility: Quad Cities Revision 3 Unit: 2 June 2, 1980 Docket: 50-265 ,I MASTER LIST
- IW CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS il SYSTEM: Core Spray f SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary l
W Plant Identification Contain- Contain-Number Generic Name ment ment MO-2-1402-25A,B Gate Valve, Motor Operated X MO-2-1402-24A,B Gate Valve, Motor Operated X MO-2-1402-4A,B Globe Valve-Motor Operated X FT-2-1461A,B Flow Transmitter X PT-2-1460A,B Pressure Transmitter X 2-1401A,B Core Spray Pump X MO-2-1402-3A,B Gate Valve, Motor Operated X r
= PS-2-1464A,B Flow Switch X MO-2-1402-38A,B Gate Valve, Motor Operated X PS-2-1462A,B,C,0 Pressure Switch X
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I Facility: Unit: Quad Cities 2 Revision 3 June 2, 1980 Docket: 50-265 MASTER LIST C LASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Iligh-Pressure Coolant Injection SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Primary Primary Contain- Contain-Number Generic Name ment ment MO-2-2301-4 Gate Valve, Motor Operated X I DPIS-2-2352 Differential Pressure Indicating Switch X DPIS-2-2353 Differential Pressure X I Indicating Switch PS-2-2389A,B,C,D Pressure Switch (Low) X MO-2-2301-5 Gate Valve, Motor Operated X MO-2-2301-2 Gate Valve, Motor Operated X SV-12 Turbine Stop Valve X MO-2-2301-14 Globe Valve, Motor Operated X PT-2-2359 Pressure Transmitter X FT-2-2358 Plow Transmitter X Gate Valve, Motor Operated I MO-2-2301-9 X (de) MO-2-2301-6 Gate Valve, Motor Operated X (dci MO-2-2301-10 Globe Valve, Motor Operated X MO-2-2301-48 Gate Valve, Motor Operated X MO-2-2301-49 Gate Valve, Motor Operated X .I None Turbine Gland Seal Conden- X sate Hotwell Drain Pump None Gland Steam Exhauster Fan X -I
l Revision 4 5 November 1, 1980 SYSTEM: Iligh-Pressure Coolant Injection (Continued) Page 2 SPECIFIC COMPONENTS ASSOCIATED WITli ABOVE SYSTEM Location - I Plant Identification Inside Primary Contain-Outside Primary Contain-Number Generic Name ment ment PT-2-2382 Pressure Transmitter X MO-2-2301-35 Gate Valve, Motor Operated X and Position Switch MO-2-2301-8 Gate Valve, Motor Operated X MO-2-2301-15 Gate Valve, Motor Operated X TS-2-2370A,B,C,D Temperature Switch X TS-2-2371A,B,C,D Temperature Switch X TS-2-2372A,B,C,D Temperature Switch X TS-2-2373A,B,C,D Temperature Switch X MO-2-2301-36 Gate Valve, Motor Operated X and Position Switch S0-2-2301-30 Air Operated Valve, Solenoid X S0-2-2301-29 Air Opersted Valve, Solenoid X S0-2-2301-65 Air Operated Valve, Solenoid X S0-2-2301-64 Air Operated Valve, Solenoid X II} Ai-r--Operst4M! Valve , Pccition X I POS 2-230l=30 Gwi-teh X II) POG--2-2-3Ol = 2 0 Air Operated Valve, Pc c R-icn hhh I1I POG-2-23&l-64 Ai-r-Opereted Va1vc, Pas +t-to n X I POR-2-;'304-6 5 "ir Opcrated Va1vc, Pael-t-ic n
. X I1I I Mone Motor Speed Changer X None Motor Gear Unit X i
I
l Revision 4 November 1, 1980 SYSTEM: Ifigh-Pressure Coolant Injection (Continued) Page 3
,I SPECIFIC COMPOt1ENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside !
Primary Primary f Plant Identification Contain- Contain- l
?! umber Generic flame ment ment None Emergency Oil Pump X tione Auxiliary Oil Pump X L3-2-2351A,B Level Switch X FS-2-2354 Flow Switch X lI PS-2-2360 Pressure Switch X PS-2-2368A,B Pressure X 2-23C6 IIPC 4 Motor Control Signal X Convertor LS-LCS-1 X Level Switch (1) This component has been deleted because it is used for position indication only and failure of the switch will not affect the associated valve control circuit.
I I I I I I I I I l
Revision 4 Facility: Quad Cities November 1, 1980 Unit: 2 50-265 I Docket: MASTER LIST I CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Auto Depressurization/ Main Steam SPECIFIC COMPONENTS ASSOCIATED WITli ABOVE SYSTEM Location Inside Outside Primary Primary Contain- Contain-Plant Identification Generic Name ment ment Number Target Rock Valve and X 2-203-3A Associated Solenoid X 2-203-3B,C,D,E Electromatic Relief Valve and Associated Solenoid Valve I AO-2-203-1A,B,C,D Main Steam Isolation Valve with Associated X Solenoid Valves Globe Valve, Motor X MO-2-220-1 Operated X TS-2-261-15A,B,C,D Temperature Switch 16A,G,C,D I 17A,B,C,D 18A,B,C,D X Globe Valve, Motor I MO-2-220-2 Operated Main Steam Isolation X AO-2-203-2A,B,C,D I Valve with Associated Solenoid Valve X I DPIS-2-261-2A,B,C, D , E , F , G , il , J , K , L e M , N,P,R,S Differential Pressure Indication Switch III PGG-- 2 20 1 A , S ,C,0 "a in St-eam-Isolat4cn Valve , X Pe&i-t-icn Sw i t-eh v.I 1 ) I POG-2-GO-3-2 A , B , C , D "ain Steam Icciat4cn Valve, Posi+ ion-Swi-teh PG-2-264-30A,n,C,D Preocure Switch F(l) (1) These components have been deleted because, although they initiate a scram, the scram is an anticipatory scram for I conditions not related to the postulated accidents. i l
Facility: Ouad Cities Revision 4 Unit: 2 November 1, 1980 Docket: 50-265 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS
. SYSTEM: Residual Heat Removal / Containment Spray
.g SPECIFIC COMPONENTS iSSOCIATED WITH ABOVE SYSTEM
' c^ti n E Inside Outside Primary Primary Plant Identification Contain- Contain-Number Generic Name ment ment PT-2-1043A,B Pressure Transmitter X MO-2-1001-7A,B,C,D Gate Valve, Motor Operated X PS-2-10 5 3 A , B , C , D, E , Pressure Switch X F,Hr3 MO-2-1001-18A,B Gate Valve, Motor Operated X MO-2-1001-36A,B Globe Valve, Motor Operated X MO-2-1001-37A,B Globe Valve, Mator Operated X MO-2-1001-28A,B Globe Valve, Motor Operated X
-I MO-2-1001-34A,B Gate Valve, Motor Operated X MO-2-1001-29A,B Gate Valve, Motor Operated X MO-2-1001-26A,B Gate Valve, Motor Operated X MO-2-1001-23A,B Gate Valve, Motor Operated X FT-2-1051A,B Plow Transmitter X MO-2-1001-63 Gate Valve, Motor Operated X MO-2-1001-60 Gate Valve, Motor Operated X FT-2-1049A,B Flow Transmitter X DPIS-2-1001-81A,B Differential Pressure X Indicating Switch I
I
Revision 4 November 1, 1980 I SYSTEM: Page 2 Residual lleat Removal / Containment Spray (Continued) SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary I Plant Identification Number Generic Name Contain- Contain-ment ment MO-2-1001-50 Gate Valve, Motor Operated X MO-2-1001-47 Gate Valve, Motor Operated X MO-2-1001-19A,B Gate Valve, Motor Operated X MO-2-1001-16A,B Globe Valve, Motor Operated X MO-2-1001-5A,B Globe Valve, Motor Operated X FT-2-1042A,B Flow Transmitter X PT-2-1044A,B Pressure Transmitter X LS-2-4941-2A,B,C Level Switch (High) X 2-1001-65A,B,C,D RIIR Service Water Pumps and X Motors MO-2-1001-20,21 Gate Valve, Motor Operated X 2-1002A,B,C,D RHR Pump X MO-2-1001-4A,B Motor Operated Valve X MO-2-1001-185A,B Motor Operated Valve X DPS-2-1001-78A,B Differential Pressure Switch X 2-5745A,B,C,D RHR Service Water Pum) X Cubical Coolers I .I I I I
Facility: Quad Cities Revision 4 Unit: 2 November 1, 1980 Docket: 50-265 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Pressure Suppression Piping SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Plant Identification Number Generic Name Primary Contain-ment Primary Contain-ment S0-2-1601-69 Solenoid Valve X SO-2-1601-68 Solenoid Valve X I S0-2-8801A,B,C,D, Air Operated Valve, Solenoid X S0-2-8802A,B,C,0 %ir Operated Valve, X Solenoid PS-2-1001-83A,B,C,D Pressure Switch X PS-2-1001-88A,B,C,D Pressure Switch X I PS-2-1001-89A,B,C,D Pressure Switch X PS-2-1001-90A,B,C,D Pressure Switch X S0-2-1601-52A,B Solenoid Valve X SO-2-1601-70 Solenoid Valve X SO-2-1601-71 Solenoid Valve X PT-2-1424 Pressure--Tranemi4-ter- 'd I I S0-2-1601-51A,B Solenoid Valve X SO-2-8803 Air Operated Valve, X Solenoid I S0-2-8804 Air Operated Valve, Solenoid X SO-2-1601-65 Solenoid Valve X SO-2-1601-67 Solenoid Valve X
Revision 4 November 1, 1980 SYSTEM: Pressure Suppression Piping (Continued) Page 2 SPECIPIC COMPONENTS ASSOCIATED WITH ABOVE SYSTFM Location I Plant Identification Inside Primary Outside Primary Contain- Contain-Number Generic Name ment ment S0-2-1601-66 Solenoid Valve X MO-2-1601-57 Globe Valve, Motor Operated X S0-2-1601-50A,B Solenoid Valve X PS-2-1622A,B Pressure Switch X hT 2 1426 Level Transai-t-ter X(2) AO-2-1601-55 Gate Valve, Air Operated X (Solenoid) I ) PCC-2-1604=55 Cate Valve, Ai-r-Ope ra ted X fPosi-t ion Sw i tch )- POS 2-1641 61 Ai-r-operated valve , X(3) fPosi-t-ic- Sw i tch ) I POG-2-1-604-60 " i-r Ope rated Va1yc , fPos-i-t-ien Switcle X(3J X I} DOS --- 2 SBGlA,B,C,0 Air Operated-Velve, tPosi-t-ica Switch) PCC S BG2 A ,3, C r0 Air--Operated Valve, X II fPosi-t-ion-6w-i-teld POF 1-641 - 2 3, 2 4 "1r Operated valve
(3) w is n. _ :. : _....m:. _ . . ,
c. I POG-2-160 6 2 Air Operated Valvc X(3)
'Pc3itic W tele POG-2-1404-6 3 Air Operat-ed Va1vc X(3) f pon i t inn -r,w i*oh )
POG-2-1401-21 r32 Ai-r--Operated Va1vc X I3I
+ Peel-t-icn Suiteld POG-2-4 601--5 6 Ai-rPrated Va1vc X(3) fPosi-t-ion Sei tcle Air-Operated Valve X pog_g_1401-59
+Posi t-icn Su i teld
Revision 4 l November 1, 1980 SYSTEM: Pressure Suppression Piping (Continued) Page 3 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain- Contain-Number Generic Name ment ment P06-2-1-601 58 X I I Ai-r+ rete! Va1vc FPosit-4on41-teh)- POS - 1601-2GA ,3 " i-r--Ope ra t ed Va l v e
. X II fPee4-t4on Swit04)-
TE-2-1630A,B Tempersture Element X TE-2-1631A,B Temperature Element X (1) This component has been deleted because its function is required during normal operation only. (2) This component has been deleted because it provides indication only. (3) This component has been deleted because it is used for position indication only and failure of the switch will I not affect the associated valve control circuit. I I I l I
Facility: Ouad CAties Revision 3 Unit: 2 June 2, 1980 Docket: 50-265 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Service Water SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary
- 5. Plant Identification Contain- Contain-Number Generic Name ment ment 2-5746B South RHR Hx Room X Emergency Cooler 2-5746A North RHR Hx Room X Emergency Cooler I 2-5748B South Core Spray Equipment Room Emer-gency Cooler X
2-5748A North Core Spray X Equipment Room Emer-gency Cooler I 2-5747 HPCI Room Emergency Cooler X , 2-3903 Diesel Generator X Cooling Water Pumps 2-5749 Diesel Generator X Cooling Pump Cubicle Coolers .I I I I I I
Revision 3 Facility: Quad Cities June 2, 1980 l Unit: 2 i Docket: 50-265 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT l REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS IE SYSTEM: Diesel Oil Piping SPECIFIC COMPOWENTS ASSOCIATED WITH ABOVE SYSTEM
~
~
Location Inside Outside Primary Primary Plant Identification Contain- Contain-Generic Name ment ment Number il 2-5203 Diesel Oil Transfer Pump , X X S0-2-5201 Solenoid Valve X
- LS II/ L-2-52 41-3 Level Switch
,I 'l il ,I 4 lI If I 1 3 i
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JW Facility: Quad Cities Revision 4 Unit: 2 November 1, 1980 1 Docket: 50-265 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT I REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS . I SYSTEM: Containment Isolation SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Oa tsid e li , Plant Ide nt if ica t ion Number Generic Name (**) Primary Contain-ment Primary Contain-ment
*AO-2-203-1A,B,C,D Globe Valve, Air Operated X (M-60)
- AO-2-2 0 3-2 A , B ,C , D Globe Valve, Air Operated X (M-60)
*MO-2-220-1 Gate Valve, Motor Operated X
- =
l (M-60) I *MO-2-220-2 Gate Valve, Motor Operated (M-X I *AO-2-220-44 Gl v .,- Valve, Air Operated X (M-77)
*AO-2-220-45 Globe Valve, Air Operated X (M-77)
*SO-2-305-120 Solenoid Valve X
*SO-2-305-121 Solenoid Valve X
*SO-2-305-122 Solenoid Valve X
=
*SO-2-305-123 Solenoid Valve .X
- ju *MO-2-1001-47 Gate Valve, Motor Operated (M-79)
X
*MO-2-1001-50 Gate Valve, Motot Operated X 8 (M-79)
*MO-2-1001-37A,B Globe Valve, Motor Operated X
- MO 10 01- 2 6 A , B , Gate Valve, Motor Operated X (M-79) i I
I Revision 3 June 2, 1980 I SYSTEM: Containment Isolation (Continued) Page 2 SPECIPIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM Location Inside Outside i Primary Primary Plant Identification Contain- Contain-Generic flame (**) tiumber ment ment
*MO-2-1001-23A,D Gate Valve, Motor Operated X *MO-2-1001-63 Gate Valve, Motor Operated X (M-79)
Gate Valve, Motor Operated X
*MO-2-1001-60
- MO 10 01-3 6 A , B Globe Valve, Motor Operated X (M-79)
*MO-2-1001-34A,B Gate Valve, Motor Operated X (M-79) *MO-2-1001-29A,B Gate Valve, Motor Operated X (M-79) *MO-2-1001-28A,B Globe Valve, Motor Operated X (M-79) *MO-2-1001-7A,B,C,D Gate Valve, Motor Operated X (M-79) *MO-2-1001-20 Gate Valve, Motor Operated X (M-79) *MO-2-1001-21 Gate Valve, Motor Operated X 8 (M-79)
MO-2-1201-2 Gate Valve, Motor Operated X MO-2-1201-5 Gate Valve, Motor Operated X
*MO-2-1301-16 Gate Valve, Motor Operated X (M-89) *MO-2-1301-17 Gate Valve, Motor Operated X i (M-89) *AO-2-1301-12,13 Globe Valve, Air Operated X )
I (M-89)
*AO-2-1301-34,35 Globe Valve, Air Operated X I (M-89)
I I '
Revision 3 June 2, 1980 SYSTEM: Containment Isolation (Continued) Page 3 SPECIFIC COMPOt3ENTS ASSOCI ATED WITil ABOVE SYSTEM Location h- Inside Outside = Primary Primary Plant Identification Contain- Contain-tJumber Generic flame (**) ment ment
*MO-2-1301-25 Gate Valve, Motor Operated X (M-89) *MO-2-1402-24A,B Gate Valve, Motor Operated X (M-78) *MO-2-1402-25A,B Gate Valve, Motor Opecated X (M-78) *MO-2-1402-4A,B Globe Valve, Motor Operated X (M-78) *MO-2-1402-3A,B Gate Valve, Motor Operated X (M-78)
I AO-2-2001-3,4 Gate Valve, Air Operated (Solenoid) X i AO-2-2001-15,16
*MO-2-2301-4 Gate Valve, Air Operated (Solenoid)
Gate Valve, Motor Operated X X (M-87)
*MO-2-2301-5 Gate Valve, Motor Operated X (M-87) *AO-2-2301-29,30 Globe Valve, Air Operated X 64,65 (M-87) *MO-2-2301-36 Gate Valve, Motor Operated X (M-87) 2-700-736B,C,D,E,P Squib Shear Valve X 2-700-733B,C,D,E,P Solenoid Ball Valve X MO-2-3702 Gate Valve, Motor Operated X (M-75)
I MO-2-3703 Gate Valve, Motor Operated (M-75) X MO-2-3706 Gate Valve, Motor Operated X (M-75) i I
Revision 4 flovember 1, 1980 I SYSTEM: Containment Isolation (Continued) Page 4 SPECIFIC COMPOrlEtJTS ASSOCIATED WITil ABOVE SYSTEM Location I Inside Primary Outside Primary Plant Identification Contain- Contain-I ?! umber Generic tJame (**) ment ment PO6-2-2001-Ir4 A tr-Opera t+d-vaIne-{-PosLt4on yII) Sw i-teld-POG-2-2001-14 r1-5 A i-r--Ope re ted-Va l-v e-f-Pos 1-t-io n X(1) Gwi-tahF
*AO-1-1601-21,22 Butterfly Valve, Air X Operated
*AO-1-1601-23 Butterfly Valve, Air X Operated
.g Gate Valve, Air Operated X a *AO-1-1601-61
*AO-1-1601-56,60,24 Butterfly Valve, Air X I Operated Air Operated Valve (Solenoid) X S0-1-4720 80-1-4721 Air Operated Valve (Solenoid) X A t-e-Operat+d-Vahc ( Poa 1-t4en X I1I I POG-1-+7 20 Gwi-t-ohf A i-r-Ope r-a ted-Va kve-tPosi-tdon X(1)
POS-1 -4 7 21----- Swi-tobf 8 I
- These components are listed here for information only.
Their qualification evaluation is covered with their respective systems.
** Shows P&ID number of respective system (1) This coitiponent has been deleted because it is used for I position indication only and failure of the switch will not affect the associated valve control circuit.
I I I
Facility: Ouad Cities Revision 3 Unit: 2 June 2, 1980 Docket: 50-265
.I MASTER LIST CLASS lE t:LECTRICAL EQUIPMENT REQUIRED TO FUtlCTIOri UhDER POSTULATED ACCIDENT CONDITIONS I
SYSTEM: Control Rod Drive SPECIFIC COMPONENTS ASSOCI ATED WITil ABOVE SYSTEM Location Inside Outside Primary Primary 8 Plant Identification Contain- Contain-Number Generic Name ment ment
*SO-2-305-117 Solenoid Valve X
*SO-2-305-118 Solenoid Valve X S0-2-302-20A,B Solenoid Valve X S0-2-302-19A,B Solenoid Valve X LS-2-302-82A,B,C,D, Level Switch X POS-2-302-21A,E Air Operated Valve X (Position Switch)
I POS-2-302-22 Air Operated Valve (Position Switch) X
*SO-2-305-120 Solenoid Valve X
*SO-2-305-121 Solenoid Valve X
*SO-2-305-122 Solenoid Valve X
*SO-2-305-123 Solenoid Valve X
- Typical of 177 valves I
I I I
I Facility: Quad Cities Revision 4 Unit: 2 November 1, 1980 Docket: 50-265 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT I REOUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor (Nuclear Boiler) Recirculation I SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location
- ] Inside Outside B Primary Primary Plant Identification Contain- Contain-Humber Generic Name ment ment LITS-2-263-73A,B Level Indicating X Transmitter Switch
,I PS-2-263-lllA,B,C,D Pressure Switch X PP-2-647A 71+ Pressurt Tranaaittcr III X I@-2-646-A,P, Level Transmitter II) X PT-2-662 Pressure-Transei-t tc r X III PS-2-263-52A,B Pressure Switch X PS-2-263-55A,B,C,D Pressure Switch X I@ 264-6-1 Lcvc1 Teansmi-ttcr X(2) PO6-2-220-5-1 Cleb Valvc, Air X -(3) Operated-tPosi-t-ion 6*i-teld AO-2-220-5-1 Clobc valve, Air X (3) I POS-a-420-52 Operated (Caleno+d Valve) Clobe va1ye, Ai+- (3) X Operated (Pc3ition Swi+eth AO-2-2-2 0 - 5 2 Clobe Val-ve , Air M (3) I Operate <%1en<>td
,,,,..a l
i I ~ i
- I !
lI I
Revision 4 tiovember 1, 1980 Page 2 SYSTEM: Reactor (Nuclear Boiler) Recirculation (Continued) I SPECIFIC COMPOtlENTS ASSOCIATED WITil ABOVE SYSTEM Location Inside Outside Primary Primary I Plant Identification flumber Generic Name Contain-ment Contain-ment I LITS-2-263-59A,B Level Indicator Transmitter Switch X LIS-2-263-57A,B Level Indicator Switch X LIS-2-263-72A,B,C,D Level Indicator Switch X LIS-2-263-58A,B Level Indicator Switch X C1obe-Ve4-vc, Air X I4) POS-7--32F 4 4 I Operated-tPc3i tion Gwi-teh4 I AO-2-220-44 Globe Valve, Air Operated (Solenoid Valve) X POG-2-aaG-45 Globe Valve, Air X I4I Operated (I'O3 i t ica Gwi-teh-)- AO-2-220-45 Globe Valve, Air X Operated (Solenoid Valve) MO-2-202-4A,P, "atee-Operatel-Vcive v. (5) MO-2-202-5A,B Motor Operated Valve X MO-2-202-6A,B Motor Operated Valve X MO-2-202-9A,B Motor Operated Valve X PS-2-261-23A,B Pressure Switch X DPIS-2-261-34A,B,C,0 Differential Pressure X Indication Switch DPIS-2-261-35A,B,C,D, Differential Pressure X E ,F ,G 211 Indication Switch I I I :
l l Revision 4 11ovember 1, 1980 Page 3
.I SYSTEM: Reactor (tJuclear Boiler) Recirculation (Continued)
(1) This component has been deleted because it is required for control of the feedwater regulation valve during normal operation only. I 1 l (2) This component has been deleted because it provides indication only. (3) This piping system does not penetrate the drywell, therefore these valves are not required for containment isolation. (4) This component has been deleted because it is used for
. position indication only and failure of the switch will not affect the associated valve control circuit.
(S) These valves have been deleted because they are wired
- out to remain inoperable, and their function is not required following an accident.
!I !I I .I I
I I I g l
! l !I Facility: Quad Cities Ravision 3 l Unit: 2 June 2, 1980 Docket: 50-265 l l l MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUtiCTION UllDER POSTULATED ACCIDENT CONDITIONS
,I i
l SYSTEM: Process Radiation Monitoring SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM i Location Inside Outside Primary Primary j Plant Identification Contain- Contain-jg Number Generic Name ment ment
- g
- RE-2-1735A,B Rx Building Ventilation X
) Exhaust Radiation Element i !I i , lI I lI i l lI I
- 8
!,I
I Facility: Quad Cities Revision 3 2 June 2, 1980 l3 Unit: j Docket: 50-265 MASTER LIST ( CLASS 1E ELECTRICAL EQUIPMENT REQUIRED TO FUf1CTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Building Ventilation ; SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM ! Location I Plant Identification Inside Primary Contain- Contain-outside Primary l l Number Generic Name ment ment AO-2-5742A,B Butterfly Valve, Air X , Operated (Solenoid) i l 8 AO-2-5741A,B Butterfly Valve, Air X Operated (Solenoid) I I I I I I I I I I
- --___-____ _ _- --w _ w. .- m-
Facility: Quad Cicies Revision 4 Unit: 2 November 1, 1980 Docket: 50-265 MASTER LIST
- CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I Standby Alternating Current Power SYSTEM:
SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location
- g Inside Primary Outside Primary ig Plant Identification Contain- Contain-Number Generic Name ment ment 2-6601 Standby Diesel Generator X SWGR 23-1 4.16 kV Switchgear X SWGR 24-1 4.16 kV Switchgear X SWGR 28 480 V Switchgear X SWGR 29 480 V Switchgear X MCC 28-1A,B 480 V Rx Building MCC X 1
MCC 28-2 480 V Turbine Building MCC X j MCC 28-3 480 V Turbine Building MCC X MCC 28/29-5 480 V Rx Building MCC X MCC 29-1 480 V Rx Building MCC X !I MCC 29-2 480 V Turbine Building MCC X MCC 29-3 480 V Rx Building MCC X MCC 29-4 480 V Rx Building MCC X ! MCC 29-6 480 V Rx Building MCC X !I 8 il
- I
I Revision 3 i June 2, 1980 SYSTEM: Standby Alternating Current Power (Continued) Page 2 SPECIFIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM '.l5 Location Inside Outside Primary Primary I Plant Identification Number Generic Name Contain- Contain-ment ment I RPS Bus lA 120 V ac Reactor Protection X System Bus lA RPS Bus 1B 120 V ac Reactor Protection X System Bus 1B Essential Service Bus 120/240 V ac Essential Service X Bus Instrument Bus 120/240 V ac Instrument Bus X Cssential Bus MMG Set 120/240 V ac Essential Bus X Supply MMG Set
- g 225.'--12 Excitation Cabinet for X l3 D/G 2 g None Engine Control Panel for X g D/G 2 2252-37 Diesel Auxiliary Control X Panel for D/G 2 None Secondary Control Panel for X D/G 2 None Neutral Grounding Panel for X D/G 2 I None 4 kV Nonsegregated Bus X 3
I I I I I
l lI Facility: Quad Cities Revision 3 2 June 2, 1980 Unit: Docket: 50-265 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Standby Direct Current Power SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location I Inside Primary Contain-Outside Primary Contain-Plant Identification Number Generic Name ment ment 250 V Batt Chgr 2 250 V Battery Charger X MCC 2 (Turb Bldg) 250 V dc Turbine Building X MCC MCC 2A and 2B 250 V dc Reactor Building X MCC 250 V Battery 250 V de Battery X 125 V Batt Chgr 2 125 V Battery Charger X 125 V Batt chgr 2A 125 V Battery Charger X 125 V Battery 125 V de Battery X 125 V DCDP 2A 125 V dc Turbine Building X and 2B Distribution Panel 125 V DCDP 2 125 V dc Reactor Building X Distribution Panel X 48/24 V Batt 48/24 V Battery 2A and 2B 24 V Batt Chgr 24 V Battery Charger X 2A and 2B (+) I 24 V Batt Chgr 2A and 2B (-) 24 V Battery Charger X 48/24 V DCDB 48/24 V dc Distribution X Panel 8 2A and 2B I I
l 8 Facility: Quad Cities Revision 4 November 1, 1980 I Unit: 2 Docket: 50-265 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Core Isolation Cooling SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location I Plant Identification Inside Primary Outside Primary Contain- Contain-Number Generic Name ment ment MO-2-1301-17 Gate Valve, Motor Operated X MO-2-1301-16 Gate Valve, Motor Operated X TS-2-1360-14A,B,C,D Temperature Switch X I 15A,B,C,D 16A,b,C,D 17A,B,C,D DPIS-2-1360-1A,B Differential Pressure X Indicating Switch PS-2-1360-9A,B,C,D Pressure Switch Low X AO-2-1301-34,35 Globe Valve, Air Operated X (Solenoid) III FOG-2-1M1-34 735 01 obc Va1+c , Air Opcrated X fPos Lt-ion-Swit-ete An-2-1301-12,13 Globe Valve, Air Operated X (Solenoid) P06-2-1-301 -- 12 ,13 III Globe Valve, Air Operatel X l fPosi-t-ion Switeld MO-2-1301-S3 Motor Operated Valve X 1 MO-2-1301-60 Motor Operated Valve X l (1) These components have been deleted because they are used for position indication only and failure of the switches will not affeet the associated valve control circuit. I l I l
i lI l !I it !I i
- I i
i i l !I l lI i APPENDIX C
\
QUAD CITIES UNITS 1 AND 2 KEY 'l PLAN IDENTIFYING HARSil ENVIRONMENTAL i i i l AREAS AND TABULATION OF SERVICE CONDITIONS l !I 'I lI J !I !I I lI il ! !I 1 I !I . i
l 5 Revision 4 November 1, 1980 I LIST OF FIGURES AND TABLES I Figure C.1 Plan view general arrangement drawing I identifying harsh environmental areas for Quad Cities Units 1 and 2, el 554'-0" I Figure C.2 Plan view general arrangement drawing identifying harsh environmental areas for Quad Cities Units 1 and 2, el 595'-0" Figure C.3 Plan view general arrangement drawing identifying harsh environmental areas for Quad Cities Units 1 and 2, el 623'-0" I Figure C.4 Plan view general arrangement drawing identifying harsh environmental areas for Quad Cities Units 1 and 2, el 647'-0" Figure C.5 Plan view general arrangement drawing identifying harsh environmental areas for I Quad Cities Units 1 and 2, el 666'-0" and 690'-6" I Figure C.6 PSAR Figure 5.2.15 providing the drywell pressure response following the postulated LOCA Figure C.7 FSAR Figure 5.2.16 providing drywell temp-erature response following the postulated LOCA Table C-1 Maximum environmental conditions inside the drywell for the postulated LOCA/HELB Table C-2 Maximum environmental conditions outside the drywell following the postulated HELB acci-dents Table C-3 Post-LOCA maximum radiation doses for areas outside the drywell for 1 day, 30 days, and 1-year exposure. (Where times other than 1 day, 30 days, and 1 year apply, calculated values for the appropriate time are utilized.) I I I
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' i LEGEND l ! WRNA R ADI ATION, PR ELSUR E. '
! I, TEMPERATURE & HUMIDITY '
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M M M M M M M M e m m m m e a m Revision 3 June 2, 1980 TABLE C-1 MAXIMUM E!!VIROt!ME? ITAL CO!!DITIO!1S I!! SIDE THE DRYWELL FOLLOWIt1G Tile POSTULATED LOCA/HELB Relative Containment Gamma Submergence Pressure Humidity Spray Radiation Elevation Temperature 7 63 psia 100% Demineralized 1 day-4.3x10 rads 583'-0" 281F l rads I water 30 day-1.0x10 ' 1 year-1.1x10 rads l l i l l l I i i
m M M M M M M m m m m e m m W W W W W Revision 4 November 1, 1980 TABLE C-2 MAXIMUM ENVIRONMENTAL CONDITIONS OUTSIDE THE DRTdELL FOLLOWING THE POSTULATED HELB ACCIDENTS
'ximum Maximum Relative Pressurc Temperature Humidity Area Pipe Break (psia) ('F) (%)
Torus compartment HPCI steam 27.0 242 100 (region of postulated RCIC Steam line break) Core spray /RCIC room RCIC steam Not evaluated - Equipment in this room not required for RCIC steam line break Steam tunnel Main steam 27.0 242 100 Feedwater RCIC steam RWCU heat exchanger and RWCU Not evaluated - Only two containment isolation holding pump room valves required to function. Qualification will meet conservatively assumed inside drywell conditions. High-pressure heater Main steam Not evaluated - No equipment which is required bay - Feedwater to function is located in this area. Turbine building Main steam Not evaluated - No equipment which is required el 615'-6" to function is located in this area. north of Column G, between Columns 9 and 11 and 35 and 16
Revision 4 November 1, 1980 TABLE C-2 (Continued) Maximum Maximum Relative Pressure Temperature Humidity Area Pipe Break (psia) (*F) (%) r l Reactor feed pump Feedwater Not evaluated - No equipment which is required l room to function is located in this room. Turbine building Feedwater Not evaluated - No equipment which is required el 595'-0" to function is located in this area, area south of Unit 1 pump room and north of Unit 2 pump room Diesel generator room Feedwater Not evaluated - Qualification for the environ-ment due to a postulated feedwater line break ' is not required since three diesels are available to provide emergency ac power.
W W W W W W W W m m m M M M M M M M Revision 3 June 2, 1980 TABLE C-3 RADI ATIOrl ElIVIRO?1MEf3TAL cot 3DITIO?IS OUTSIDE DRYWELL FOLLOWIt1G THE POSTULATED LOCA MAXIMUM RADIATIOfi SOURCES Integrated Dose Levels (rads) Source
- 1 Day 30 Days 1 Year Area ,
SP 1.5x10 3.2x10 3.9x10 Torus 5 6 SP 2.4x10 9.4x10 1.7x10 Residual heat removal corner rooms 6 1.7x10 HPCI room MS 6.6x10 1.6x10 6 Core spray /RCIC rooms MS 6.6x10 1.6x10 1.7x10 5 6 Steam tunnel MS 3.1x10 5 8.5x10 1.6x10 6 6 Reactor building el 595'-0" RW 2.5x10 7.8x10 1.4 10 6 6 Reactor building el 623'-0" CA 6.8x10 1.6x10 1.6x10 5 6 0 Reactor building el 647'-6" CA 6.8x10 1.6x10 1.6x10 6 6 Reactor building el 666'-6" CA 6.8x10 1.6x10 1.6x10
- SP = Supression pool liquid RW = Reactor water MS = Reactor steam CA = Containment airborne
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