ML19351D813

Vol 1 of Revision 1 to Response to IE Bulletin 79-01B for Dresden Nuclear Power Station,Unit 3

ML19351D813
Person / Time
Site:	Dresden
Issue date:	11/01/1980
From:	BECHTEL GROUP, INC.
To:
Shared Package
ML19351D808	List: ML19351D807 ML19351D813 ML19351D817 ML19351D823 ML19351D825 ML19351D829 ML19351D833 ML19351D838 ML19351D844
References
IEB-79-01B, IEB-79-1B, NUDOCS 8011200066
Download: ML19351D813 (66)

Text

{{#Wiki_filter:. _ _ _ _ _ Io I I I I I RESPONSE TO IE BULLETIN 79-OlB FOR DRESDEN NUCLEAR POWER STATION UNI" 3 COMMONWEALTH EDISON COMPANY DOCKET NUMBER 50-249 I B PREPARED BY: BECHTEL POWER CORPORATION Preliminary Report Date: April 21, 1980 l Revision 0: June 9, 1980 Revision 1: November 1, 1980 L r 8 0//).6 D O lo G

E nevision t p November 1, 1980 I TABLE OF CONTENTS I VOLUME 1 Page 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) 4.4 Evaluation of Environmental Qualification 9 Data (Bulletin Action Items 2 and 4) 4.5 Class lE Equipment Qualification Plan 10 I 4.6 Submittal of Licensee Event Reports 11 (Bulletin Iction Item 6)

5.0 REFERENCES

12 I APPENDIXES A Dresden Unit 3 and Common Systems List B Dresden Unit 3 and Common Specific and General I Use Components List Sorted by System C Dresden Unit 3 Key Plan Identifying Harsh i Environmental Areas and Tabulation of Service Conditions VOLUMES 2 AND 3 D Dresden Unit 3 and Common Component Evaluation I Worksheets Sorted by System I . I l

Revision 1 November 1, 1980 I 1.0 STUDY OBJECTIVES This study has been prepared in response to NRC IE Bulletin 79-OlB, dated January 14, 1980. It has been prepared by Bechtel Power Corporation, Ann Arbor, Michigan, for Common-wealth Edison Company's Dresden Nuclear Power Station Unit 3. The scope of the study includes: a. Preparing a master list of all engineered safety feature (ESF) systems I b. Identifying all components required to function under postulated accident conditions I c. Defining environmental service conditions for the components identified above d. Establishing maximum flood elevation inside containment I e. Evaluating qualification data for components and documenting bases of equipment qualification f. Recommending action to be taken where qualifica-tion data for components does not exist or is inadequate for station service conditions g. Where qualification data does not exist, preparing a justification for continued station operation, I or identifying those items for which a licensee event report (LER) should be prepared by Common-wealth Edison Company. h. Preparing a report documenting the results of the study in accordance with Item 7 of NRC IE Bulletin 79-OlB i. reparing contract documents to specify testing and analysis where required to resolve outstanding items. j. Preparing procurement documents for replacement I equipment where existing equipment is identified for replacement. k. Performing engineering for equipment relocation I and modification where necessary to resolve open items. I I 1

Revision 1 I November 1, 1980 t 2.0 STUDY RESULTS The systems required to function following the postulated I accidents have been identified and the essential components listed. Environmental service conditions have been established, Evaluation of environmental qualification test reports have I been completed. Data sheets (Appendix D) are provided for essential components subject to harsh environmental service conditions. These data sheets document the qualification of I each component by reference to the qualification test condi-tions, or document action in progress to resolve the status of the component. Table 2-1 provides a tabulation of systems included in the study, percent of system components with I outstanding items, and percent of outstanding qua.'.ification data items. Data sheets for components with outstanding items also contain specific actions to be taken to resolve outstanding I items and justifications for continued station operation while the action items are implemented. I I I I I I I I I I I la i

Revision 1 l November 1, 1980 t '.0 STUDY CONCLUSIONS AND RECOMMENDATIONS Investigations in response to NRC IE Bulletin 79-01B indicates that a significant number of components are either not subjected to harsh environmental cervice conditions or have I qualification data documented. Vendors have been contacted and confirming letters have been written te the equipment manufacturers requesting qualification F if available, or component materials data for analysis. Table 3-1 provides I a list of letters written. Resolution of qualification status for the remaining components is being pursued in one or any combination of the following methods. a. Equipment will be subjected to worst case environ-mental service conditions and performance / function tested following exposure. A test report will be I prepared for each test. l* lg b. Where long-term temperature conditions are based ig on criteria established prior to station operation and referenced in the FSAR, actual worst case plant conditions (including measurements of area i temperatures, whcre required) will be utilized to reanalyze station environments and establish j actual environmental service conditions. Where lE conservatism in design results in lower actual l5 temperatures, qualification will be based on actual conditions. Qualification will not be l required where actual conditions reduce low tem-pera' cure harsh environments to nonharsh environments. Equipment will be replaced with qualified equipment. c. d. Equir nent will be relocated and/or shielded, c. Where qualifi:ation data may exist but materials l data is requiled to determine existence of suitable test reports, additional vendor contacts will be made. Ih

w Contract packages for qualification testing have been prepared and are scheduled to be issued for bids before January 1, 1981.

l3 Procurement documents for replacement components are being i lE prepared and are scheduled to be issued for bids during the j first quarter of 1981. Vendor contacts have been made and work is in progress where additional qualification data may 'I be obtainable from the vendor. I II 2 I

Revision 1 I November 1, 1980 Replacement components will be installed during the first refueling outage after the new components are received onsite. When the outstanding items identified in Appendix D are closed I 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 Appendix D. 4.0 DETAILED EVALUATION 4.1 DEFINITION OF POSTULATED ACCIDENTS NRC IE Bulletin 79-OlB defines the postulated accident conditions to be addressed as the loss-of-coolant-accident / high energy line break (LOCA/HELB) inside the containment and the HELB outside the containment. For the Dresden Nuclear Power Station Unit 3, the LOCA/HELB I 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. 37, Revision 1, submitted to the NRC in February 1975. In evaluating the effects of HELB, concur-rent multiple breaks are not evaluated. For the LOCA/HELB inside the containment, worst case environ-I mental conditions are established by the LOCA resulting from a double-ended recirculation line break. The environ-mental conditions which result from this accident are provided in Section 4.3 and Appendix C. For a HELB outs!de the con &.inment, Special Report No. 37 identifies the high energy lines and the location of postu-I lated breaks. In support of the response to IE Bulletin 79-OlB, studies were. performed to establish equipment integrated radiation doses as a result of the postulated accidents. These environmental conditions are discussed in Section 4.3. The following postulated accidents involving HELBs were analyzed to establish the worst environmental conditions: a. LOCA inside drywell b. Main steam line break in the steam tunnel I I I g 3

Revision 1 November 1, 1980 c. Main feedwater line break d. High-pressure coolant injection (HPCI) steam line break e. Isolation condenser steam line break f. Reactor water cleanup (RWCU) line break i Where components, because of their location, could be sub-jected to differing environments for the various accidents, the most severe environmental conditions were utilized for qualification. Components located within compartments with ,g postulated HELBs would be subjected to pressure, temperature, !5 and humidity conditions resulting from that HELB, but wguld not be subjected to radiation doses in excess of 5 x 10 rads simultaneously. These se.ne componegts could be subjected to I radiation doses in excess of 5 x 10 rads following a LOCA, but these doses would not be simultaneous with pressure, temperature, and humidtty. To simplify this analysis, qualification data I initially sought which demonstrated operability of these was components for the combination of all environmental conditions. Where qualification could not be demonstrated for the entire g spectrum of conditions simultaneously, components were g evaluated for the conditions associated with each individual accident. Environmental conditions are based on the specific accidents for which the components must function. Components which are exposed to harsh environments during accidents for which they are not required to function do not require qualification for these environments. Where qualification I testing is to be performed, testing will be performed for each postulated environment separately. 4.2 IDENTIFICATION OF CLASS lE COMPONENTS REQUIRED TO I FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS (BULLETIN ACTION ITEM 1) i The Dresden Nuclear Power Station FSAR and emergency proce-dures were reviewed to identify the engineered safety feature systems which are required to mitigate the consequences of I the postulated accidents discussed in Section 4.1. These systems ara those needed to achieve reactor shutdown, contain-ment isolation, reactor core cooling, containment and reactor heat removal, and to prevent the release of radioactive I material to the environment in excess of the guidelines of 10 CFR 100. I J ,I 4 5

Revicion 1 Novcmber 1, 1980 Appendix A provides the master list of Unit 3 and common systems required to function following all of the postulated .g acc:. dents discussed in Section 4.1. Table A-1 identifies g which systems are required to function following each of the postulated accidents. The station piping and instrument diagrams and electrical schematics were reviewed to determire the specific compo-nents which must function following the postulated accidents. I Based on this review, a master components list has been developed for each system identified in Appendix A. The master components list identifies each Class lE and/or essential electrical component that is required to function following the postulated eccidents discussed in Section 4.1. Appendix B provides the master components list for Unit 3 and common systems. Throughout this report Class lE is used .g in reference to components designed to Class lE as well as 5 components not designed to Class lE, but which are essential following the postulated accidents. 4.3 DEFINITION OF ENVIRONMENTAi, SERVICE CONDITIONS (BULLETIN ACTION ITEMS 3 AND 5) 4.3.1 Inside the Drywell The drywell pressure and temperature response following the I postulated LOCA are provided in FSAR Figures 5.2.11 and 5.2.12, respectively. These figures are included in Appendix C. The maximum humidity inside the drywell is defined in FSAR Table 5.2.2 as 100%. Chemical sprays are not used in the I Dresden design. Demineralized water containment spray is utilized and considered in the evaluation. The Dresden FSAR does not provide integrated radiation doses inside the I drywell. Studies were performed to establish the integrated doses inside th^ drywell for a postulated LOCA. The integrated doses for 1 day, 30 days, and 1 year are provided in Appen-I The study methodology is described in Section 4.3.5. dix C. Radiation doses are evaluated for actual equipment operating times. Appendix C also defines the containment spray fluid. I and provides the maximum drywell pressure, temperature, humidity, and flood elevation. 4.3.2 Outside the Drywell, Subject to HELB HELB is discussed in detail in Special Report No. 37, Revision 1, submitted to the NRC in February 1975. The

g environmenual conditions (pressure, temperature, and humidity),

g due to a pipe break in the steam tunnel, torus compartment, RWCU heat exchanger room and turbine building are listed in Appendix C. Radiation doses following a HELB are less 1 severe than the doses associated with a LOCA and are there-fore not provided. Flooding does not occur outside the I I 5

I Rovision O June 9, 1980 I drywell as a result of the postulated HELBs. Chemical and demineralized water spray do not exist outside the drywell. For this study, the environmental effects of a pipe break I are considered only in the compartment in which the break occurs as well as areas open to the break area. 4.3.3 Outside the Drywell, Post-LOCA Radiation Exposures Integrated doses have been calculated for areas outside the I drywell. Doses were established for 1 day, 30 days, agd 1 year exposure. Integrated doses of less than 5 x 10 rads during a component'e service life are evaluated as nogharsh environmental c; lons. Integrated doses of 5 x 10 rads I mnd greater are evaluated as harsh environmental conditions. Appendix C provides integrated doses as a function of expo-sure time for areas containing components identified in I Appendix B. The radiation study methodology is described in Section 4.3.5. 4.3.4 Nonharsh Areas Plant areas which are not covered in the above referenced Appendix C tables are considered nonharsh environmental I areas with respect to HELB and post-LOCA radiation. These areas are either maintained in a suitable environmental condition by safety-related heating, ventilating, and air conditioning (HVAC) equipmtut, or are considered nonharsh because they are controlled to less than 104F prior to the postulated accidents and are relatively large open areas with no large motors or other equivalent heat sources. Where environmental conditions are maintained by HVAC equip-ment, the HVAC system is provided with redundant components I and/or a backup power supply for reliable operation. Safety-related HVAC systems are provided for the following areas: I a. Control room, cable spreading room, battery rooms, j computer room, and electrical equipment room b. Standby diesal generator room c. HPCI room d. Low-pressure coolant injection 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 inventor

• was based on General Electric I

I I e

g Revision 1 g Novemb r 1, 1980 document " Radiation Source Information for NUREG 0578 Implementation, Computer Run Identified as SNUMB 7007S" dated November 1979. 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 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 material (e.g., valve motor actuators in metal enclosures). I The gamma dose was established based on immersion of the component in the gaseous drywell atmosphere for the time which the component must remain functional. For components I enclosed in organic material (e.g., cable), beta radiation doses were t1so calculated. Where components enclosed in organic matarials are installed in metal enclosures (e.g., I cable in conduit or flex-conduit), beta radiation will be neglected. Inspections have been performed in the Dresden 3 drywell, confirming that all equipment and cable is enclosed in nonorganic materials. Beta doses have therefore not been considered. I For components located outside the drywell, source terms were established for piping systems containing reactor steam, reactor coolant liquid, suppression pool liquid, and I containment atmosphere. Since the piping wall thickness is sufficient to shield against beta radiation, only gamma radiation need be considered. Each Class lE 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 comt.ient operating time. Where a component I could receive doses from more than one piping system, the doses were added to derive a total dose. Appendix C, Table C-3, provides integrated deses as a function of time I calculated 1 foot from the greatest single source in each major plant area. I I 7

RFicion 1 November 1, 1980 4.3.6 Aging In this, study, the need to consider aging is based on the I evaluation of component design and application. The effects of aging have also been considered based on Enclosure 4 to NRC Bulletin 79-01B, " Guidelines for Evaluating Environmental I Qualification 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 The environmental conditions inside the drywell I are defined as harsh (Sections 4.3.1 and 4.3.4) and hence the effects of thermal and radiation aging are evaluated for all Class lE electrical components. b. Components Located Outside the Drywell 1. Radiation aging The components which are located outside the drywell and steam tunnel are exposed to insignificant amounts of radiation during normal operating conditions. The effects of I radiation aging are therefore not considered in the qualification evaluation of these components. Under postulated accident conditions some j compongnts may be exposed to greater than 5 x 10 rads (integrated 7;adiation dose ). I The effects of this short-term radiation exposure are considered in the qualification evaluation. Components located inside the steam tunnel are l evaluated 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 environmental design temperature is I 103F, which in this study is defined as a nonharsh environment (Section 4.3.4). Thermal aging for these components is not 'g requi.:e d since the normal and post-accident g environments are nonharsh. In addition, temperature extremes (up to 120F) may occur I 8

Ravicion 1 I Novembnr 1, 1980 I in some plant areas. However, these conditions would result only during periods of extreme I outdoor temperatures. Equipment designed and installed per industry standards would be capable of satisfactory operation without

e. th" 8, ting age-related degradation due to I

th oe temperature extremes. Therefore, the effects of thermal aging are not considered for components located in areas where the I maximum ambient temperature is maintained at 120F or below. I 4.4 EVALUATION OF ENVIRONMENTAL QUALIFICATION DATA (BULLETIN ACTION ITEMS 2 AND 4) g Appendix B identifies all specific components necessary g following the postulated accidents. In addition, this bulletin covers general use electrical items such as motor lubricating oil, sealants, tape, terminal blocks, gaskets, etc. These general use items are discussed in Section 4.5. For each specific component identified in Appendix B, a I component evaluation worksheet was prepared. These worksheets identified the most harsh environment each component would l be subjected to following the postulated accidents. Environ-ments were considered nonharsh when the temperati.re was I controlled to 104F or less and the gaximum integrated radiation dose was less than S x 10 rads. Areas where infrequent temperature extremes up to 120F could occur, and l additionally, where temperature variations are not a result 5 of the postulated accidents are considered as mild environments. ( Equipment in these areas fur.ctions normally in the same environ-94 ment as postulated for post-accident conditions. For nonharsh g and mild environments, qualification data is not required. Since industry standards did not exist for environmental qualification of Class lE electrical equipment during the time the Dresden station was designed and constructed, qualification testing was not required for these components when originally purchared. However, many of these same l components were used i later designs and qualification testing data is availa'oie. Also some testing has been performed by the Nuclear Steam System Supplier in response to NRC IE Bulletin 79-01. These qualification reports have been evaluated to determine their applicability to the components identified in Appendix B. Where applicable j qualification data exists, this data is entered on the l component evaluation worksheets to document the suitability of the component. l 9 ~

Revicion 1 Novcmber 1, 1980 I Some components wili be qualified by analysis or a combination I of analysis and testing. In these cases, the component evaluation worksheets will reference the subject analysis and testing and document the suitability of the component. Finally for those components which are exposed to harsh environments and for which data is not available and qual-ification by analysis is not appropriate, the qualification I status will be resolved by testing, replacement, or reloca-tion of the component to a nonharsh environment. I The component evaluation worksheets are provided in Appendix D (Volumes 2 and 3) for Unit 3 and common components. The qualification plan, which will be followed to resolve I outstanding items is discussed in Section 4.5. 4.5 CLAS5 lE EQUIPMENT QUALIFICATION PLAN 4.5.1 Specific Components Where it has been demonstrated that a component will not I function under the postulated environment, an LER will be prepared. Where existing data is not available to demon-stra, qualification of a component, one or more of the I following methods will be utilized to resolve the status of the component: l I a. The component will be tested for worst case environ-mental conditions. b. Analysis of actual in-plant environmental condi-I tions will be performed to determine if actual in-plant environmental conditions are narsh. c. An identical component from the spare parts inventory or one of the installed components will be tested. I d. The component will be relocated in a nonharsh environment. e. The componei.t will be replaced. I .I I I 10 I

Revision 1 November 1, 1980 4.5.2 General Use Components I A walkdown inspection of accessible electrical boxes and cable connections was performed in the Dresden Unit 3 dry-well. The inspection was performed following the spring 1980 g refueling outage prior to returning the station to power. g Mr. J. Hughes, NRC Region III inspector, was onsite and accompanied the inspection team for a portion of the drywell inspection. The purpose of the inspection was to identify miscellaneous general use electrical items (i.e., gaskets, seals, grommets, I terminal blocks, splices, and termination tapes) used inside the drywell. In addition, the condition of cable at the electrical boxes and component terminations was inspected. g Boxes which did not have preassigned numbers were numbered 5 'Y '" 'n8Pection team. These field-assigned numbers were pr(.xed with 79-OlB. The boxes were generally in satisfactory l condition, with minor repairs required of three boxes. This Information was discussed with station electrical personnel who agreed to made the repairs prior to returning the unit to power. Splices and termination tapes were not found in the electrical boxes inspected. The results of the electrical box inspection are provided in Table 4-1. Where qualification data is not available for existing 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 l .I will include qualified materials and t teps implemented so that only these materia], are utilized on Class lE components. 4.6 SUBMITTAL OF LICENSEE EVENT REPORTS (BULLETIN ACTION I ITEM 6) In the event any Class lE electrical equipment item is ~l determined to be not capable of meeting its required func- = tion under the established service conditions, Bechtel will advise Commonwealth Edison Company so that an LER can be 'g submitted. LERs, when submitted, will identify the conditions g 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-OlB. 'I 11 -I

Revision 1 November 1, 1980 .I LERs will not be submitted for items prev lously documented .g as not being capable of meeting their required function in the M response submitted for NRC IE Bulletin 79-01 (Reference 5.0.e).

5.0 REFERENCES

I a.

USNRC IE Bulletin 79-OlB, dated January 14, 1980 b. Dresden Nuclear Power Station Final Safety Analysis Report, Docket Number 50-237 and 50-249 c. Analysis of Effects of Pipe Break Outside Primary .gg Containment, Dresden Station, Units 2 and 3, Special Report No. 37, Revision 1, February 1975 d. Dresden Station Emergency Procedures, DGA-1, Loss-of-Coolant (Break Inside Drywell), Revision 4, January 1980; DGA-2, Loss-of-Coolant (Slow Leak), -l Revision 2, Jat.uary 1980; DGA-3, Loss-of-Coolant 5 (Break Outside DJywell), Revision 4, January 1980 e. Report on Results on Qualification Data Search for I Dresden Units 2 and 3, NEDO-24218, General Electric Company, November 1979 I f. NUREG 0588, Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment I I I I I I I I 12

Revision 1 November 1, 1980 = TABLE 2-1 COMPONENT QUALIFICATION STATUS Components With Outstanding I Number of Outstanding Qualification System Components Items (%) Data Items (%) Reactor protection 8 0 0 Core spray 22 63 37 High-pressure coolant 61 5 2 injection Auto depressurization/ 47 19 3 main steam I Low-pressure coolant 54 44 .2 injection Pressure suppression 44 9 3 ^ Standby gas treatment 23 69 9 Service water 5 40 22 ~ Diesel oil piping 6 0 0 4 Containment isolation 33 12 7 Control rod drive 542 0 0 I hydraulic Reactor recirculation 45 22 15 Process radiation 2 0 0 monitoring Reactor building 4 0 0 ventilation Control room HVAC 13 0 0 Standby ac power 30 26 12 Standby de power 20 0 0 Isolation condenser 10 40 22 General use electrical 38 97 93 Total 1,007 13 8 I

Revision 0 June 9, 1980 I TABLE 3-1 LISTING OF LETTERS TO MANUFACTURERS REQUESTING QUALIFICATICN DATA I Letter Manufactor_er Chron Number Date Sent Automatic Switch 772 May 6, 1980 Barkdale 804 May 9, 1980 I Barton 820 May 9, 1980 Buffalo Forge 883 May 3, 1980 Chromalox (Dave Ray 876 May 22, 1980 I & Associates) Cutler Hammer 836 May 15, 1980 Dresser Industries 784 May 8, 1980 Edwin L. Wiegland 876 May 22, 1980 I (Dave Ray & Associates) Fenwal 785 May 8, 1980 Electromotive Division 834 May 13, 1980 I G.M. General Electric (cable) 911 May 29, 1980 General Electric (motors) 912 May 29, 1980 I GE (neutron monitoring 913 May 29, 1980 preamplifiers) Foxboro 904 May 22, 1980 Gould 835 May 13, 1980 I Harlo 877 May 22, 1980 Leeds & Northrup 893 May 22, 1980 Limitorque 914 May 29, 1980 I Magnetrol 813 May 13, 1980 Mercoid 815 May 13, 1980 Namco Snap-Lock 845 May 15, 1980 j Raychem Corporation 915 May 29, 1980 W Simplex Wire & Cable 892 May 22, 1980 Company Static-O-Ring 846 May 15, 1980 I United Electric Control 848 May 16, 1980 Versa 847 May 15, 1980 Yarway 833 May 13, 1980 I Temptron 842 May 13, 1980 Static-O-Ring (2) 916 May 29, 1980 Essex 917 May 29, 1980 H.K. Portor Company 918 May 29, 1980 i (Limitorque Peerless) I 1I 1 .I 1

W W W W 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 ELFCTRICAL BOXES INSIDE THE DRYWELL Box Location Component Number Type Elev Azim Terminal Blocks Type Remarks MO-3-1301-4 79-018-11 Pull 538 190 NA MO-3-1001-1B cont. acts l to this box also MO-3-1301-4 79-01B-25 Pull 536 85 NA AO-3-203-1A 79-01B-17 Term 524 15 Could not be identified, similar to Allen Bradley AO-3-203-1A 79-018-16 Term 521 15 GE 264D965 AO-3-203-1B 79-018-15 Term 524 5 Could not be identified, similar to Allen Bradley AO-3-203-1B 79-OlB-14 Term 521 5 GE 264B965 AO-3-203-1C 79-OlB-21 Term 524 355 Could not be identified, similar to Allen Bradley AO-3-203-lc 79-OlB-20 Term 521 355 GE 264B965 AO-3-203-lD 79-01B-19 Term 524 345 Could not be identified, i similar to Allen Bradley AO-3-203-lP 79-018-18 Term 524 345 GE 264B965 j MO-3-220-1 None NA NA NA NA Component located at 517 elev and 355 Az S0-3-220-44 79-01B-3 Pull 539 85 NA 1 S0-3-220-4 79-10B-4 Pull 539 90 NA

W W W M M M M M M M M M M M M l Revision 1 November 1, 1980 Table 4-1 (Continued) Box Location Component Number Type Elev Azim Terminal Blocks Type Remarks MO-3-1201-1 79-01B-1 Term 540 120 Inaccessible MO-3-1001-1A None NA 522 350 NA No box could be located MO-3-1001-1B 79-01B-11 Pull 538 210 NA MO-3-1301-4 connected to same box POS SW for None NA NA NA NA Inaccassible AO-3-1501-25A POS SW for 79-OlB-2 NA 517 265 NA Box could not be opened AO-3-1501-25B POS SW for 79-01B-23 Term 522 90 GE 264B965 Cover missing - Not in AO-3-1501-26A Bulletin Scope POS SW for 79 OlB-24 Pull 520 90 NA AO-3-1501-26A POS SW for 79-01B-12 Term 524 210 GE 264B965 Not in Bulletin Scope AO-3-1501-26B POS SW for 79-018-12 Pull 537 210 NA AO-3-1501-26B AO-3-220-51 79-01B-5 Term 575 90 GE 264B965 Not in Bulletin Scope i l AO-3-220-52 79-01B-5 Term 575 90 GE 264B965 Not in Bulletin Scope SRM/IRM None Pull 520 200 NA

a. m-. a I i i I I I APPENDIX A DRESDEN UNIT 3 AND COMMON SYSTEMS LIST I I I I I 3 l I I _.__..__.,I

n Revision 4 Facility: Dresden Unit: 3 November 1, 1980 Docket: 50-249 l DRESDEN 3 AND COMMON Systems or Portions of Systems Required Following a LOCA, MSLB, or Other HELB I 1. Reactor Protection System l 2. Core Spray System 3. High-Pressure Coolant Injection System 4. Auto Depressurization System / Main Steam System 5. Low-Pressure Coolant Injection / Containment Spray System l 6. Pressure Suppression System 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 15A. Reactor Building Ventilation System ISB. Control Room, Office, and Drywell Air Conditioning 16. Standby Alternating Current Power 17. Standby Direct Current Power 18. Isolation Condenser System 19. General Use Electrical Equipment I Containment isolation includes all components in various systems performing the containment isolation function.

Revision 4 November 1, 1900 TABLE A-1 SYSTEMS (AND ASSOCIATED COMPONENTS REFERENCED IN APPENDIX B) REQUIRED FOLLOWING EACH POSTULATED ACCIDENT {y) LOCA LOCA MSLB MSLB Feedwater HPCI RWCU Isolation Large Small Inside Outside Line Line Line Condenser System Break Break Drywell Drywell Break Break Break Line Break Reactor Protection X X X X X X Core Spray X X X X X HPCI X X X (2) ADS /MS X X X LPCI/ 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 X X X X X X X X Monitoring RB HVAC X X X X X X X X Control Room HVAC X X X X X X X X Standby AC Power X X X X X Standby DC Power X X X X X Isolation Condenser (2) General Use Electrical X X X X X X X X (1) This table is provided to identify which systems 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.

lI 'I I I I I APPENDIX B DRESDEN UNIT 3 AND COMMON SPECIFIC I AND GENERAL USE COMPONENTS LIST SORTED BY SYSTEM .I lI

I iI

,I I

I Facility: Drorden Revision 4 Unit: 3 November 1, 1980 Docket: 50-249 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Reactor Protection I SPECIPIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside i Primary Primary Plant Identification Contain-Contain-Number Generic Name (**) ment ment

• LS-3-302-82A,B,C,D Level Switch (M-365)

X PC 3 503A,E,C,O Prcosurc Cwitch Low X (!i 346)

• AO-3-203-1A,B,C,D Glove Valve, Air Operated X

(M-345)

• AO-3-203-2A,B,C,D Glove Valve, Air Operated X

(M-345)

• PS-3-1621A,B,C,D Pressure Switch - High X

(M-356)

• PS-3-263-55A,B,C,D Pressure Switch (M-357)

X

• LIS-3-263-57A,B Level Indication Switch X

I (M-357)

• LIS-3-263-58A,B Level Indication Switch X

(M-357) n?Ji 3 0762A,D,C,D, Inti Prcamplifier X(3) E,P,C," RAri - 3 ^7 5 2A,0, C,0 CDri Prcampli fier --- -- -x ( 3 )

• • • TE-3-1291-60A,B, Temperature Element X

C,D,E,F,G,H I 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 I

'I lg Revision 4 lg November 1, 1980 Page 2 ~ l SYSTEM: Reactor Protection (1) (Continued) (1) This listing includes additional miscellaneous components required to detect or mitigate the 7pecified accidents. Some of these components are not part of the reactor I protection system. (2) These components have been deleted because, although I they initiate a scram, the scram is an anticipatory scram for conditions not related to the postulated acci-d ela ts. (3) These components have been deleted because their function is to monitor transients not associated with the postulated i accidents. il I I 'E I I

l il 1

I

I Facility: Dresden Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 MASTER LIST .i CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Core Spray SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside 8 Primary Primary Plant Identification Contain-Contaiti-Number Generic Name ment ment MO-3-1432-25A,B Gate Valve, Motor Operated X MO-3-1402-24A,B Gate Valve, Motor Operated X MO-3-1402-4A,B Globe Valve, Motor Operated X FT-3-1461A,B Flow Transmitter X PT-3-1460A,B Pressure Transmitter X 3-1401A,S Core Spray Pump X MO-3-140:2-3A,B Gate Valve, Motor Operated X FS-3-1464A,B Flow Switch X MO-3-1402-38A,B Gate Valve, Motor Operated X PS-3-1466A,B,C,D Pressure Switch X I I I I I I i

I Facility: Drocden Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 5 MASTER LIST CLASS lE ELECTRICAL EQUIPM3NT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: High-Pressure Ccolant Injection SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside i Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment l MO-3-2301-5 Gate Valve, Motor Operated X MO-3-2301-3 Gate Valve, Motor Operated X SV 12 Turbine Stop Valve X PT-3-2359 Pressure Transmitter X FT-3-2358 Flow Transmitter X MO-3-2301-9 Gate Valve, Motor Operated X (de) 8 MO-3-2301-8 Gate Valve, Mocor Operated X (de) I None Turbine Gland Seal Condenser X Hotwell Drain Pump (de) PT-3-2382 Pressure Transmitter X MO-3-2301-35 Gate Valve, Motor Operated X MO-3-2301-6 Gate Valve, Motor Operated X i TS-3-2370A,B,C,D Temperature Switch X TS-3-2371A,B,C,D Temperature Switch X l TS-3-2372A,B,C,D Temperature Switch X TS-3-2373A,B,C,D Temperature Switch X l ll I.

I Revision 4 I November 1, 1980 SYSTEM: High-Pressure Coolant Injection (Continued) Page 2 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM i Location Inside Outside Primary Primary I Plant Identification Contain-Contain-Number Generic Name ment ment SO-3-2301-30 Air Operated Valve X .I (Solenoid) POC 3--2301 30 Air Operated Valvc X( (Position Switch)- SO-3-2301-29 Air Operated Valve X 4 (Solenoid) 1 POC 3 2301 29 Air Operated-Valvc X (Pcsition Swi4ch3-MO-3-2301-4 Steam Supply Isolation X Valve None Motor Speed Changer X None Motor Gear Unit X None Emergency Oil Pump X None Auxiliary Oil Pump X None Gland Steam Exhauster X Fan DPIS-3-2352 Differential Pressure X Indicating Switch DPIS-3-2353 Differential Pressure X Indicating Switch PS-3-2389A,B,C,D Pressure Switch X MO-3-2301-14 Gate Valve, Motor Operated X MO-3-2301-15 Gate Valve, Motor Operated X MO-3-2301-49 Gate Valve, Motor Operated X I l I

Revision 4 November 1, 1980 SYSTEM: High-Pressure Coolant Injection (Continued) Page 3 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location (elevation) Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment SO-3-2301-64 Air Operated Valve X (Solenoid) 1 POC-3 2301 6 '. Air Operated Valvc X (Positicr. Cwitch) S0-3-2301-65 Air Operated Valve X (Solenoid) POC 3 2301 55 Air Opcrated Valvc X( ( Pc c i t ion-Ewi+eh)- MO-3-2301-36 Gate Valve, Motor Operated X MO-3-2301-10 Motor Operated Valve X 3-2386 HPCI Motor Control X Signal Convertor W PS-3-2360 Pressure Switch X LS-3-2351A,B Level Switch X FS-3-2354 Flow Switch X PS-3-2368A,B Pressure Switch X LS-LCS-1 Level Switch X LS-2/3-2350A,B,C,D Level Switch X !l (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

Facility: DrOcden Revision 4 Unit: 3 November 1, 1980 Docket: 50-249 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Auto Depressurization/ Main Steam I SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary 5 Plant Identification Contain-Contain-Number Generic Name ment ment i 3-203-3A Target Rock Valve and X Associated Solenoid I_ 3-203-3B,C,D,E Electromatic Relief Valve X and Associated Solenoid Valve AO-3-203-1A,B,C,D Main Steam Isolation X Valve with Associated Solenoid Valves POC 3-203 in,D,C,D licIn Otccm Icolation Vaivc X (Position Cwitch) MO-3-220-1 Globe Valve, Motor Operated X TS-3-261-15A,B,C,D Temperature Switch X 16A,B,C,D 17A,B,C,D 18A.B,C,D MO-3-220-2 Globe Valve, Motor Operated X I AO-3-203-2A,B,C,D Main Steam Isolation X Valve with Associated Solenoid Valve I PCC 3 203-2A,0,C,D ticin Steam Icciation Valvc X(1} (Position Cwitch) I DPIS-3-261-2A,B,C, Differential Pressure X D,E,F,G,H,J,K,L,M, Indication Switch N,P,R,S i I I

Revision 4 November 1, 1980 SYSTEM: Auto Depressurization/ Main Steam (Continued) Page 2 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment PC 3 0261 30A,0,0,0 Prcseurc CWitch X(1) I I I I I I I I I E I (1) These components have been deleted because, although they initiate a scram, the scram is an anticipatory scram for conditions not related to the postulated accidents. I I

l Facility: Drced n Revision 4 W Unit: 3 November 1, 1980 Docket: 50-249 I MASTER LIST I CLASS lE ELuCTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Low-Pressure Coolant Injection / Containment Spray SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM I Location Inside Outside Primary Primary -l Plant Identification Contain-Contain-W Number Generic Name ment ment MO-3-1501-5A,B,C,D Gate Valvo, Motor Operated X PS-3-1554A,B,C,D,E, Pressure Switch X F,G,H 3-A,B,C,D-1502 LP Coolant Injection Pump X MO-3-1501-3A,B Globe Valve, Motor Operated X (and Position Transmitter) g DPT-3-1543A,B Differential Prescure X j Transmitter MO-3-1501-llA,B Gate Valve, Motor Operated X MO-3-1501-32A,B Gate Valve, Motor Operated X MO-3-1501-13A,B Gate Valve, Motor Operated X FT-3-1549A,B Flow Transmitter X MO-3-1501-18A,B Globe Valve, Motor Operated X MO-3-1501-19A,B Gate Valve, Motor Operated X FT-3-1551A,B Flow Transmitter X FS-3-1501-58A,B Flow Switch X 4 = t I A a

8 Revision 4 November J., 1980 SYSTEM: Low-Prescure Coolant Injection / Page 2 Containment Spray (Continued) SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location I Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment MO-3-1501-21A,B Angle Valve, Motor Operated X MO-3-1501-22A,B Gate Valve, Motor Operated X MO-3-1501-27A,B Gate Valve, Motor Operated X MO-3-1501-28A,B Gate Valve, Motor Operated X 3-A,B,C,D-1501-44 Containment Cooling Ser-X I vice Water Pumps FT-3-1542A,B Flow Transmitter X MO-3-1501-38A,B Globe Valve, Motor Operated X I ^'" I I I I I I I I I

I Facility: Drccdcn Revision 4 Unit: 3 November 1, 1980 l Docket: 50-249 5 MASTER LIST I CLASS lE ELECTRICAL EQUIPMENT REQUIF"D TO FUNCTION UNDER l-OSTULATED ACCIDENT CONPITIONS SYSTEM: Pressure Suppression 1 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM I Location Inside Outside Primary Primary B Plant Identification Contain-Contain-Number Generic Name ment ment LT 3-1541 1 Lcycl Tran nittcr X 1 S0-3-1601-68 Solenoid Valve X S0-3-1601-69 Solenoid Valve X POS 3 1601 51 Cate Valvc, A4r Operntcd X(2) (Position Switch) POC 3 1601 SO Outterfly Valvc, Air X Operated (Position I Switch) SO-3-8501-2A,B Solenoid Valve X ) I SO-3-8501-4A,B Solenoid Valve X S0-3-9203A,B Solenoid Valve X S0-3-9204A,B Solenoid Valve X S0-3-8501-6A,B Solenoid Valve X PS-3-1632A,B,C,D Pressure Switch X PS-3-1501-62A,B,C,D Pressure Switch X PS-3-1629A,B Pressure Switch X PS-3-1621A,B,C,D Pressure Switch X PS-3-1628A,B Pressure Switch X c3) PT 3 = P= =c T==mc = x I I l

I Revision 4 l November 1, 1980 ) SYSTEM: Pressure Suppression (Continued) Page 2 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE 3YSTEM Location Inside Outside Primary Primary Plant Identification Contain-Contain- .I Generic Name ment ment Number v(2) n..m._.

n. n c

. e n i __,, uuwww.....

u. u.i.. _

.m...- vu w uv. .e J .w, a o Cpercted (Position .r m _ t..r, I ww v s 2,\\ i a vu w .vv. 1 n..m m _ _ c.i.. t.r ~,.. _ s..t _ nac__,- sent_,A n wuwwwm.g u..w, u Opercted (Position - -. $. _n.. s, e..: v(2) en, ,,_u_

_ vym.mmmm e____m_a nmc,

.i .e, .vm m. (Pccition Switch) SO-3-1601-70 Solenoid Valve X I v(2) ,en, e, n..mm__ci.. ,2_

n. m c

u. u_,.. _

vu w .vv. ww uuwww..AJ A .w, K.A. n Opercted (Position

v. m _t.. r, c.

ms I .en. n..mm__,,.,.

u. m_,.. _

.s..._ v(2 , ce nmc, .um -mmmm. .m, m Operated (Pccition

E

m. m _ t..r, c.

-m AO-3-1601-55 Air Op rated Valve X (Solenoid) I v.. ( 2 ) nmm . e. n. n _. m _ _.c,.. u. .2.. _ c, _, ni m Opercted (Position I m:. m

u.. s, e.

mm .en. n.. m m _._ r,.. u._,.._ .m.._ v(2) nnc, mmmm Operatcd (Position I . m

t.. r u:

c. .m..._ v( nc ,en, er n..mm__rs.. ,t_1.._

n. v u -

I s Avv. sv ut.www. 4y .u. .ug n Opcrated (Position m:. m _t.. r c. mm v(2) I -_-, s rum, en su

u. m_,.. _

en n..mm__r,.. mm ummmm.. .s, n. o Opcrated (Position c. 1 m _t.. r W.. bb S0-3-1601-66 Solenoid Valve X MO-3-1601-57 Globe Valve, Motor X Orarated I I

I Revicion 4 November 1, 1980 SYSTEM: Pressure Suppression (Continued) Page 3 SPECIFIC COMPONENTS ASSOCIATED WIT!! ABOVE SYSTEM Location Inside Outside I Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment POC 3-1601 50 Clobc Valyc, ?.i-r Ope rated X(2) (Position Cwitch)- S0-3-1601-67 Solenoid Valve X POC 3-1601 207. Dutterfly,M vc, 7.i r X I Opcrated (Position C'.Jitch) POC -3 1601 200 Outterfly Valvc, 7.i r X-Opcratcd (Position Ewitch) OPT 3 1502 12 Diffcrcntial Presourc X(4) Transmitter DPIS-3-1622A,B Differential Pressure X Indication Switch LT 3 162C Lcycl Transmitter X S0-3-1601-65 Solenoid Valve X S0-3-1601-71 Solenoid Valve X S0-3-1601-51A,B Solenoid Valve X .I S0-3-1601-52A,B Solenoid Valve X S0-3-1601-50A,B Solenoid Valve X PS-3-1620 Pressure Swl.tch X I (1) This component has been deleted because it provides indication only. (2) This component has beer. deleted because it is used for position indication only and failure of the switch will not affect the associated valve control circuit. l (3) This component has been deleted because its function is required during normal operation only. (4) This component has been deleted because it is used for containment pressure control during normal operation only. I

.g Facility: Drcsdan Revision 3 g Unit: 3 June 9, 1980 Docket 50-249 MASTER LIST I CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Standby Gas Treatment SPECIFIC COMPO!:ENTS ASSOCIATED WITH ABOVE SYSTEM I Location Inside Outside Primary Primary Plant Identification Contain-Contain-I Number Generic Name ment ment 2/3-A,B-7506 Fan X FT-2/3-7541-40A,B Flow Transmitter X FS-2/3-7541-45A,B Flow Switch X MO-2/3-7507A,B Butterfly Valve, Motor X Operated MO-3-7503 Butterfly Valve, Motor X Operated I MO-2/3-7504-A,B Butterfly Valves, Motor X Operated MO-2/3-7' 9 5-A, B Butterfly Valves, Motor X Operated TSH-2/' -7 5 41-ll A, B Temperature Switch X III CCR 2/1 7541 35A,4 ECR X 2/3-A,B-7503 Electric Air Heater X FSL-2/3-7541-41A,B Flow Switch X 2223-28A,B Local Control Panel X I (1) This component has been deleted because it is integral to MCC 38-2 which is included elsewhere in this report. I I I

I Facility: Dreedon Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIR"O TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Service Water SPECIFIC COMPONENTS ASSOCIATED WITli ABOVE SYSTEM 'I Location Inside Outside Primary Primary I Plant Identification Contain-Contain-Number Generic Name ment ment I 2/3 & 3-3903 Diesel Generator Cooling X Water Pumps 3-5746A,B Emergency Air Cooler X I Reactor Building 3-5747 HPCI Building Cooler X

I I

3 I I I .I .=I I

Facility: Drccdtn Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Diesel Oil Piping .g SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM ~g Location Inside Outside Primary Primary j Plant Identification Contain-Contain-Number Generic Name ment ment 2/3 & 3-5203 Diesel Oil Transfer Pump X LS-3-5241-3 Level Switch (High/ Low) X LS-2/3-5241-3 Level Switch (High/ Low) X S0-3-5202 Solenoid Valve X S0-2/3-5202 Solenoid Valve X I

I

!I I

I

I

'I !I il g

Facility: Dracdgn Ravicion 3 Unit: 3 June 9, 1980 Docket: 50-249 i MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Containment Isolation j SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM M Location Inside Outside I Primary Primary Plant Identification Contain-Contain-Number Generic Name (**) ment ment I

• AO-3-203-1A,B,C,D Globe Valve, Air Operated X

(M-345) I

• AO-3-203-2A,B,C,D Globe Valve, Air Operated X

(M-345)

• MO-3-220-1 Globe Valve, Motor X

I Operated (M-345)

• MO-3-220-2 Globe Valve, Motor X

Operated (M-345)

• SO-3-220-44 Solenoid Valve (M-357)

X

• SO-3-220-45 Solenoid Valve (M-357)

X MO-3-1201-1 Gate Valve, Motor Operated X MO-3-1201-2 Gate Valve, Motor Operated X MO-3-1201-3 Gate Valve, Motor Operated X MO-3-1001-1A,B Gate Valve, Motor Operated X MO-3-1001-2A,B,C Gate Valve, Motor Operated X MO-3-lPJ1-5A,B Gate Valve, Motor Operated X

• MO-3-1501-5A,B,C,D Gate Valve, Motor X

Operated (M-360)

• SO-3-305-120 Solenoid Valve X
• SO-3-305-121 Solenoid Valve X

P L

I Revision 3 June 9, 1980 SYSTEM: Containment Isolation (Continued) Page 2 I i SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Primary Primary Plant Identification Contain-Contain-Number Generic Name (**) ment ment

• SO-3-305-122 Solenoid Valve X
• SO-3-305-123 Solenoid Valve X
• MO-3-1501-22A,B Gate Valve, Motor X

Operated '-360)

• MO-3-1501-18A,B Globe Valve, Motor X

Operated (M-360)

• MO-3-1501-19A,B Gate Valve, Motor X

Operated (M-360)

• MO-3-1501-38A,B Globe Valve, Motor

.V Operated (M-360)

• MO-3-1501-20A,B Gate Valve, Motor X

Operated (M-360) I

• MO-3-1501-13A,8 Gate Valve, Motor X

Operated (M-360) I

• MO-3-1501-28A,B Gate Valve, Motor X

Operated (M-360)

• MO-3-205-2-4 Gate Valve, Motor X

Operated (M-357)

• MO-3-1301-1 Gate Valve, Motor X

{ Operated (M-359)

• MO-3-1301-2 Gate Valve, Motor X

Operated (M-359)

• MO-3-1301-3 Gate Valve, Motor X

Operated (M-359)

• MO-3-1301-4 Gate Valve, Motor X

Operated (M-359) 1 I

• MO-3-1402-3A,B Gate Valve, Motor X

Operated (M-358)

• MO-3-1402-25A,B Gate Valve, Motor X

~ Operated (M-358) I I

Revision 4 November 1, 1980 SYSTEM: Containment Isolation (Continued) Page 3 SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location I Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name (**) ment ment

• MO-3-1402-4A,B Globe Valve, Motor X

Operated (M-358)

• MO-3-2301-36 Gate Valve, Motor X

Operated (M-374)

• MO-3-2301-9 Gate Valve, Motor X

Operated (M-374)

• MO-3-2301-5 Gate Valve, Motor X

Operated (M-374) AO-3-2001-105 Gate Valve, Air Operated X (Solenoid) I AC-3-2001-106 Gate Valve, Air Operated X (Solenoid) AO-3-2001-5 Gate Valve, Air Operated X I (Solenoid) AO-3-2001-6 Gate Valve, Air Operated X (Solenoid) POS-3-2001-105 Gate Valve, Air Operated X fPosition Switch) POS-3-2001-106 Gate Valve, Air Operated X (Position Switch) POS-3-2001-5 Gate Valve, Air Operated X (Position Switch) POS-3-2001-6 Gate Valve, Air Operated X (Position Switch) MO-3-3702 Gate Valve, Motor Operated X NO-3-3703 Gate Valve, Motor Operated X MO-3-3706 Gate Valve, Motor Operated X I

• AO-3-1601-60 Butterfly Valve, Air X

Operated (M-356) I I

l W Revision 3 June 9, 1980 SYSTEM: Containment Isolation (Continued) Page 4 SPECIFIC COMPONENTS ASSOCI ATED WITil ABOVE SYSTEM Location I Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name (**) ment ment

• AO-3-1601-61 Gate Valve, Air Operated X

(M-356) I

• AO-3-1601-20A,B Butterfly Valve, Air X

Operated (M-25)

• AO-3-1601-23 Butterfly Valve, Air X

Operated (M-25)

• AO-3-1601-24 Butterfly Valve, Air X

Operated (M-25) I

• MO-3-1601-57 Globe Valve, Motor Operated X

(M-25) I

• AO-3-1601-62 Globe Valve, Air Operated X

(M-25)

• AO-3-1601-21 Butterfly Valve, Air X

I Operated (M-25)

• AO-3-1601-59 Butterfly Valve, Air X

Operated (M-25)

• AO-3-1601-58 Butterfly Valve, Air X

Operated (M-25)

• AO-3-1601-56 Butterfly valve, Air X

Operated (M-25)

• MO-3-1601-57 Globe Valve, Motor X

Operated (M-25)

• AO-3-1601-22 Butterfly Valve, Air X

Operated (M-25)

• AO-3-1601-63 Butterfly Valve, Air X

Operated (M-25) I

• AO-3-1601-55 Butterfly Valve, Air X

Operated (M-25) I so-3-4720 Air Operated Valve X (Solenoid) I I

Revision 4 November 1, 1980 SYSTEM: Containment Isolation (Continued) Page 5 SPECIFIC COMPONENTS ASSOCIATED WITil ABOVE SYSTEM Location .I Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name (**) ment ment AO-3-4721 Air Operated Valve X (Solenoid) I III POC 3 4720 Air Operated Valvc X (Position Cwi+eht POC 3 4721 Air Operated Valvc X( (Position CWitch) 3-700-733A,B,c,D,E Solenoid Ball Valve X 3-700-736A,B,C,D,E Squib Shear Valve X I I I \\ !I 4 I 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 j

(1) This component has been deleted because it is used g for position indication only and failure of the switch will not affect the associated valve control circuit. . I I

I Facility: Dro den Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 l MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Control Rod Drive Hydraulic SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Primary Primary Plant Identification Contain-Contain-Number Generi: Name ment ment

• SO-3-305-117 Scram Solenoid Valve X-
• SO-3-305-ll8 Scram Solenoid Valve X

SO-3-0302-20A,B Scram Solenoid Valve X SO-3-0302-19A,B Scram Solenoid Valve X LS-3-0302-82A,B,C,D Leve1 Switch X POS-3-302-21A,B Air Operated Valve X (Position Switch) POS-3-302-22 Air Operated Valve X (Position Switch)

• SO-3-305-120 Solenoid Valve X
• SO-3-305-121 Solenoid Valve X
• SO-3-305-122 Solenoid Valve X
• SO-3-305-123 Solenoid Valve X

I .I I

• Typical of 177 Valves 1I 1I 1

Facility: Drccden Revision 4 Unit: 3 November 1, 1980 Docket: 50-249 I MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Reactor (Nuclear Boiler) Recirculation SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment LITS-3-263-73A,B Level Indicating X Transmitter Switch PS-3-263-ll1A,B,C,D Pressure Switch X PT-3-6'.'A,0 Prescurc Transmitter X(1 1 LT-3-S'.6-A,E Level Trancmitter X 1 PT 3 552 Precourc Trcncmitter X I PS-3-263-52A,B Pressure Switch X PS-3-263-55A,B,C,D Pressure Switch X LT 3 263-51 Lcvci Transmittcr X(

l

's MO-3-205-2-4 Gate Valve, Motor Operated X (3) POC 3 220 51 Clche-Vcivc, Air Operated X (Position Switch) (3) AO 3-220 51 Cicbc Valvc, Air Operated X (Colcncid) (3) POC 3 220-52 010bc Valvc, Air Operated X (Pccition Switch) (3) AO 3 220 52 Cicbc Vcive, Air Operatcd X (Colencid) I I I

Revision 4 November 1, 1980 Page 2 SYSTEM: Reactor (Nuclear Boiler) Recirculation (Continued) SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM I Location Inside Outside Primary Primary Plant Identification Contain-Contain-I Number Generic Name ment ment LITS-3-263-59A,B Level Indicator X Transmitter Switch LIS-3-263-57A,B Level Indicator Switch .X LIS-3-263-72A,B,C,D Level Indicator Switch X LIS-3-263-58A,B Level Indicator Switch X (4) PCC 3 220 Cicbc Valvc, ?.ir Operated X ^^ (Position Switch}- AO-3-220-44 Globe Valve, Air Operated X (Solenoid) I4) POC 3-220 ^5 Cicbc Valve, ?.ir Operated X (Position Switch) AO-3-220-45 Globe Valve, Air Operated X (Solenoid) I DPIS-3-261-35A,B,C,D Differential Pressure X E,F,G,H Indicating Switch I DPIS-3-261-34A,B,C,D Differential Pressure X Indicating Swit.ch (5) MO 3-202 A.?.,O Cct Valve, Mci e -Oper-at e d X MO-3-202-5A,B Gate Valve, Motor Operated X MO-3-202-6A,B Gate Valve, Motor Operated X MO-3-202-7A,B Gate Valve, Motor Operated X MO-3-202-9A,B Gate Valve, Motoi? Operated X (1) These components have been deleted because they are required for control of the feedwater regulation valve during normal operation only. (2) This component has been deleted because it provides indication only. I

I , I Revision 4 November 1, 1980 Page 3 SYSTEM: Reactor (Nuclear Boiler) Recircul:61on (Contint 4) (3) This piping system does not penetrate the drywell, therefore, these valves are not required for containment I isolation. (4) This component has been deleted because it is for position indication only a.;d 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

Facility: Dresden Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Process Radiation Monitoring SPECIFIC COMPONENTS ASSOCI ATED WITil ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment RE-3-1735A,B Rx Building Ventilation X Radiation Element I I I I I I I .I 1 E I

i Facility: Dresden Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 MASTER LIST l CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTZM: Reactor Building Ventilation f SPECIFIC COMDONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside

E Primary Primary

.m Plant Identification Contain-Contain- _ Number Generic Name ment ment AO-3-5742A,B Butterfly Valve, Air X Operated (Solenoid) ll AO-3-5741A,B Butterfly Valve, Air X l" Operated (Solenoid) !I lI !I ~l

I

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I Facility: Drecdon Revision 3 Unit: 3 June 9, 1980 3 Docket: 50-249 g MASTER LIST l CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS S SYSTEM: Control Room, office, and Drywell Air Conditioning SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment 2/3-5772-100 Isolation Damper and X Solenoid Valves 2/3-5772-99 Damper X 2/3-5772-101 Isolation Damper X 2/3-5731 Supply Air Fan X 2/3-9472-024 Damper X 2/3-9472-023 Damper X 2/3-5772-62 Damper X 2/3-5728 Return Air Fan X 2/3-5790 Diesel Generator Room Fan X 2/3-5732A,B Control Room Air Con-X l ditioning Compressors SE-2/3-8941-013 Smoke Detector X So-2/3-9441-003 Solenoid Valve X SO-2/3-9441-004 Solenoid Valve X g i 8 l 8 1 0

Fccility: Drecdsn Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 MASTER LIST CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: Standby Alternating Current Power i SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside i Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment 3-5209 Standby Diesel Generator X 2/3-5209 Standby Diesel Generator X l SWGR 33-1 4.16 kV Switchgear X SWGR 34-1 4.16 kV Switchgear X SWGR 38 480 V Switchgear X SWGR 39 480 V Switchgear X MCC 38-1 480 V Rx Building MCC X MCC 38-2 480 V Turbine Building MCC X "CC 38-3 480 V Turbine Building MCC X 'I MCC 38-7 480 V Rx Building MCC X MCC 39-1 480 V Rx Building MCC X MCC 39-2 480 V Turbine Building MCC X MCC 39-3 483 V Rx Building MCC X M0 39-4 480 V Rx Building MCC X MCC 39-7 480 V Rx Building MCC X I RPS Bus 1 120 V ac Reactor Protec-X tion System Bus 1 i RPS Bus 2 120 V ac Reactor Protec-X tion System Bus 2 I

I l Revision 3 lI June 9, 1980 SYSTEM: Standby Alternating Current Power (Ccntinued) Page 2 l SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location i I Inside Outside Primary Primary f Plant Identification Contain-Contain-Number Generic Name ment ment Essential Service 120/240 V ac, Essential X Bus Service Bus Instrument Bus 120/240 V ac Instrument X Bus Essential Bus 120/240 V ac Essential X MMG Set Bus Supply MMG Set 2223-41 D/C 2/3 Excitation Cabine* X None D/G 3 Excitation Cabinet X None D/G 2/3-3 Engine Control Panel X None D/G 2/3-3 Speed Sensing Panel X at Engine None D/G 3 Relay and Meter Panel X 2223-33 D/G 2/3 Relay and Meter Panel X None 4 kV Nonsegregated Bus X I I 8 I I I E I

Facility: Drcedsn Revision 3 Unit: 3 June 9, 1980 Docket: 50-249 MASTER LIST .g CLASS 1E ELECTRICAL EQUIPMENT W REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Standby Direct Current Power SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM I Location Inside Outside Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment 250 V Batt Chgr 3 250 V Battery Charger X l 250 V Batt Chgr 2/3 250 V Batter Charger X l MCC 3 (Turbine 250 V de Turbine Building X l Building) MCC l 3 MCC 3 (Rx Building 250 V dc Reactor Building X l5 Bus 3A & 3B) MCC 250 V Battery 250 V dc Battery X 125 V Batt Chgr 3 125 V Battery Charger X 125 V Batt Chgr 3A 125 V Battery Charger X 125 V Battery 125 V de Battery X 125 V DCDP Main Bus 3 125 V dc Turbine Building X l Distribition Panel (Main Bus) 125 V DCDP Res Bus 3 125 V dc Turbine Building X Distribution Panel (Reserve Bus) 125 V DCDP Main Bus 3 125 V de Reactor Building X Distribution Panel (Main Bus) l 48/24 Batt 3A & 3B 48/24 V Battery X 24V Batt Chgr 3A & 24 V Battery Charger X 3B (+) 24 V Batt Chgr 3A & 24 V Battery Charger X 3B (-) l 48/24 DCDB 3A & 3B 48/24 V de Distribution X Panel I

Facility: Droeden Revision 4 Unit: 3 November 1, 1980 Docket: 50-249 ,I MASTER LIST CLASS lE ELECTPICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS SYSTEM: Isolation Condenser SPECIFIC COMPONENTS ASSOC ~ATED WITH ABOVE SYSTEM Location Inside Outside i Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment 1) POC 3 1301 17 Clcbc Valve, Air Operated X (Position Switch) I AO-3-1301-17 Globe Valve, Air Operated X (Solenoid) I POC 3 1301 20 Cicbc Valvc, Air Operated X(1 -fa7sition Cwitch) AO-3-1301-20 Globe Valve, Air Operated X (Solenoid) MO-3-1301-3 Gate Valve, Motor Operated X (dc) DPIS-3-1349-A,B Differential Pressure X Indication Switch MO-3-1301-4 Gate Valve, Motor Operated X MO-3-1301-1 Gate Valve, Motor Operated X MO-3-1301-2 Gate Valve, Motor Operated X (dc) DPIS-3-1350A,B Differential Pressure X Indication Switch I (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 1l l

Facility: Dre: den Revision 4 Unit: 3 November 1, 1980 Docket: 50-249 MASTEh,._ST I CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS I SYSTEM: General Use Electrical Equipment 'l SPECIFIC COMPONENTS ASSOCIATED WITH ABOVE SYSTEM Location Inside Outside I Primary Primary Plant Identification Contain-Contain-Number Generic Name ment ment Cable 5 kV Power X Cable 600 V Power and Control X X Cable Instruments X X Cable Thermocouples X X Electrical Pene-High-Voltage Power X X tration Electrical Pene-Low-Voltage Power & X X tration Control Electrical Pene-Instruments X X tration Electrical Pene-Thermocouples X X tration Terminal Blocks Terminal Blocks X X I 'E I I I

4 I I lI ) I !I ApeEND1x c 4 DRESDEN UNIT 3 KEY ELAN IDENTIFYING HARSH ENVIRONMENTAL AREAS AND TABULATION OF 1 SERVICE CONDITIONS I 4

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I Revision 1 November 1, 1980 LIST OF FIGURES AND TABLES I Figure C.1 Plan view general arrangement drawing identifying harsh environmental areas for I Dresden Unit 3 el 476'-6" Figure C.2 Plan view general arrangement drawing I identifying harsh environmental areas for Dresden Unit 3 el 517'-6" I Figure C.3 Plan view general arrangement drawing identifying harsh environmental areas for Dresden Unit 3 el 545'-6" Figure C.4 Plan view general arrangement drawing identifying harsh environmental areas for Dresden Unit 3 el 570'-0" Figure C.5 Plan view general arrangement drawing identifying harsh environmental areas for Dresden Unit 3 el 589'-0" and 613'-0" Figure C.6 FSAR Figure 5.2.11 providing the drywell pressure response following the postulated I LOCA Figure C.7 FSAR Figure 5.2.12 providing drywell temp-I erature response following the postulated LOCA Table C-1 Maximum environmental conditions inside I the drywell for the postulated LOCA Table C-2 Maximum environmental conditions outside the drywell following the postulated HELB Table C-3 Post-LOCA maximum radiation doses for areas I 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 8 I I

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g g^g m~M M M M W 8 i 50

a. ONE CONT. COOLING LOOP 2 CORE SPRAYS

b. BOTH CONT' COOLING LOOPS-1 CORE SPRAY

c. ONE CONT COOLING LOOP.1 CORE SPRAY

d. % CONT COOLING LOOP-1 CORE SPRAY 40 C

5 ~ l En E 30 G \\ M INITIATION OF CONTAINMENT SPRAY E 6 20 I-C 10 y o (d) ~ M g(a,c) O I 0 10-1 i 10 101 '1 102 103 104 105 y 106 TIME AFTER ACCIDENT (SECONDS) Figure 5.2.11 Pressure Response to Loss-of-Coolant Accident

---

J

300 4 6 g i i i

a. ONE CONT. COOLING LOOP-2 CORE SPRAYS

b. BOTH CGNT. COOLING LOOPS ICORE SPRAY

c. ONE CONT. COOLING LOOP-1 CORE SPRAY 250

d. % CONT. COOLING LOOP-1 CORE SPRAY 200 1

C L INITATION OF E CONTAINMENT SPRAY 3 (d) 1 (a, c) 2 150 fj (b) -j ?!$ i 5 40 50 2 ? o I I I I b 0 10-1 100 101 102 103 104 105 106 TIME AFTER ACCIDENT (SECONOS) Figure 5.2.12 Temperature Response to Loss-of-Coolant 4. -ident

Revision 0 June 9, 1980 TABLE C-1 MAXIMUM ENVIRONMENTAL CONDITIONS INSIDE THE DRYWELL FOLLOWING THE POSTULATED LOCA Relative Containment Gamma Submergence Temperature Pressure Humidity Spray Radiation Elevation 7 281F 63 psie 100% Demineralized 1 day-4.3x10 rads 505'-6" i 8 water 30 day-lxlO ads 1 year-1.1x10 rads l l l l j

Revision 1 November 1, 1980 TABLE C-2 MAXIMUM ENVIRONMENTAL CONDITIONS OUTSIDE THE DRYWELL FOLLOWING THE POSTULATED HELB Maximum Maximum Relative Pressure Temperature Humidity Area Pipe Break (psia) (*F) (%) Torus compartment High-pressure 27.0 242 100 (region of postulate 1 coolant injection l CI line break) steam Reactor building pipe Isolation condenser 27.0 242 100 chase, el 589'-0", f'O'-0", and 545'-6" south cf drywell between Columns L and M near Column 41; and iso 11-ion condenser area Steam tunnel Main steam / 27.0 242 100 feedwater Reactor water clean _; Reactor water Not evaluated - Only containment heat exchanger and

lding cleanup isolation valves required to function.

pump room Qualification will meet conservatively assumed drywell LOCA conditions. High-pressure heater bay Main steam / Not evaluated - No equipment which is feedwater required to function is located in this area. Turbine Building Main steam Not evaluated - No equipment which is el 538'-0", required to functio 4 is located north of Column G, in this area. between Columns 40 and 42 and 46 and 48

E E E E E M M M M M M M M M M M M Revision 1 November 1, 1980 TABLE C-2 (Continued) l Maximum Maximum Relative Pressure Temperature Humidity Area Pipe Break (psia) (*F) (%) Reactor feed pump room Feedwater Not evaluated - No equipment which is required to function located in this room Diesel generator room Feedwater Not evaluated - Qualification for the environment due to a postulated feedwater line break is not required since three diesels are available to provide ein cgency ac power.

l Revision 0 June 9, 1980 TABLE C-3 RADIATION r.NVIRONMENTAL CONDITIONS OUTSIDE DRYWELL 19LLOWING THE POSTULATED LOCA MAXIMUM RADIATION SOURCES Integrated Dose Levels (rads) Area Source

• 1 Day 30 Days 1 Year 7

Torus SP 1.5x10 3.2x10 3.9x10 5 5 6 Low-pressure coolant injection SP 2.4x10 9.4x10 1.7x10 corner rooms 6 High-pressure coolant MS 6.6xlO 1.6x10 1.7x10 injection room 5 6 Steam tunnel SP 1.9x10 7.0x10 1.3x10 6 6 Reactor building RW 2.5x10 7.8x10 1.4xlO el 517'-6" 6 Reactor building CA/SP 2.2x10 6.2x10 1.1x10 el 545'-6" 5 5 Reactor building CA 2.2x10 5.4x10 6.1x10 el 570'-0" 6 Reactor building RW 3.2x10 1.1xlO 1.8x10 el 589'-0"

• SP = Suppression pool liquid RW = Reactor water MS = Reactor steam CA = Containment airborne

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