ML20133C947
| ML20133C947 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/31/1985 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20133C929 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8508070187 | |
| Download: ML20133C947 (75) | |
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SUMMARY
REPORT QUAD CITIES STATION UNITS 1 & 2 COMPLIANCE TO REGULATORY GUIDE 1.97 REVISION 2 July 31, 1985 hp Mk! b54 PDR C_ __m_-___ _ _ _ _ _ _ _ _ _ . _ . - _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _
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Aj Table of Contents Page l l Section I Executive Summary.............................. 2 l Section II Introduction................................... 7 Section III Technical Approach............................. 8 Section IV Variable Summary Table......................... 17 Section V Justifications................................. 52 Section VI Conclusions.................................... 61 Appendix A References...................................... 62 Appendix B Table 1: BWR Variables (NRC Regulatory Guide 1.97, Revision 2)........................ 63 Appendix C Abbreviations Used in Appendix B............... 71 Appendix D Abbreviations Used in the Variable Summary Table.......................................... 73 i i. 1 l o 1-s -p 'm. r
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~ EXECUTIVE
SUMMARY
Section I Commonwealth Edison Company has analyzed the existing instrumentation to determine if the measurement range, design, qualification criteria, and other guidelines outlined in the Regulatory Guide 1.97 (hereinafter called the Reg. Guide) are met. The methodology used is delineated in Section III, Technical Approach. Every variable in the Reg. Guide has been checked for its applicability to station specific requirements. In addition, we have verified that variables required in the task analysis (generated through the DCRDR) have been included in our analysis. The requirements of Supplement 1 to NUREG 0737 (the design of the Safety Parameter Display System (SPDS), design of instrument displays based on Regulatory Guide 1.97 guidance, control room design review, development of function oriented emergency operating procedures, and operating staff training ) are being integrated with respect to the overall enhancement of operator ability to comprehend plant conditions and cope with emergencies. The Reg. Guide variables are grouped into 5 types: A, B, C, D and E. Type A variables are those which the operator requires in order to perform specific manually controlled safety functions for which no automatic control is provided. Type D variables provide information to the operator to indicate whether or not the station safety functions are being accomplished. Type C
r e variables provide information to indicate the potential or actual bre'ach of fission product barriers. Type D variables provide the operator with indications of the operation of individual safety systems or other systems important to safety. Type E variables are used to determine continually the extent of radioactive material releases to the environment. l Type A, B, and C variables relate to the determination of the safety condition of the plant and provide the operator with the information to perform tasks needed to mitigate accidents. Table I.1 on page 4 identifies 1) the total number of variables reviewed (83); 2) the number of variables which is not required to meet the Reg. Guide due to the station configuration; 3) the number of variables to which exception is taken; 4) the number of variables which require design modification or instrument replacecent in order to meet the Reg. Guide requirements; 5) the number of modifications required to meet the Reg. Guide; and 6) the number of to be analyzed /possibly modified variables.
Table I.1 Relative Compliance Total number of variables.......................... 83 Number of variables not applicable to Quad Cities Station............................................ 3 Number of variables to which exception is taken.... 4 Number of modified variables....................... 13 Number of modifications needed..................... 5 Number of analyzed /possibly modified variables..... 5 Table I.2 summarizes the required changes, by variable, needed to meet the requirements of the Reg. Guide. The analysis to determine whether an instrument needs to be replaced will be completed and any instruments requiring modification or replacement will be included in the implementation schedule due February 1, 1986. This schedule was committed to by Commonwealth Edison Company in the Confirmatory Order dated June 12, 1984. Section II contains an introduction. Section III contains an elaboration of the technical approaches used. Section IV contains the Variable Summary Table. Section V contains justifications for deviations from the Reg. Guide. Section VI contains conclusions which may be drawn concerning the extent of the station's compliance to Reg. Guide 1.97. i l 1 l l 4
Tcbio I.2 e Summary of R;quircd Chnngsco Variable No. Variable No. in Summary Action in Summary Action Table Required Table Required Al M, rewire, recalibrate, 36 - revise 37 - A2 M, replace 647A,B; add 38 A (calc); M. shield or s/c isol, recal replace A3 A, recal, rescale 39 M, replace xmtr A4 - 40 - A5 - 41 - A6 M, add temp (avg), recorder 42 - (indiv) and.isol. to 43 - computer 44 - 45 A/M analyze / replace TC 01 - if necessary see 32 02 - 46 A/M analyze / replace 03 - if necessary 04 M, see Al for LWR 47 - 05 - 48 - 06 M, see A2 49 - 07 - see A3 50 - 08 - 51 P, see 15 09 - see A3 52 - 10 - 53 - 11 - 54 - 12 - 55 - 13 - 56 - 14 M, see A2 57 - 15 P, recalibrate, rescale 58 - 16 - 59 - 17 - 60 - 18 M, see A3 61 - 19 M, see A2 62 - 20 - 63 - 21 - 64 - 22 - 65 ) 23 - 66 M, Mod in progress 24 - 67 l not part of R.G. 1.97 25 - 68 - 26 - 69 - 27 - 70 - 28 - 71 - 29 M, see A3 72 - 30 - 73 - 31 M, see A6 74 - 32 A/M, analyze / replace 75 - sensor if necessary 76 - 33 - 77 - 34 - 35 -
- See Legend next page o
M Total A 1 M 5 A/M 4 P 1 Legend A = Analyze for environmental qualficiations M = Modification req'd A/M = Analyze first, modify if analysis fails P = Documentation change
- = No change req'd S/C = Signal converter LWR = Lower wide range level O
I i l ~6-I
e INTRODUCTION Section II This report summarizes the review of Quad Cities Station Units 1 and 2 for compliance to the Nuclear Regulatory Commission Regulatory Guide 1.97 Revision 2 " Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environ Conditions During and Following an Accident" and delineates the extent to which the station meets the requirements of each variable in this Regulatory Guide. In assessing the compliance wiht R.G. 1.97, Commonwealth Edison company used information contained in various station docu.nents listed in the reference section of this report. Each variable l listed in the Variable Summary Table follows sequentially with the listed variables in the Reg. Guide. The results of the l review are summarized in Section IV of this report. Deviations from the guidance in the Reg. Guide are explicitly shown with supporting justification or resolution alternatives in Section V of this report. The justifications are listed by the variable number referenced in the Variable Summary Table. Summaries which form the bases for these justifications are available for
- auditing purposes.
r-f TECHNICAL APPROACH Section III Quad Cities Station Units 1&2 began operating prior to many of the current regulations concerning seismic and environmental design. Consequently, the Quad Cities has committed to update original designs as needed to keep current with the regulations. The following information identifies the major areas used in the technical approach in this study. The analysis began with a survey of the as-built plant configur-ation to examine which systems are applicable to the Reg. Guide requirements. The survey included the attributes and qualification status of existing instrumentation which may be used to fulfill the Reg. Guide requirements. A document review combined with a plant walkdown was performed to confirm documentation and drawing information. The documents reviewed are referenced in Appendix A. The plant walkdown determined whether or not the instrumentation was actually installed. Some instrumentation is undergoing modification due to require-ments other than those for Reg. Guide 1.97. Therefore, all modifications currently being installed as well as all planned modifications were reviewed to determine the extent to which they might affect those variables required to be monitored. l
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After gathering the basic data for each parameter, the data was analyzed to determine the degree of compliance with the Reg. Guide. A work sheet was filled out summarizing the following for each variable type, function, description, degree of compliance j requirements relative to seismic and environmental qualification, quality assurance requirements, redundancy, range, power source by bus, type of display and display location, comments and recommendations. l l A table was generated to show how the data for a particular instrument loop compared with the Reg. Guide requirements. Where the instrumentation conformed to the Reg. Guide, the work sheet identified the compliance. l If the instrumentation did not comply with the Reg. Guide, either justification was provided to explain that the existing instrumentation should be retained and why its deviation is acceptable or recommendations were made for the replacement or modification of instrumentation to meet the Reg. Guide requiremento. A variable Summary Table in provided in Section IV which summarizes the results of the analyses. Deviations from i the Reg. Guide which are not covered by suggested modifications and/or analyses are explained in Section V Justifications. The selection of Type A variables for this station has been based on an analynis of the required tanks the operator in required to i perform as delineated in the Station Technical Specifications and l
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e Emergency Operating Prccedures (the DCRDR Task Analysis). These Type A variables and the criteria for choosing them are as follows:
- 1) Reactor Water Level - used as a criterion to initiate SLCS, stop ADS, and flood up the Reactor Pressure Vessel;
- 2) Reactor Pressure - used as criterion to initiate emergency depressurization and flood the Reactor Pressure Vessel (RPV);
- 3) Drywell Pressure - used as a criterion to initiate drywell and torus sprays, and restart Standby Gas Treatment for venting primary containment;
- 4) Suppression Chamber (Torus) Pressure - used as a criterion to initiate drywell and torus sprays, depressurize the RPV and flood the RPV;
- 5) Suppression Pool (Torus) Water Level - used as a criterion for initiating ADS, starting drywell and Torus Sprays, suppression pool water cooling and torus and drywell venting;
- 6) Suppression Pool (Torus) Water Temperature - used as a criterion for initiating suppression pool water cooling, reactor scram and RPV depressurization.
The type B, C, D and E variables are identified in the Reg. Guide. We have verified that the variables required by the Task Analysis are included in the A-E variables in the Reg. Guide. Refer to Appendix B or the Variable Summary Table in Section IV. Plant specific variable ranges, which incorporate the Reg. Guide guidance for Types A, B, C, D and E variables, are listed in the Variable Summary Table under Variable / Required Range. Seismic Concerns , The seismic criteria for Quad Cities Station Units 162 has not changed from the original design. Specific seismic requirements ___,s
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f for safety-related instrumentation have also not changed. The seismic requirements for all new equipment are delineated in Commonwealth Edison Company Design Criteria DC-SE-01-DQ, Revision 3 dated April 2, 1985. Therefore, currently installed safety related instruments which either fulfill the requirements of Regulatory Guide 1.97, Revision 2, Category 1 or those which were previously designated as seismic by the 1980 FSAR Safety Related and ASME Classifi-cation Valve, Equipment and Instrument List, the Master Equipment List or the instrument data sheets will not undergo seismic qualification. Replacement instruments or new instruments must meet the seismic requirements of IEEE 344-1975, Regulatory Guide 1.100 and station requirements. Safety-related instrument racks have been seismically upgraded by adding bracing as required. However, instrumentation mounted on these instrument racks has not undergone additional seismic qualification beyond the original design. Environmental Qualifications In order to show that safety-related electrical equipment is capable of functioning in a harsh environment, Commonwealth Edison Company provided a response to IE Bulletin 79-018 for Quad Cities Station Units 162. Environmental zone maps were established which identified the temperature, pressure and radiation values in various locations of the station. That j f I h l equipment which performed a safety-related function and was located in a harsh environment was included in the program to be environmentally qualified for its respective location. Safety- ; related equipment in a mild environment was not required to have additional environmental qualifications. l i The approach taken for the Reg. Guide in this analysis was to use the 10CFR50.49.K ruling allowing the us#e of instrumentation that , was qualified under the 79-01B program. Instruments that were not covered under the 79-01B program but are required to fulfill l Category 1 or Category 2 requirements of the Regulatory Guide, I may be qualified by engineering analysis if like instrumentation ! has been previously qualified by the 79-01B program. An engineering analysis to show qualification will be performed on I other instruments when the materials from which they are composed l can be identified. I If none of the above actions can be performed, then the
- instrumentation will be replaced in order to meet the i
requirements of Category 1 or Category 2. If an analysis can be i i made to show that other diverse instrumentation can be relied on to provide the operator with the needed information to perform a specific task, this analysis will be used in lieu of l qualifictiation. The analysis required to confirm environmental i qualification will be concluded before February 1986 so that any
- additional modifications can be included in the implementation
- schedule.
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E l l l , l l i Power Sources Power sources for instrumentation have been checked for their 1 ! ability to provide power under postaccident conditions. Each bus has a main source and at least one backup or reserve source of power. Table III.1 page 16 lists the buses, the main source to the buses and the reserve source. Each Category 1 variable requires redundancy to ensure that at i least one channel provides the necessary information to the i operator. Existing instrumentation for every category 1 variable j was checked to verify that the redundant loop receives power from l a different bus. Neither Category 2 nor Category 3 instrumentation requires i redundant monitoring channels. Therefore, only one power source for these categories of monitoring instrumentation is required. Even though this station was licensed prior to the categorisation of power sources as Class IE or non-!E, the power sources and the reserve sources provide the required reliability to meet the intent of this Reg. Guide. Cables All instrument cables have been included in the environmental qualification program for Quad Cities Station. Under this program the cable tabulations were checked to catalogue instrument cables by manufacturer and cable type. The purchase
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e specifications for these cable types were then checked to identify the approved vendors. The environmental qualification (EQ) program included original station design instrumentation cable. The environmentally qualified cables are identified in section 19 of the Response to IE Bulletin 79-01B for the Quad Cities Station. This station was licensed before Regulatory Guide 1.75 estab-lished the requirements for physical independence of electrical systems. Existing instrumentation used for postaccident monitoring does not follow these separation requirements. New instrument loops added to fulfill a Category 1 requirement will comply with the requirements of Regulatory Guide 1.75. 10CFR50 Appendix R requirements will be complied with as part of other commitments to ensure the safe shutdown of the reactor in the event of a fire. Quality Assurance Requirements Quality annurance requirements for instrumentation were extracted from either 1) the FSAR safety-related and ASMC Valve, Equipment and Instrument Lint, 2) the instrument index, or 3) the instrument data sheets as applicable. Regulatory Guide 1.26 originally dated March 23, 1972 did not apply to the design of Quad cities Station Units 1&2. QA requirements are delineated in Appendix B of the updated FSAR. These requirements have controlled the purchase and installation at Quad Cities k__.____ ___m..__._ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ - _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
1 l e Station. Current QA requirements will be followed for new instrumentation where those requirements apply. TSC and EOF In accordancewith NUREG-0696, the required set of Type A, B, C, D and E variables from Reg. Guide 1.97 Rev. 2 will be available (availability listed in the Summary Table under TSC and EOF) in the Technical Support Center (TSC). Since the computer system which provides that information is linked to the Emergency Operations Facility (EOF) also, the required data points available to the TSC will also be available to the EOF. Variables that are manual in nature are not required, and will not be available at the TSC (examples grab sampling with onsite analysis). Inputs which are not currently provided as noted by a "No" in the TSC, EOF column of the Variable Summary Table will be determined by the Task Analysis produced by a Human Factors Review of the TSC and EOF. The resulting modifications will be included in our implementation schedule due February 1986. Identification of Postaccident Monitoring Instruments Reg. Guide 1.97 suggested that accident monitoring instrumenta-tion be uniquely identified to aid the operatot during accident conditions. This item is being addressed in the Detailed Control room Design Review, nc~ as a specific Reg. Guide issue. l l i i
Table III.1 l MAIN RESERVE BUS SOURCE SOURCE MCC 19-1 and MCC 29-1 Division I 480V BUS tie to a Division 120VAC Distribution switchgear backed up II Bus with a diesel POnel by a diesel generator generator backup Computer A dedicated UPS feeds none l the computer 125VDC Turbine Room Battery chargers Batteries and Unit Main and Reserve (Divis;,on I and II) generators Distribution Panels from Units 162 48/24VDC Distribution Supplied power through 48/24V batteries or Panel A and 5 battery chargers which the Division I diesel are fed from the generator 120VAC instrumentation BUS 120V Essential BUS 1 A UPS normally feeds Division I 480V cnd 2 this BUS. The UPS is switchgear BUS backed fed from 3 sources, up by a diesel l 250VDC battery, generator Division II switchgear l which is backed up by a diesel generator and from a non-divisional 480V BUS 120V Instrumentation Division I 480V Automatic transfer to BUS switchgear BUS backed non-divisional 480V up by a diesel switchgear BUS l generator MCC 18-2 and MCC 18-2 Division I 480V Manual transfer to BUS 120VAC Distribution switchgear backed up tie to a Division II POnel by a diesel generator BUS with a diesel generator backup R0 actor Protection Division I 400V Manual transfer to BUS A switchgear to motor non-divisional backup generator set supply 480 V BUS R0 actor Protection Division II 480V Manual tran9fer to BUS B switchgear to motor non-divisional backup generator set supply 480V BUS l - - -
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~
VARIABLE
SUMMARY
TABLE j Section IV
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,. '*he, Variable Gummary Table lists the displays which fulfill the
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requ'.trement for tne variables 1n the Regulatory Guide. The s Va.iab'54'Su m.iry Table is formatted that the first and second she'etpi for tne ,'.1stod varLablas be laid side by side to lint all t.N'd.itatissociated'withagivenvariable. Table IV.1 identifies t$a meanings of the'variouc tiulds in the table. The meanings of the'abbreviatians unsd in the table can be found in Appendix D.
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I l e l I Table IV.1 Column Definitions for Variable Summary Table Column Definitions i Variable / Required Range: The variable being monitored as listed in Table 1 attachment to the
. Regulatory Guide and its required range specific to the Station.
Type / Category: The categorisation of the variable based on how the information for the parameter is used as defined by ANS-4.5 and the Regulatory Guide 1.97, Revision 2 (R.G. 1.97, Rev. 2) The set of design criteria required l to be applicable to the instrumen-tation monitoring variable. Existing Range The range of applicable instrumenta-tion for the parameter as found in l station documentation. l Display Type: Continuous indication, recording, trending by computer or indicating lights. j Present Environmental A " comply" or "will comply" indicates l Qualifications that the documentation will be suffi-cient to show that the instrumenta-tion used to monitor a parameter is qualified performing its safety function under accident environmental conditions. Present Seismic A " comply" or "will comply" indicates l Qualifications that the existing or replscement instrumentation will continue per-forming its safety function following l a design basis selsmic event. Channel Redundancy: Identification of whether the varia-ble is displayed via redundant instrumentation as required by the Regulatory Guide. Power Supply: A " comply" or "will comply" indicates the electrical bus that feeds the-l ...-. - -
f Table IV.1 (Cont'd) Column Definitions Power Supply (Cont'd): instrumentation complies with the intent of the Regulatory Guide requirements for reliability. TSC: A "yes" or "no" indicating whether the variable is currently provided to the Technical Support Center. EOF: A "yes" or "no" indicating whether the variable is currently provided to the Emergency Operations Facility. Comment: Reference to other information as may be necessary for clarification or a statement that the station complies with the requirements of the Regula-tory Guide 1.97. s I L 4
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P l A A A A A A C Y l T A D C A U Q R L i H I tl L L MR L L R R A U O O S ig l A U U l OR O R C % i I l s S P f P F t S p S i g l I t Y v "8 E L g N Hi s N A N A R R E 4 H0 Hi s 0 I O W i O W U I A E l I p I f I I o I 4 C 01 p 1$ ) S ) S ) A "6 M / N R i R 1 L S S 0 S S 0 S S R 5 t E A O O L 5 1 U 7 E U l 3 E U 11 S t R I I o I HR HR i HR i l C "5 C t W o t TO V o 1 O M ot l A 1 IO L t l l RI RD f A 3 E 2 R - A E 0 R 8 Y 4 N [ t 0 lu( S to0 l u( S l f t O l U T ( I ( 0 A A I I V U _ R Q A E l 2 3 4 5 6 V R A A A A A A j ,i fi ! ijIl; ;jji i 1 i I , .
. .g QUAD Cliffs - UNIIS 1 & 2 Sin +1ARY Ri tu<l 01-73-85 22 lHfStNI lHfStNI ENVIRONMlNIAL SEISMIC CilANNL L l' owl R VARI Altl i QlJAlIIICAllON QUAlIrlCATION RIDtN)ANCY SUl1*l Y ISC' 1 05
- UM4fNTS Al RfACIOR llVil Complies Ccaplies Ccmplies Complies Yes Yes fransmitter loops will be recalibrated and arranged to provide a qualified eecordcd channe1.
l 42 RI ACIOR fHI SSURL Complies Wi l l Conpl y Complies Complies Yes Yes Qualifiedtranbitterswillbe installed. I 1 A3 URYWI 1 l IHLSSURL Wiii Compty Comptius Compties Compiles Yes Yes Analysis for !Q will be performed, i A4 $Ui1HESSION OIAMillR Will Comply Complies Complies Complies Yes' Yes Some as A3. Also see Justification j (IORilS) THi SSilRI Section. o I
- A3 SUI'lHI SSION POOL Compiles Compties Campi ies Compteus Yes Yes Compiles wi1h requiremenis. i (IORUS) WAlfR !
11 Vi l I i A6 SilPlHLSSION l'OOl Complies Ocmplius Cunpl ies Complies No No Average Suppression Pool Water , ilORUS) WAllR lempera t ur e Record i ng w i l l t>e l Il ke'l RA I URI added to the 14ain Conte of floard. I i 5 l
+
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' Additional inputs to the ISC and 100 which aru not cur rent ly provided (swiled as "No" in the ISC,105 co l umn *,) will be determined by the Task Analysis Produced by llumen Foctors Review of the ISC and 106 Ihu resulting modificolions will be included in our inep t emen t a t ion schedu le due february, 1986.
i i4
23 VARI Atit E'
SUMMARY
I AHi t UUAD ClIllS - 11 Nils.1 & 2 StM4ARY Ril0RI 23-85 . VARIABII/ lYP1/ FXISTING D1SPIAY RtQUIRID RANGE CAIlCORY RANGF IYPi 01 NEUIRON fIUX lil 10 to 100 Cl*S Indicator SRM: 10 -6 to 105 10 to IO DCPS Recorder AiHM O-1001 0-1255 Recorder 02 CONilMX 14JO 11 3 full in i iqtif t. (G) I'OSil10N 00 to 48 Digital Ind f ull in 00 to 48 C(unpu t er 03 RCS S0tUlil[ DORON 11 5 Osfutson Analy/cr CONCE NIRAI10N Ikpenden t (SAMPil) O to 1000 ppm-O to 1000ppe 04 C008 ANT IIVEl IN lit -243" to 57" Indicator RCAC10R -334 to 66" Recorder
-296" to 117" -42" to 358" Indicator 05 indR CORT. til N/A N/A Illt RMOCOUPt E S see comments 0 0 200 1 1o 2300 1 06 RCS PRESSURL 111 0 to 1500 psig Recorder 0 to 1500 psig 0 to 1500 psig Indicator 01 IMYWi l l lHI SSIM lil -S to 2$0 psig Indicator 0 to 63 psig -5 to 250 psig Recorder i
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QUAI) Cl l l LS - uni l s 1 & 2 Sill 44ARY Rilmi (11-23-85 24 lHESENT fHf St NT INVlROPO4L NT Al SLiSNIC CllANNI L loft R e VARI Allt t QUALIIICATION QtIAL1I1 CATION RtOl1NDANCY SlH'I*t Y ISC' I Of a COpect NIS 01 NiUfRON l TUX None None Compiles Compiles Yes Yes See JustifIcolion Section. 02 CONIROI 140 0 N/R N/R N/It Compiles Yes Yes Ompt les wi th requirements, 8 %)S t I ION 01 RCS sot tatt i 110RON N/R N/R N/R Ca plies N/R N/R Complies with requirements, CONCINIRAllON ISAMPti) 04 COOT ..NI I I Vi l IN Complies Compiies Omnplies Complies Yes Yes Complies with requirements. RtACIOR O*) ItWR CORE N/A N/A N/A N/A N/A N/A see Jusiiiicalson Section. IIfl RMOCOUI'l L S 06 RCS IHI SSURL Complies will Comply Complies Complies Yes Yes Some as A2. 01 11RYWI I I IHLSSURE Wiii Compiy Compfie, Compiles Compties Yes Yes Some as A3.
. y 25 .
VARI AHi t SLM4ARY T Altl i QUAD Clldl$ - UNil5 1 & 2 SIM4ARY HlPOHI 07-23-85 , VARIAHtE/ I YPL / FXISTING DISPtAY RfQUIRED RANGl' CAIICORY RANCE IYl4 08 DRYWtti SIM* I I VI I fil N/A N/A Iksi tom to top see comunen t s 09 IHlMARY CONIAINMLNI DI -5 to 250 psig Indicolor IHLSStRL -5 Io 250 psig Recorder
-5 to 63 psig 10 - IHIMARY CONIAINMINI Ill Open - Closed Ib illon ISOLAllON VAlVI Iigtils POSITION (IXCIUDING CitiCK VAlVLS)
Open - Closed 11 RADIOACTIVIIY C1 1 uCi/gm to Analyfer CONCINIRAllON OR 10 Ci/gm 1 ChanncI RADI ATION I FVil IN CIRCULAllNG IHIMARY COOlANI 2.5 to 500 uCia/gm 81-151 dose equivalent 12 ANAL YSIS Of IHIMARY C5 1 uCi/gm to Analyter COOLANT (CA>NA IO Ci/qm SPtCIRUM) 10 uCi/gm io 7.02 Ci/qm 13 IlWR CORI. CI N/A N/A litt le40COUPI t S see commenis , 200 i to 2300 I
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)
Y N V N A O l I L H49 I > S i I I V I I B t l O A 1 M N N G V I I A O C _ t O O N N I V A N l C f O ( ) lU S C C O O N i A l O 1 4 N l l V 1 1 IR 0 Ci Y l S I M 1 t C l Y l Y f l C N l R R I N R R O l R $ R A l Mt K l A I A I A S A I OM i A $ A L I C C O C l C iM Y t C C H I W M I M OsX) f I N ) l O 1 l lt l Y ( m I Hl H I HI S TI I ( O f ) I A O C RNN H I I A O N C s t R i W l l A I I l R A 4 1 I R A 8 9 0 I 2 3 V 0 0 1 I 1 1 J1~ l11] 4 4 : : i '! l! 1 ,1 il}I i {j> I <a t i
m 2I VARIMili StM4ARY I Allt I QUAD ClIll 5 - LM1IS I & 2 StM4ARY Rt PORI 01-23-85 , VARIABtE/ TYPE / EXISTING DISPtAY RfQUIRID RANGE CAIlCORY RANGF f Yi4 14 RCS PRt SSURt 01 0 to 1500 psi 9 Recssder 0 to 1500 psig 0 to 1500 psig Indicolor 0 15 IHIMARY CONIAINMtNI C3 10 to 10 R/br Reux der AREA RADIAllON IDrywell) I to 10 N/hr I to 10 N/hr Recorder (forus) 16 INYWIII IMAIN SUMi% Cl N/A N/A I i vi t (IDINI11ItD see conunents AND (MfDINIilitO
- l t AKMA p Bottos to top 17 SUPlHLSSION P0(X. C1 0 to 30 tt. Indicolor WAllR LLVEL 0 to 30 ft. Recorder 3 to 17 ft.
18 ORYWit t IHESStHE Cl O to 60 psig Indicolor O to 63 psig Hoth channels 19 RCS IHLSStHL Ci o to 1500 psig Recorder 0 to 1500 psig 0 to 1500 psig Indicator 20 IHIMARY CONTAINMLNI C1 -5 to 250 psig Indicolor lHLSSURL -5 to 250 psig Recordes
-5 to 252 psig
T1
= .
m QllAI) Cllll S - llNIIS I & 2 Sl##4ARY ltilTWI 07-23-85 28 PRESINT IHISI NT [NVlHONMENTAl SLISMIC CilANNi l IWIR VAH1 ARI i QUAlilICAIlON QllAl16BCATlON lll filNI)ANCY SUPPLY ISce g og " C0004 NTS 14 14CS PHE SSURL Complies Will Comply Complies Complies Yes Yes. Some as A2. 15 IHIMARY CONI All#4f NI N/R N/R N/R Complies Yes Ye s Recalibration and resealing A141 A NADI AllON of low end for range requirements. 16 IWYWt t i LNAIN silMP N/A N/A N/A N/A N/A N/A Same as 08, li vil t ilM NI ll il D AND (MilM NI16 ll D liAKAGI) 17 $U11HLS$10N l'OOL Complies Complies Cumplies Compiecs Ye. Yes Compl ius w i t h s equ i r e. men t s. WATIR IIVII 18 IRYWi ll IRI SStHL Will Comply Complies Complies Complies Yes Yes Some as A3. 19 RCS IHt SStHL Compties Wiii Compiy Compties Compties Yes Yes Samo as A2 20 INIMARY CONI AINME NT Compiies Compties Compiies Compiies Yes Yes See Justification Sectlon, fHLSSIRE a
29 VARIAHit Stae4ARY IAlstl QUAD Cilll S - IMIIS I & 2 StM4ARY Ri tutt 01-23-85 . VARI AHI E/ IYPf/ FXISilNG I)l5PI AY RfQUIRtD RANGE CAllCORY RANCE I Yl't 21 CONTAINMLNT AND CI O Io 1Of Recorder DRYWi! L HYUMOCl N 001h channeIs CONCINIRAll0N O to 30f (-3 to 63 psig) 22 CONIAINM(NI AND Cl O to 10f Rt.cor der ORYWill OMYGI N iksth channels CONCENIRAll0N O to 108 (-3 to t:5 psig) 23 CONTAINMINi C3 10 1o 10 uCi/cc Recor der il i i U1 NI xe-I55 RAlliOACI I V 1 I Y - 50' to 106rpm Cnti Iera NOHLL CASIS (IROM IINNTIFilD RIlFA56 10lNIS INCLUDING STAE1HY CAS TRfAT-MI NI SYSIE M VI NI)
-6 10 to 10" uCi/cc
y QUAD CllllS - UNilS I & 2 StH4ARY RilO48 07-23-85 30 lHESENI IH1 St NI I NVil40NMI NI AI SilSMIC CilANNi l IWi lt VARIAltif QUAL if ICAl l0N QUAlliICAll0N RilMINDANCY Sul11 Y ISCa 1 01 ' COD 94fNIS 21 CONIAINMINI /ND Complies Complies Q nplies Ocwplies Yes Yes See Justification Section. IN4YWI I L llYIN40Cl il CONCINTRAllON 22 CONI AINME NI AND Complies Complies Complies Complies Yea Yes Qaplies wi th requirement s, 184YWI I L OXYGIN CONCINIRAIION 23 CONIAINMtNT N/R N/R N/R Complies Yes Yes Cm plies with requirements, fiiiUtNI RADIO-ACIlVIIY - NODII CA$t5 (INOM llWNIllllD RlltASE IT)lNIS INCIUDING SIANIMlY CAS lRtAl-MI NI SYST[M VFNT)
l 31 VARI Alli t SilMMARY T Alli t (,MJAD Cllll S - IINil5 1 & 2 SIM4ARY HilO41 01-/3-85 , VARIAHIE/ l Yl*[/ IXlSilNG DISPIAY RfQljlRID RANGl CAllCORY RANCI lYPl 24 RADI AllON EXPOstlRE C2 0.1 to 1000 mR/llr Recorder RAIE (INSIDE 1500iDiNCS OR ARIAS, i.G., AUX 11iANY llullDiNC, iUlt ilANIX ING IMillDING St CONDARY CONI AIN-MI NI , Mil O f ARI IN DIRICI CONIACI Wl Ill IHIMARY CJWil A1 NMI NI Will RI f*tNIIHAIIONS AND flAICittS arf IOCA11D 10 to 10 R/hr ?$ lillulNI HADlQ- C2 10' to 10' uCe/cc Recor der ACI I V I I Y-N0lli i CASIS Xe-131 (6 tulM DUllDINGS AS 10to 10 cpm Cnti ferm INDICAIFD A110VE)
-6 10 to 10 uCi/cc 6
26 MAIN lit DWAllR D5 0 to 6x10 I nd i a.olor IIOW Ibs/hr (ex h pump) 6 6 O to S.6x10 0 to 12x10 Recos der Ibs/hr Ibs/hr(lofal) 21 CONDINSAll SIORAGI D5 0 to 37 It Indetalor IANK IEVil O to 32 18 28 St#*lHLSSION CilAMDI R D2 O to 20,000 gpm Recor der SlHAY f l OW D to 215 gpm
. 2 3 o
. en h o t
g on n t i o d i
's l
nt e a u p c p ei in dyt i f s s s t t t n er s n n n io d a u e e e vJ m m m t iv e e e c os r e ee i r ir ir S e S p gS u u u I n q q q n N s a e e e o 1 rR . r r r i 0 0 o e i a 0 f n h h h 0 . o t t t c C inF oO s i w i w i w I f ml n i o . s s s t nd i n e ie ie s u n aio t i ia a t i i l p l p lp J rcd c m m m e eS a e 4 A o e C I e S 0 C C S 5 8 5 2 7 0 a y s s s s s i ( e e e e e g Y Y Y Y Y m i d I Y a R C s s s s s A S e e e e e N I Y Y Y Y Y N l t S Y s s s s s R t ie e e e ie W 1' i i i L VIS N tp lp lp lp tp 2 I m m m m m o o o o o
& C C C C C t
S l i m Y t L C L N
- N A N D S A N I l t
OD i l R 14 R R R l f / / / / / i R N N N N N C D A U N Q O I T CT N I A t MCI S S i 1 F HLS I I l R R R R R A / / / / / U N N N N N Q l N T A O I N I I I A s s N N CI e ie L N i S O I lp tp E H I e HI V l n m R R m ( A o o / / o N U N C N N C [ Q
, - N R L S G N I 0 L l R A N I R ) l C l i
U L I A 1 D F I f A M S R Y DI N I 1 N - V R A WA I N C 0 H O R O l IV A. A A R l I i l ll O A Y l D S H I C X l f 1 uU C i l I R I S t l l N N A A ll S 1 i O 1 f H C N A N N N A O ) A l NW S 1 Y i CO N t l I A R - H S f M L i O 0 N N G X GG R i V G I V Hl eIRA $ D I I l l t 0 l l l I N U N N A I I A M I l 0 I N T I I( N I l A i l A S 1 1 5 l I I l D D 1 N ,C A I 0 ll I V S D C l N Y A L L . l 0 O T N C N t R t i t IN N 0A U l t t S i D I N l l K N IHA E I I I C. ll l I A 'W t i i N A 1 H i ACC A uNl I D A U il A t I l I O 1 ( i I N l H A R U ( l l l S M l I W C 1 H f l l A OI I S A I R l M C S R > A 4 t ? 8 V 2 7's 7 ? 2
y.. . . ~ . . - ._ _. - __ . . . . . _ . _ - . _ _ . . . . . _ . _ - .._m ._ .. ...m. _._ ..m. -- . . _ ~ _ _ _ _ _ . . . _. 33 VARIMitt SupetARY IMitt QUAD Cl f it S - tmlIS I & 2 StMMARY Ril1HI 01-23-85 VARI AtM E / IYlT/ EXISIING DI5l1 AY Rf QUIRT D RANCE CAIICORY RANCE IYl1 29 DRYWE LL IHLSSURE D2 0 to 5 psig ludicolor ,
-3 to 3 psig O to 75 psig Recorder ;
o to 70 psig 30 StN4HfSSION 1001 D2 N/R N/R WAllR IfVit see comments (wir design) 3I StN1HI $$10N l'001 02 0 to 300 i Reuw der WAllR Il WIRAlllRt 0 30 i f u 230 6 l 32 INYWLil AIMOSI'lll RL D2 40"I to 400"I Computer
- II W(RAllHE (min) i 40 t to 440 i O to 600 t Ruuw der 33 DRYWt LL S4 HAY f LOW D2 O to 12,000 gem Indicator O to 5170 gpa . l i
i 34 MAIN SIEAM OSOLAll0N D2 N/R N/R ; VAL VLS' t [ AKACI see comments CONTROL SYSilM IH[SStlRf , 35 IHINARY SYSTE M SAI E TY D2 Closed - t iglil ! RtL11i VAlVI open l'OS I I IONS, g iNClUD1NG AUS OR , F I OW IllHOUCil OR IHfSSURI IN val VI , 1 INE S . Closed - not closed i i I I
QUAI) CillLS - tmlis 1 & 2 StiMMARY Rt KWI 07-25-8S 34_ . PRf SENT FHfSINT [NV1RONMINIAt $[lSMiC OIANNLL POWIR VARI Allt f QUAliflCAllON QllAl if lCA T ION Id OUNIMNCY StN1't Y ISC8 I Ol e COpetNIS 29 IWYWi l l FHfSSURE Will Comply N/R E/R Complies Yes Yes Some as A3. 30 StW4HiSSION POOt N/R N/R N/R N/R N/R N/R Ihe Suppressfort Pool al Quad Citles WAltR llVit Station.does not contaan a weir well.
.51 SIN 4HI SSION P001 Complies N/R N/R Ca ptees Yes Yes Complies with requirements.
Wall R II M1 RAltN41 32 IWYWf'll AIMOSlHE RL Will Comply N/R N/H Compliet. Yes Yes Analysis for IQ will tse performed. Il M'l RAllHf Sensor w i 1 i 1,e rep t aced, it necessary. 55 IWYWi l l SlHAY ll OW Complies Complies Crmplies. Complees Yes Yes Instrument is used to verity only that flow exists. Complies wi th olla:r requirements. 34 MAIN SILAN ISOtA N/R N/R N/R N/R N/R N/R Ihis system does not exist al IlON val VI I E AKAGE Quad Citles Station. CONil40t SYSIEM IHI SStHE 35 IHIMARY SYS1tN Complies N/R N/R Complies Yes Yes Complies with requirements. SAf f lY Ril st i VAlVL POSITIONS, 1NCELUtNC ADS OH I L OW Il#40001 OR ikt S$4HI IN VAtVL I INI $
r 35 V Al41 Alll i StlHMARY I Allt f QtJAl) CllllS - IINIIS I & 2 SilMMARY R!luti 01 - 7 5- t:5 . VARI Allt f/ TYl'f / IXIS11NG DISPIAY HiQUIRED RANCE CAllCORY RANCE B Yl*l 36 ISOEAIION CONDINSER I)2 N/R N/R SYSitM Sliitt-SIDL see comments WAltR (fVfL 0 to 12 ff 37 ISOL AllON CONut NSt H D2 N/R N/R SYSitM VAlVI. see comments iM illON Open 38 ICIC f l OW 132 O to SOO gpm ilo Ind. Cntrl O to 440 qpa 39 lati ilOW D2 0-6000 9pm India.aliv i O to $500 gpm 40 CORI SlHAY SYSilM D2 0-6000 gpm I nd i c a t or iI OW O to 4950 99= 41 1Its SYS11M iiOW D2 0-22 m 10 gpm Re< order O to 15950 gpm 42 StCS 1iOW D7 N/A N/A O to 42.9 gpm see comments 43 SICS SIORACE D2 0-1005 I nd s c,s t or I ANK t i vt l 0-1001
_ m - __ _ _ _ _ _ . . _ _ . - _ _ . . . - , _ . . . ~ _ - - - . . _ _ _ _ _ _ - _ . . _ . ~ . . .__..--._..__._..m- . - - . ~ . _ .__ b e QtlAD ClIIIS - tmIIS 1 & 2 Slee4ARY Id 1941 07 85 M PHI SE NI PHEStNT
- l ENVIRONNI NI At StiSMIC OIANest1. l' OWL R V AN_I.A.HI i QlJAtiIICATION QljAtiIICAiiON NiOUIOANCY SINi'l Y ISCe gge C0844NIS ,
j 56 ISOIAIION COesMN$tM N/H N/M N/R N/R N/R NM4 Ihis sysIce does not enist ai SYSItM SHfIt-SIDt' Quad Citles Statlon. is4IIH tivlt i i i i ! 57 1500 AllON (X)esN NSE R N/R N/H N/R N/R N/H N/H this system does not exist at SYSffM VAIVf Quad Cities Station. ! 38 HCIC ItOW None N/H N/R Complies Yes Yes Analysis f or t Q will tw perf ormed. l Sensor will be replocco, it necessary, i ) h e f i 39 lett f l OW Will C(anply N/H N/R Complies Yes Des Quali t ied Ironsmi t ter wi l l tsu installed, i i 4 i i f h 40 COH1 SlHAY SYSIE M Complies N/H N/R Complies Yes Yes t'e mapl ies w i t h r equi ronmen t s, ) llOW j .- a i . t 45 8 5'C1 SYSitM ftOW Complies N/R N/R Complies Yes Yes Complies with requirements. t l 47 StCS ItOW N/A N/A N/A N/A N/A N/A See Jusiificalion Section. {. 4 4 45 StCS SIORAGl Compties N/R N/N Compiles No No Campf ies Wiih requirements.
- IANK lkV11 }
i, 4 I ..
! t 1
i l i i I 1 I, I 5 ! l i
= .
37 VARI Alli t $1M4ARY I Allll QUAD CilllS - UNIIS I & 2 SINMARY Ril'ORI 07-73-85 V ARI Allt I / IYl4 / EXISilNG Disti AY RIQtilRID HANGI CA Il GNY RANGl I Yl1 44 D H SVSifM fIOW 07 O-??uIO gpm Heror.ter O to 15950 gpa 45 50 H lli AI I XQiAtJGI R D2 0-M)O I Raor der Ollit f I I! MPI RA lilR1 (l l'Cl lif XOH) 0 32 1 to 3501 46 C001ING WAllR D7 O-600"t Recorder ll H1 RAIURf 10 I St SYSIEM COMT)NI Nis 32 I to 700 1 47 C001ING WAllR I)? O 8000 gpm Indacolor IIOW IO I SF SYSILM COMPONLIS O to 7700 gpm 48 IllGI RAD 10ACIIVilY D3 0 to 1001 Rec or der iIQUID LANK 16Vil O to 100% 49 iMilClNCY VINIll.AlION D1 Open-Clo<,ed i e gt.t . DA66T R POSI T ION Open-C1used
R
, 8 8 4 * ;I
;?
gj (, i i =- 'i 88 kC 3% -* B3 84
-=
e t
-- $u
. ._ a 1- .
1: 8
~
52> 8t [ 21 21 ; gi x . u - t -t j -, yMi4 e 3 1 21 -% o=2 =5 3 i i 8. 5 m 3 _ _. a -2 -2 2 2: 8@2
%a
=
8- 8_ 3 =t 3~
- : : =: : 88 f= f= 26 3: 4
-)
1 a " y . 48e i . y e7 pi' d i ) EX A ii 233 E
,1, 7
~
o -
- f 9 - ,
~ a_ > > 1 1 1 2 5
E
~
= L a
l 2 2 2 2 2 2
> + a e + a +
xy .G
. .D 4
_3 0
.0 6
3,se a . - a e g [ g e d u d d
~
il 5I b O g I I x E z E z E z kz kz 5 5
~
7"; 25h g-3: g E E E E E E 5 25 > > 5c _E 6_ _$ .$ N &
>~
z 3 3 x m O 2% t-ts : 3_ _s - E_ l ,i x 2
-xx 2:
E 1 # E7W N b~ _5 M eC .= U 1-{yr_
=1 E Z > {
155 5 O og 2 _x
> g une ~ p # y @ "
g p
~
g -5 EEt g 3 s s33 h:t-1C _ 2O h~. t51 I_ = c c ~ e e p- e w w w at w
39 VARI A13l E StM4ARY I Altl E QtlAD CillfS - UNIIS I & 2 StM4ARY Ril'ORI 01-23-85 , VARIMME/ T Yl'E / EXISilNG DISI'l AY RfQUIRfD RANrE CAlfGORY RANCE I Yl'f 50 STAIUS Of SIAM 0Y D2 O to 600 AM 5 Indicator IVWlR AND OlllE R O to $250 Vac Indicator (NERGY sot lRCfS $8 to 62 III I nd ic a t tw IM VRIANI 10 SAltlY O to 100V todicator (ItYl)RAllt IC, O to 150V I nd ica t or l'Nl tMAl l C) O to 300V Indicator 0 51 M4iMARY CONIA1NMINI Ii 10 to 10 N/hr Recor der ARL A 64ADI AllON - (Min, of (IVywell) iloth t hannels filCil RANCI 2 Wide:l y IR/hr to 10 R/hr ,cpar a t e delet f or s f ram
- 60 Kt:V to 3 AcV
- 20s where ener gy is from 0.1 NV to 3 MeV overall a(. cur oo y w/in factor of 2 over entere range.)
52 RtACIOR IMDG. OR t? O.I to 1000mR/hr Recorder
$1CONDARY (Overa11 CONIAINMINI ARfA system RADIAlION a(curacies 10 to 10 R/hr, mithin a f ac tsn^
of 2 l
s O QUAll ClIILS - UNII$ I &2
SUMMARY
R1I W 1 07-23-85 40 IHI SI NI IHf St NI [NVIRONMINTAl $115MIC OIANNII IW1 R VARIAH46 QUAa11BCAfION QilAl16ICAllON Ri lillNDANCY Sulii Y ISC' l (A 8 CODNINIS SO $I A105 Of STAMEY Compiies N/R N/R Compfies No No CAwnplies wi th requiramenis, lOttR AND 01111R INIRCY SOLIRCfS IM O4fANI 10 SAI I I V (llYllRAUI I C, IHilMAllC) Si lHIMARY CONIA' % NI Complies N/R Complies Complies Yes Yes Some os 15
\RIA RADIAllON -
194G1 RANCl $2 kl ACION tilliG. OR Name N/R N/R Complies Yes Yes S.sme as 24
%I CONI MRY CONIAINMINI ARLA RADIAllON
O 41 VARI Alli i SIM4ARY I Alu t QUAD CllitS - UNIIS I & 2 $l# NARY Rtlutt 01-25-85 , VARIAHil/ IYPt/ IXISIING DISI'I AY RIQUIRfD RANCE CAllGORY RANGI ( Yl4 53 RADI AllON [XPOSUR[ t2 0.1 to IO00mR/hr Recorder RAlf (INSIDL llt (C.'S. OR AHf AS (th:tes f or s metre ACC[$5 IS w/t:0 KcV RIQulRfD TO SIRvfCl to 3 kev EQUIP. IM O4fANI 10 +20% wher e SAllIV) ener g y as
~I #
10 R/hr io 10 R/hr irom O.I WV t.o 3 NW overaII oCCutocy w/in factor of 2 over entise ronge) 54 N0lu I GAsl S I/ N/R N/R DRYWL4t l'UNGE see commen8 SIANIM1Y GAS lOverall IRlAIMENI SYSilM system l'tNG (fOR MARK I occutocir, AND 11 l'1 ANIS) AND within a SLCONDARY CONIAIN- f a f or MLNI IU4GE (IOR ut 2) MARK II AM) I11 PiANIS 10 uCi/cc to 10 uCi/cc
2 4 e
. v o
s - I 2 l i S d n aI o I se sl : l e e R i n l n I N iorlia : t v 1 4 o e b l l i s O o C . sl 4 2 ie p t i s o C e id m m o 4 uu S Q o e-3 2 t U e g s R l e / E o_ g Y N it i t l Y e R C s R A S e / M I Y N N I S Y s H 4 ie 1 2 WlSu I lp m R o / C N I 5 1 1 N Y J ( I C I N
- N A N D S A N I l 1
1 I OO l R
/
R t / I R N N C D A l l N Q O I N C i 1 I A F M C S S 1 f i i HLS I I l R R A / / l l N N Q t N A O I I N I T t A N M C t N I S Of f R i e R n R P IV Al o / N U N N L Q D - f I N N R S M A I ) U A S K S S I 1 . il R ) IA R O I O R ' l A S A S N N i X hA $$ l O C Y M I O f( A t R 0 U Q I S MSA S R A N C N iN O CC I 1 WI I S i N i I I l G I O t Y D N 9( P S N 4 1 Ol l l sA I R 1 A Y A C l y t t M 8 W1N 1 1 CRI U 0 V IHS l I 1 l A I 1 i u I 1 1 N ll t i i W lN A 0 O I K I Y A D C N R H iwRtQR 15 iM A i l t 6 i I 2 D A l t HI% R N A A R i tl l 1 l I S O I 11 A $ IM M A I R I J I R A 3 4 V S $
43 VARINili SUMMART INM L QUAO CliIES - IMIIS I & 2 Sl##4ARY Ri tuti 07-23-85 VARIAHiI/ IYlT/ E XISilNG ()lM*1 AY Hi QUINT D RANCE CAIlCORY ltANCi 1 Yl't 55 StCONDARY CONTA1NMENT t2 N/R N/R PtlHCE (TOR NAIM i, see commeni il ANI) lli PIANIS) (Overall 10' uCi/cc system to 10 uCi/cc accuracies . within a factor of 2) 56 $1 COM)ARY (XMI AINMI NI i2 N/R N/R (RI ACION Silllll) see comment till1G ANNiilllS,11 (Overall IN INSICN system 10'D uCi/cc accuracies to 10" uCi/cc , within a iactor of 2) 57 AUXILIARY HullDING f2 N/R N/R (INCITE) LNG ANY see comment ful)G. CONI AINING (Overall fHINAltY SYS, CASE S system L.C., NASIL CAS accuracies IX CAY T ANK) . within a
-6 10 uCi/cc factor 3
to 10 uCi/cc of 2)
+ .
QilAD CilitS - UNilS 1 & ? SilMMANY HlW H1 01-73-85 44 IHi $1 NT IHLSENI INVIRONMINTAt StiSMfC ClIANt4L t 00WIR VARl Al11 I QtJAl if ICAI ION QllAlii1CAIION RIDUNDANCY St N Pt Y ISC' 1 Of a COMMINIS 55 StCONDARY N/R N/R N/it N/R N/R N/tt Some as 54 CONI AINMf NI IHRGt H OR MARK l, 11, ANI) lli PlANIS) % SICONDARY N/R N/R N/H N/R N/H N/R Same as 54 CONIAINMINi (Rf ACIOR Silti t D lit 10. ANNillUS, il IN IX$1CN) 57 AtlXllIARY ltullDING N/R N/R N/R N/R N/R N/It Same as 54 (INCilN11NG ANY lil!X;. CONT AINING IHIMARY SYS. GAslS I.C., WAS!! CAS DECAY IANK
<2
=
i
. .* .. t .*7'
_ ,, < , o 45 _, VARI AHI E StM4ARY I Allil ,'t,HAD Ci l l L S . - UNIIS 1 & 2 SLM4ARY RLPORI 07-23-85 m . . 1 VARIABIf/ TYPf/ EXISTING DISPIAY \y
.RfQUIRID RANGE CATI GORY RANGE IYPt 3. . c $ ^ 'Wl[ '
e %-{ 1 4
$8 CODMON PtANI VLNI L2 10 to 10 uCi/cc Recorder ' ' s YOR MJLTitutf0SL Xel33 VENI DISCilARGING (Overall 10I to 106 cpm Cnti ferm '
5:'NN ANY Of AHOVL RflI ASI S (lF system accurac i ers
~'k '
ORYWLil. OR SGIS. within a T .-. PtlRGI 15 lNCilllX D factor of **
-6 10 uCi/cc of 2) to 10 uCi/cc
e'.
$9 N/R I All Ollil R llM Nili llO t/ N/R ,
Rf I I ASI POINIS 4 .. - - , . . a... 10 uCi/cc (OveraiI -
- s '5j to 10 uCi/cc sysice ~~ '
( accuracies within a d 7 , foctor of 2) , 60 PARIICUL AIES AM) L3 I uCi/gm to Anal /yer ilAlOGENS AlL 10 Ci/ syn IDENIIFllD RLtEASL POINIS, SANPIING WIIll ONSIll ANALYSIS CAPAHitIlY 10~ uCi/cc 2 to 10 uCi/cc 61 RADIAL 10N EXIOSURL I NON! N/R N/R ME II HS (CONIIMJOUS see commenis INDICAll0N Al iIXLD 10 Call 0NS)
.e QllAD CilllS - UNilS I.& 2 SilMMARY Ril'ORI O/-2 5-tis 46 PRESI.NT PRESE NT ENV1RONMtNIAL SEISMIC OlANNIL IOWLH VARIARLF QllAl1fICAT10N QlJAtIfICATION RIOUNDANCY SilPPtY- ISC' IOf8 COMMFNTS 58 CODOION PLANT VLNT CompIies N/R N/R Comp 1ies ~ Yes Yes Compiies wiih requiremenis.
OR MUL TlI'URIME VfMI DISOIARCING ANY Of AHOVE Rt i t ASI S (11 DRYWitt 04 SGIS, l'tlRCI 15 INCllllM D)
'59 Al 1 01111 R N/R N/14 N/it N/R N/14 N/it Quad Cities Sidiion has no ollwer llM NI1118 D Notale Gas r elcose poin ts in a RI t i Ast l'OI NI S post-occident condsiion, t>0 l'ARilOll All s AND N/R N/R N/It Complies No No (bnpl ic . wi t h t equirement s, llAt W. INS AlI fl4 N1il ILD liANI HlilASE ICINIS. SAM-I'l I NG WIIll ONSI16 ANALYSIS cal'AHil 1 I Y 61 RADIATION fXIVSURL N/R N/R N/R N/R N/R N/R See Justificalion Section.
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SUMMARY
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JUSTIFICATIONS Section V The justifications are listed by the variable number and name and identify the deviations of the instrumentation, provide a discussion of the rationale for alternate means of meeting the Reg. Guide intent and identify the recommendations for upgrade, if any are required.
Variable Variable Number Name Identification A4 Suppression The differential pressure between the Pool Pressure suppression chamber and the drywell is minimized by the torus to drywell vacuum breakers. There are 12 vacuum breakers and they actuate at approximately 0.5 psid. The drywell pressure monitors (Variable No. A3 & 20) will be used to check excessive pressure in the torus knowing that the actual pressure in the suppress-ion chamber should not be greater than 0.5 psi higher than the drywell. Another instrument loop is available for backup as well as planned modification to add containment water level monitoring which will be implemented in such a way as to provide drywell pressure, containment level and torus pressure via the computer. 01 Neutron Flux The existing neutron monitoring system (SRM/IRM/APRM) is considered acceptable even though the cables and detectors inside the primary containment are not qualified for a LOCA environment. The updated FSAR Figure 7.4.3:3 pg 7.4.3-3 is a chart which shows the relationship of SRM count rate to actual core power level. Even though the SRM's are fully withdrawn during startup to prevent rod block, the SRM readings can be correlated to the actual power level based on the attenuation factor of the surrounding materials and the known neutron leakage factors for this BWR design. The attenuated power levels at the SRM , (when fully withdrawn) change directly as-the core power level changes. A period meter is provided which shows how quickly the power level changes relative to the factor of "e". Therefore, this meter is capable of showing power level changes down to minimum sensitivity of the
Variable Variable Number Name Identification detector even when the detector is fully out of the core. This gives the operator information on the direction of power changes ~. Two SRM channels are powered from 24V/48V Bus lA(2A); the other two channels are powered from 24V/48V Bus 1B(2B). The source of power to the SRM drive system is Buses 18-1, 19-1 (28-1, 29-1); two SRM drives per bus. The probability that all four SRM drives would lose power is remote. It is probable that at least one SRM drive will operate. The Intermediate Range (IRM) Power level instrumentation may be relied upon as a backup. These eight detectors (similar to the SRM's) are capable of co related powerleveldowntoabout5x10-g%when fully inserted. The IRM's are also powered from the same buses as the SRM's. The probability of at least one of these eight operating is very high. In addition to the above neutron level monitoring there are eight APRM channels which may be usable, however, there is little chance that the APRM's would be utilized unless increasing power level could not be controlled by the negative reactivity of the control rods. Under the conditions of a design basis LOCA event the scram system is assumed to operate properly. A scram can be verified by diverse means such as: a) ' Indication of scram relay operation b) Scram valve position indication c) CRD scram accumulator low pressure
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,3 , d) Scram Discharge Volume high level alarms e) Indication of expected responses, i.e., makeup to the vessel, pressure decay, torus temperature rise, etc.
b
2 i l Variable Variable
- Number Name Identificztlon Adequate redundant indications powered 4 from reliable power sources and diverse indications assure that the operation can ascertain the reactivity status of the reactor. The existing instrumentation-utilized as Category 3 is considered !
sufficient to monitor this variable. j 05 BWR Thermocouples From industry reports, thermocouples
- mounted in BWR cores will not provide i adequate response for the intended purpose of monitoring core uncovery.
i Adequate and qualified reactor water i level instrumentation is utilized for .
; monitoring core uncovery (see Variable !
!' No. Al in Variable Summary Table). } Therefore, BWR thermocouples will not be
- implemented at the Station.
1 08 Drywell Sump Level Leakage rate to the drywell sumps are calculated every 4 hours when the sumps 3 i are required to be pumped. Leakage from i small leaks, which causes the sumps to r l fill before the 4 hours has elapsed, i cause an alarm on high sump level and the problem is investigated per the station i operating procedures. For large leaks,
- drywell conditions will be such that the j sumps will be isolated due to automatic i i primary containment isolation actuation.
i j Leakage rate and not actual sump level is i the important parameter. Operator actions and alarms are adequate for this i parameter for small leaks. Note that the
- i. actual amount pumped out of the sump can j be calculated from an existing flow recorder. The discharge rate (gym) multiplied by the time (minutes) will yield the amount of leakage (gallons).
4 The operator can then determine if the ! leakage is getting by subsequent pumping ! ! of the sump. This is a leading i , indication for determining loss of 4 coolant. Implementation as Category 3 is considered acceptable. i
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r O Variable Variable Number Name Identification 10 Primary Containment Redundancy for this parameter is Isolation Valve not required on each redundant Position isolation valve. Each primary containment isolation valve is equipped with one channel of position indication. Since each primary contain-ment penetration has two isolation valves in series proper isolation can be veri-fled by observing the position indication of the redundant valve if any PCIV positior. indication fails. Additionally, backup parameters of pressure, flow and temperature for the system can be used to verify valve closure. Isolation functions which require certain valve interlocks in order to change status may also be interpreted to obtain PCIV position status. For valves which are air or solenoid operated, the failure mode of the valve is such that it is in the safe direction (which is closed, in most cases) on loss of air or electrical power. Therefore, the correct valve position status for these types of valves can be ascertained. Motor operated isolation valve position switches are qualified as part of the valve operator which meets the require-ments of the valve for Category 1 service. The above designs satisfy the intent of the Regulatory Guide. 11 Radioactivity The monitoring of this variable, al-Concentration or though useful to assess the extent of Radiation Level radioactivity released to the primary in Circulating coolant, will not provide the operator Primary Coolant with information needed to prevent or mitigate a gross breach of fuel clad-ding. The operator's critical actions are to shut down the reactor and maintain l water level. The monitoring of this l variable will have no influence on these actions.
s Variable Variable Number Name Identification It is interpreted that the active coolant (or a sample thereof) circulating past the core is to be monitored. The Post Accident Sampling System (PASS) provides a representative sample which can be monitored once the PASS is activated. In the interim, between primary containment isolation and operation of the PASS, monitoring of the primary containment radiation and containment hydrogen will provide information on the status of the fuel cladding. Existing Category 3 instrumentation is considered adequate for monitoring fuel cladding status. 20 Primary Coolant The required range of -5 to 252 psig Pressure is being monitored by instruments which monitor over the range of -5 to 250 psig. The range of these instruments adequately meets the intent of this variable while providing a less awkward scale. 21 Containment and The control room displays read 0 to Drywell Hydrogen 10%, remote accessible displays read Concentration 0-10% or 0-20%. The monitored range extends well into the explosive mixture range for which there are no required actions by the operator based on the Emergency Operating Procedures. Either the remote 0-20% readings or the PASS may be used as backup. The system is considered adequate in fulfilling the intent of Reg. Guide 1.97 to detect the potential for a breach of the primary containment. 24 Radiation Exposure Radiation exposure rate in the secondary containment will be largely a function of radioactivity in the primary containment and in fluids flowing through the ECCS piping which will cause direct radiation shine on the area monitors. It is doubt-ful if the area monitors can provide an indication of a containment break or leakage under these conditions. The l
Variable Variable Number Name Identification chimney and reactor building vent radia-tion monitors (variable Cl3) provide positive evidence of a break or leak-age. Therefore, this item is being implemented as a Category 3 variable. It is felt that the range of the existing area radiation monitoring system is acceptable because: a) the range is adequate for normal operation and wide enough to use as a criteria for local evacuation b) under emergency conditions, entries past the access control point are controlled by established emergency plant procedures using portable monitors. 28 Suppression Chamber The suppression chamber spray is used Spray Flow to control the pressure and temperature in the suppression chamber. The LPCI system flow element is used for this flow indication. However the current instru-ments are not accurate enough to provide indication as low as required. The spray system.is turned on but not throttled. The piping is sized to limit the spray flow. Other devices are available to verify that spray flow exists: 1) valve position indication for this branch line;
- 2) pump running indication; 3) pump discharge pressure; 4) torus pressure; 5) torus temperature.
[ The above indications are considered* adequate to enable the operator to determine the existence of spray flow to the suppression chamber without the use of a dedicated device for this variable. 42 SLCS Flow There are no flow measuring devices for this variable. Besides pump discharge pressure indication in the main control room, the Standby Liquid Control Tank level is indicated and hi/ low level is alarmed, a flow light indicates when flow
Variable Variable Number Name Identification exists, squib valve continuity is indicated, and neutron flux level and period are indicated at the same location. These indications provide adequate monitoring of system operation. The use of the above indications is considered to be a valid alternative to monitoring SLCS flow indication. 47 Cooling Water Flow The Component Cooling Service Water to ESP System (CCSW) flow is adequately covered by Components qualified existing instruments. The Diesel Generator Cooling Water (which services pump room coolers and the diesel generators) flow is not monitored, however, pitot tube test taps are available. The temperature of ESP components / equipment are monitored individually via indicators or alarms and the DG pumps are accessible to monitor discharge pressure. Based on the above, sufficient diverse instrument is available to determine the condition of the DGCW system. The above arrangements are considered to meet the intent of this R.G. 1.97 variable. 49 Emergency Damper The Diesel Generator room dampers are Position not provided with position switches. The Diesel Generator rooms have high tempera-ture alarms which are an indication of the overall Diesel Generator HVAC performance. All other areas where the other emergency dampers are located are accessible to determine system status if system operation is in doubt. The Reactor Building isolation dam'per control panel is in a mild area. The emergency dampers for the Reactor Build-ing fail closed on loss of power and are interlocked to the Standby Gas Treatment System. The Main Control Room (MCR) damper position indications are available just outside the MCR in a mild environment and can be readily checked by an auxiliary
~
Variable Variable Number Name Identification operator, if need be. Fan indication and trouble alarms also provide backup system status information since the MCR fans are interlocked with their isolation dampers. Adequate indication is available to the operator to determine system status without the need to provide additional instruments to meet the intent of this R.G. 1.97 parameter. 61 Radiation Exposure It is not probable that a few fixed station area monitors could provide sufficiently reliable information to be of use in detecting releases from unmonitored containment release points. Environs radiation exposure is covered under the GSEP procedures. Therefore this variable will not be implemented. 64 Plant and Environs The instrumentation required for this Radioactivity variable has been found to be too (Portable delicate for use in the field. Instrumentation) Therefore, samples will be taken to an appropriate location for analysis. 76 Containment Air The existing indicating range of 0 to Oxygen Content 10% in the control room and 0 to 20% at an accessible remote panel provide adequate though not complete, coverage of this Reg. Guide requirement. The range is considered adequate since monitoring is provided well into the explosive mixture range. 4
CONCLUSIONS Section VI Overall, Quad Cities Station meets the intent of Regulatory Guide 1.97. Some modifications are required to bring the Quad Cities Station in compliance with the Reg. Guide requirements for Type A variables. These are the most important variables for establish-ing the required operator action, and therefore provide the most valuable information to the operator of post-accident condit-lons. The evaluation of Quad Cities for Regulatory Guide 1.97 has taken into account fire protection policies, human factors evaluations, as well as design modifications planned and those being implemented. Existing instrumentation, meeting the intent of the Reg. Guide, adheres to the original station design for seismic and quality assurance requirements and to the Response to IE Bulletin 79-01B for environmental qualification. Any new instrumentation required to fulfill the Reg. Guide requirements will take into account the most recent regulatory guidelines and follow the Commonwealth Edison Company Quality Assurance Program. I 4 l L
o - Appendix A References A. System piping and instrumentation diagrams B. Instrument loop schematic diagrams C. Control schematic diagrams D. Control panel wiring diagrams E. Control panel front elevation drawings F. Updated Final Safety Analysis Report G. Emergency Operating Procedures H. Instrument Data Sheets I. System descriptions per the Equipment Manual series GEK 786 J. Vendor instruction manuals K. Response to IE Bulletin 79-01B L. Environmental and seismic qualification reports, as available M. SPDS Input Signal List N. Updated fire hazards analysis O. Plant technical specifications P. BWROG Position on NRG Regulatory Guide 1.97, Revision 2 Q. BWROG Emergency Procedures Guidelines R. NRC Regulatory Guide 1.97 Revision 2 " Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident"' S. NRC Regulatory Guide 1.97 Revision 3 " Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident" T. Modification Index (for) Dresden and Quad Cities Station dated 4-16-85 U. General Electric Design Specification 22A25dl, Revision 0, Separation Requirements for Reactor Safety and Engineered Safeguards System.
- APPENDIX B
- - TABLE 1: BWR VARIABLES (NRC Regulatory Guicle 1.97, Revision 2) TYPE A Variabico those sariables to be monitored that provide the primary information required to permit the control soom operater to take specific manuaDy controDed actions for which no automatic controlls provided and that are required for safety systems to accomplish their safety tunctions for design basis accident events. Primary information is informa-tion that ss essential for the direct accomphshment of the specified safety functions; it do:s not include those variables that are associated with contingency actions that may also be identified in written procedures. A variable included as Type A does not preclude it from being included as Type D, C. D, or E or vice versa. Category (see Retplatory Variable Range Position 1.31 Purpose Plant specific Plant specific j lnformation required for operator action . TYPC B Variablet them variables that provideinformation to indicate whethcr plant safety functions are bems a Plant nfcty functions sre (1) reactivity control, (2) core cooling, (3) maintaining reactor coolant system internty, mamiaining contamment integrity (meluding radioactive effluent control). Variables are bsted with designated range category for design and quahfication requtrements. Key variables are indicated by design and quahfication Category Reactivity Control Neutron Flus 10% to 100~ full power i Function detection; accomplishment (Skhi, AFRht) of mitigation Control Rod Position fruu in or not fullin 3 Vstification RCS Solub!c Doron Concen- 0 to 1000 rpm tration (Sample) 3 Verification Core Cooling Coolant lavelin Reactor Bottom of core support plate to i Function detection; accomplishrnent lesser of top of vesstl or center. of mitigation;long term surselll alice line of rnain steam line. BWR Core Thermocouples: 200*F to 2300*l2 8 1 'Io provide diserse indication of water level Maintaining Reector Coolant Systern integrity RCS Pressure' 15 psia to 1500 psig i Function detection; accomphshment of mitigation;verificajion Drywell Pressure' 0 to design pressure8 (psig) i Function detection; accomplishment of mitigation;venfication I four thermoccurtes ret quadrant. A rnonimum of one inessurement ter quadrant is tequired for operation. I Where e tenatite te i.ited $3t psee stan one potreme,lhe instrumentetson requttements may t's intestated md mly one entse strese. Dettsn rtetaure is that tatue tortespondins to A$ktr tode valuu that are otiteined at ce below tode allowst,le values for m 4 e4
TABLE I (Continusati e , Categosy (see Veelable Regulatory Ranoe Position 1.31 Purpose TYPE B (Continued) Drywell Sump level 3 Bottom to top 1 Function detection; accompinhment
.Of mitigation; verification Maintaining Containment integrity Primary Containment Pressure 2 10 psia to design pressure 3 i Function detection; accornplishment of mitigation; verification Primary Containment isola-Closed-not closed i tion Valve Po. ition (exclud- Accomplishment of isolation ing chcck valves) ,
TYPE C Variables: those vari 4Het that preside information toindicate the potentialfor being t reac the barners to fission product releases. The barriers are (il fuel cladding. (2) primary coolant pre tainment. Fuel Cladding Radioactivity Concentration or 1/2 Tech Spec limit to 100 times 1 Detection of breach Radiation levelin Circulating Tech Sree famit. R/hr Primary Coolant Anal) sit of Primary Coolant 10 WCt/gm to 10 Ci/sm or (Gamma Spectrum) 3* Detail analysis; secomplishment of
- TID 14E44 source term in initigation; verification; long term coolant volume suncillance BWR Core Thermocouples3 200*F to 2J00*F 8 1 To monitor core cooling Reactor Coolant Pressure Boundary RCS Pressure 3 15 rsta to 1500 psig 8 1 Detection of potential for or actual breach; accomplishment of mitiga-tion;long term surveillance Primary Containment Area Radiation 3 I R/hr to 10' R/itt 3'J Detection of breach; verification l
samples.Samthatf or gates, of rnoniteront the ersteria ofor ANSIradioactne til).I shouldhausds anJ t e oppned. Itatf haveda. ates should prosasions be reeftirmed shouts be made in atotmenne samrlm het sones. Meludet and samrting hnet should be designed to minimaat slalecut et deposition. Iof sale and convenient os ! e. $hieldene te, mai9tain taJiethen deste A L Alt A. * ' D. hample euntainees usth containetumthng port connettet etsmpatthtlity,
- e. Carstnhts or samphng unaat rtimary spstem pressure and nedettve pressures.
- d. llendung and tesasport earablett. and *
- e. Preartengement for analysis end snierpretetson.
I fhe meumurn value may be tensed upward to salufy A7% S tequirements. 6 Minimurn of two monitors et midely eerstated loeshons. I Detectors should eeseend to estems tadiation r*.otons usthin sav eneter tante from (0 kev to 3 MeV w of $30 range. rescent at any spesires photo,s energp frorn 01 MeV to a Me% chetalt systeen astussey seiould te
m . TABLE 1 (Continued)
. Category (see i Regutetory
- Varialite Range Position 1.3) fuepose TYPE C (Continued) l Reactor Coolant Pressure .
Soundary (Continued)
'Drywcu Drain Sumps hvel' Bottom to top I Detection of breach; accomplishment (Identified and Unidentified of mitigation;verificataon;long term Leakage) surveillance surpression Pool Water uset Betsom of ECCS suction ime i Detection of breach; accomplishment to $ ft abose normal water of mitigation;terification;long term level surveiUance Drywell Pressure? O to design pressure 3 (psig) I l I Detection of breach; verification Containment RCS Pressurci 8 i
l$ psia to 1500 psig 1 I)etection of potential for breach; accomplishment of mitigation l Pnmary conta nrnent l'ressure' 10 psia pressure to 3 times desir.n I Detection of potential for or actual pressure3 for concrete; 4 times breach; accomphshment of mitiga.
, design pressure for steel tion Containment and Dr)well O to 30~< (capahbty of operating I Detection of potential for breach; il> drogen Concentration , from 12 rsia to design pressure3 ) accomphshment of mitigation l
Containment and Drywc!I O to 103 (capabihty of operating I Detection of potential for breach; ! Onygen Concentration (for from 12 rsia to desir,n preuure3 ) accomphthment of mitigation inerled containment riants) Containment l~ffluent2 Radio. 10 pCi/cc to 10 2 ggjf,, 3 a.e Detection of actual breach; accom- , activity . Nnble Cases (from . pbshrnent of mitigation; verifica. l identified release points includ- tion i int Standby Gas Treatment l System Vent) Radiation Exposure Rate ( n. t 10 R/hr to 10' P./hr 2' Indication of breach side buildtngs or areas, e p.,
- auxiliary buildmg, fuel hand. '
I ng buildinr, steondary con. tainment, which are in direct contact with rrimary con. . tainment where renetrations l and hatches are located) O ttomiens shtmlJ Pe msJe in monient att identitieJ rathwsts far eeteste or raseous tediasetive eneterials to the environs 64 tonfoernance Mvh General ths en t'esierinn v4. Monienrece or mJ.ieJua6 ernuent streams an onis teauued where suth streams are retessed dweetts enen the environment. It inn ne more streams are comt'ined reint to telent trom a common discharge point. monitoring or the com%ned ofreets is consideied to eneet al.e intent or that teguistory fueJe prossJed such monotonna has a tense adequate to measure worst esse selettes.
' 'Manienn shouti e
- terable of detectent end meetur6nt esJenettive pseenus efrtuent eencentret6nns with eemrositions tenging trem fresh equdititium anHe g e to.+ . #, r'nduei emsfores to l&daveelJ rmatures, niin e.verait is stem securacies Mthen e f attot or 2.1 tnuent toneentre-
' tennt man be earrened er terms ni ne 1)) tavivalents ne en letmo nf ans not te sat nutledels) l' et nha enreeled that a sentle innassarine deme hile hate tufrecient etere ettenmragt the entire 84neP riv'iJ'd in this le841alDr) f'JeJe end Itist multgle te,mponents ce erstems Mil tie needed,l. testing equirmia t oss t'e wwd to monstne ont puetens of the stated range within the equipment design teleng,
TAlsLE 1 (Cont:n sed) Category heo g
. Varialde' Hegulatory .
Ranrn Position 1.31 Purpose TYPE C (Continued) Con *ainment l Continued) ! Fiflucr.: KaJioactmty' floble 4 10 UQ/cc to 108 tri/cc l 2' Indication of breach ' Cases (from bui!Jmt.s as indicated aboie) , l TYPE D VariatJes: those variables that provi.le inform 3 tion to bdicate the operation ofind systerns important to safety.1hese uriables ate to http the operator make 3;irropriate decisio tems important to safel) in rnitirating the consequences of an accident. Condensate and Feedwater System Main Feedwater Flow 0 to 110"; design flow 3 Detection of operation; analysis of cooling Condenute Storate Tank Lesel bottom to top ' 3 Indi:ation of asallable water for cooling Primary Containment Related Systems Suppression Chamt et $ pray Flow 0 to 110'*< desitn flow'O 2 To snonitor operation Dr> w ell l'ressure8 12 piia to 3 psig 2 To monitor operation
, O to 110', design pressure 3 Suppicssion l'ool Water Lesel Top cf vent to top of weit well 2 To monitor operation Suppresuon Pool Water Temperature 30*f to 230'r 2 To monitor operation Dr)well Atmosrhete 40*F to 440*F lemperature 2 To mor.itor operation Drywell Spray Flow 0 to i10.. design flow 2 To mor.itor o, cration Main steam system Ma;n steam!!ne Isolation 0 to 15"of water 2 Yahes' Leal.are Control 0 to 5 psid To provide indication of pressate SysternPressure
- boundary maintenance .
Primar) 53 stem Saft y Rch:f , Closed-not closed or 0 to 50 psig 2 Valve Positions, fr.cludag Al)S Detection of accider.t: bour.dary er ilow Throufh or Prenuse
- internly indication in Vahe Lines I*Desosn now se he mes6mem now est,vpated sn normd eteressen.
4
TAI 3LL 1 (Continued) . Category (sce Varishte Her;ulatory H. nat Position 1.3) Purpose TYPE D (Continued) Safety Systems Isolation Condenter 53 s:cm Top to tsottom 2 - To monitor operation ShcIl $ide Water Inci
- lsolation Condenser System Open or closed Valve Position 2 To anonitor status RCIC Flow 0 to i103 design Daw'8 2 To snonitor operatien llPCI l'iow 0 to i107. des:t.n now'0 2 To monitor operation Core Spray System finw 0 to 1107. design now'0 2 To rnonitor oper:tien LPCI System flow 0 to 1107, design flow'O 2 To monitor operation S LCS Ilow 0 to 110";, design 0o4 2 To monitor operation SLCS Storage lant Level Dettom to top 2
- To monitor operation flesidual Heat Hemoval (HHH)
Systems RilR $> stem flaw 0 to l107 design Gow 'O 2 To monitor operation RilR llest Exchancer Outlet 32*F to 350*F Temperature - 2 .To monitor operation Cooling Water System Coobnr Water Ternrerature to 32*f to 200*r LST System Components 2 To monitor operation Cooling Water Flow to I:S!? O to i107, design Osw'O 53 stem Components 2 To monitor operation Hadnaste Systems liith RadiosefFi:y Liqui:f Tank Top r3 bottorn Level 3 To monitor operation Ventilatioi Sys'tems I:merrency Ventilation ()amper Open closed status Position 2 To monitor operation Power Supplies Status of Standty I'ower and Other 1.nergy Sources linportant Ve>trate s, eurte r.ts, pentare s 2 To monitor system status to Saftly (hydraube, pneunsatic)
'Eletus mdashon of oin 5:enJby Power e e tuses o c buses Hve t r er ou'rve buiet, and rneumshe sur side
I 1 AllLt.1 (Contmoed)
- a
,
- scliot matesuls and continually assessing such releases 1Yl'I' l' Wriabics: tho:e ,
Category (see l Variable fleculatory Rene Position 1.3) _ Purpose Containtnent Hartistion l'rimary Containment Area Radiation . lkrA Rarite' I R/hr to 10' R/hr l Detection of si;;nificant releases; release assessment;long term
- survedlance; erncrgency r!an actuation Reactor Duddint.or Secondary
- i 80 R/hr to 1'0
- R/hr for hlark 1 2' D,etection of si tnificant releases, Containtnent Area Radiation 8 and il containments
! - release assessment;long term 1 II/hr to 10' II/hr for klark !!! l ' sunedlance { containment Area itadiation . i Radiation Esposure P.atet 10 R/hr to 10* R/t.r 2' (inside buildsnes or areas where Detectien of sirnificant rcleases. access is required to sersfce release avessment;lorig te:rn equirtuent important to safety) suneiUanec Altborne Hachoactive Materials Released from Plant Noble Cases and Vent Flow Rate
- Drywet! Purre, Standby Gas 10 Wilce to 10' Wilec 2' Detection of significant releases; 1reatment System Pur;e 0 to l10'. vent design flow
(for f. lark I and 11 plants) release assesstnent (Not needed if etnuent discharges and Secondary Contain- through common plant sent) ment Putre (for Af ark 111 plants) ,
- Secondary Containment 10 6 Ki/cc to 104 Wilec 2' Purre IIor Plark I,11, and 0 to 110 *: sent desitn nowl0 Detection of sir.nificant releases.
111 plants) release assessment (Not needed if efnuent dis:harges throut.h common plant vent) Secondary Containment 10 pCi/cc to 10" Wilce (reactor shield building, 2' Detection of si nificant t re! cases; O to 1807. vent design flowl ' annulus,if in desitn) release assessment (Not needed if ef09:nt dischartes throur,h cornmon plant vent) l
- AusDiary Duilding 10 pct /cc to 103UCi/cc 2' (incluJing any buddsag 0 to 1107, vent des!;n flow 80 Detection of significant releases; containing pnmary system release assessment; tong term (Not needed if effluent dis:hartes surveillance rases, c.g., waste gas decay thrcur.h common rl ant sent) tant ) '
+
Cominon Plant Vent or Afulti- 10 pCi/ee to 103 Wilec rurpose Vent Dah:rring 2' Detection of significant releases; 0 to 110 *. Sent des:gn Scw Any of Above Releases (if release assessenent long term - drywell or SGTS purre is surveillance includedi 10** pCi/cc to 108 pCi/cc 4 6
r n 1 AIJLL 1 (Coittinued) e Category (ste Variable llegulatory flantre Position 1.3) Purpose 1Yr0 C (Continued) MeteoroloyfIS - Wind Direction 0 to Jf,0* (25' accura:y with a
- 3 Reicase assessment ocilection of 15*). Starth4g speed 0.45 rnrs (1.0 mph). Damping ratio between 0.4 and 0.6, distance con-stant L2 metets Wind Speed 0 to 30 mrs (67 mrh) :0.22 rnrs 3 Release anessment (0.5 mrh) accuracy for sind speeds less than 11 rars (25 mrh) with a starting threshold ofless than
- 0.45 mrs (1.0 mrh)
Estimation of Atmos - Dased o*: sertical temperatute 3 Release assess:nent rhtlic Sta t.ihty difictence from rntaary system, 5*C to 10*C ( 9'F to IE*F) ar.d 20.15'C accuracy per 50 meter intervals (10.3*F accuracy rer 164 foot mterials)or anatorous tante for alternative stabbty estimates Accidcnt Simpling Caps-bility (Ant. lysis Capabil-ity On Site) ,
- Pnmary Coolant and Sump Grab Sample 8 3 Release assessment; verification;
- analy sts Gross Activity 10 pCs/ml to 10 Ci/ml
- Gamma 5pectrum (Isotopic Ani!) sis)
- Doron Content 0 to 1000 rpm
- Chloride Content 0 to 20 rpm
- Desobed ifydrogen er 0 to 2000 cc(STP)/kg '
Total Cas'"
- Dissolved OxygenI8 0 to 20 rpm e
til I to 13 Containm:nt Ah Grab Sampla
, 3* Reicase assessment; verifi:ation,
- Hydroren Content analysis 0 to 10~e O to 30~ for inerted containments
- Ox>ren Content O to 30~ '
- Gamma $rectrurn (Isotopt: analysts)
II Progeoms in Surgoel of bu6 legs Iv.er hones."G.4idance nn metemelork., enewarementa is beet developed i N which should te *1thari 24 howes.1he tWe foi tsuna and anstyreg samples should be 3 hours os less from the time 8 l>vud(ng sump bautJ aarnries.An (notst'ed estebu.tv ehoutJ be provided foe obtaining conteinment eumr. ECCS rum Aprises orJr to g,rimary ecclent. col to samp. 6
E
-o
- TAllt E 1 (Continued) -
' Category (tse Regulatory Variable Range Position 1.3) Purpose TYPE E (Continuad)
Airlsorne flathnactive Mstctia!s
- Released f rom fiant (Continued)
Noble Cases and Vent I' low Rate (Continued) AU Other identified Release 104 (Ci/ec to 10: gggfe, 9 2 Detection of significant release
. l'oints O to 110~, vent deurn flow 30 relcase asussment;long. term (Not needed if effluent discharges surveillance throut.h other n onttored plant -
vents) Particulates and lla!ncens e AU Identified Plant Release 10'3 tCi/ec to 102 pc fee 3: 2 Detection of significant releaset Points. Sainphng with Onsite O to llCG sent design flow 30 release assessment;long tert, Analysis Capahhty surveillance Ensitons Radiation end Rrdio-activity Radiation Exposure Mete: Range, location and quahfica- Verify significant releases and lx (continuous indi:ation at tion criteria to be developed to magnitudes fined locations) - satisfy NUREG 0654, Section , ll.li.5b and 6b requirements for ernergency radiological inonitors Airborne P.adiohslotens and 10** pCs/cc to 10'8 tC /cc 13 3 Rc! case assessment; anah sis Particulates (rcittabic sararhng with onsite analyr:$ capahhty) I'lant and Environs Radiation 10'3 R/hr to 10' R/hr, photons 3 Rc! case assessment, ana!ysis (portab!c instrurnentatmn) 10*3 rads'hr to 10" rads /hr, beta 3 34 radiations and low energy pt.ctons Plant and Enurons Radio- Multichannel gamtr.2 tay 3 Release assessment. analys!s activity (portable snstru- spectrumeter inentatio,n)
'I tiy rinilte1o 14erovide infusmition hi.ratory terarding t-essweetnenu of releste s rr etesoffor radiosttive hatetent taJ.ur slotens andanJ rartiewtates. Continuous r tticulates.1he collection denitn envelote of representative for thatlJant, samrles t anJi.nr. fc'.Ne ar.J sea >t estroses th!J asswme 30 t':r.utes of titerrateJ sa .rtia nme at teralet steum flaw, an sierste concer trateon of so' J.etes e>f ra; ai .e.
in gestr us or taror f;rm, an a*erare e..ncenitation of sol td.i/ct of pencviate saJsoiudines and gatuculates other trian taJ.cioJo es, a*.e averate gainma photon enetts of o.s MeV ret daintegration.
' for esumating refeate f ates of tsJ40setive materiets released dwrung an acciJetet.
"To enonitor esJintin end sitt.nrne radioactivity enneentrations in many stese throurhout the facdity and the site enissons mtete I
$m('fatheallG snittl* alal6Liest) rional@rs eat'tble of Cotefing both nottflat and attederalletels.
[ . 4 e APPENDIX C ABBREVI ATION S ADS automatic depressuritation system APRM average-pover range c.onitor ATUS anticipated transients without scram BWR boiling unter reactor BWROG Boiling Water Reactor Ovners Group . CRD control rod drive I CS core spray CST condensate storaye tank ECCS cmcrgency core cooling systen EDG cnergency diesel generator EPG Emergency Procedure Guidelines EPRI Electric Peuer Research Institute ESP engineered safety featurc IIPCI high-pressure coolant injection IE! intermediate-range monitor LOCA lors of coolant accident LPCI lou-pressure coolant injection LPCS Iou-pressure core s' pray LPD: Iccal power range r.cnitor NMS neutron nonitoring system - NSAC Nuclear Safety Analysir Center NSSS nuclear steam supply system OG Ovners Group PASS post-accident sampling systen
- PUR pressurized uater reactor .
RCIC reactor core isolation cooling RCS reactivity control systen RitR recidual heat removal RG Regulatory Cuide i . 4
'l l'l'V reactor pressure vessel M.'CU reactor water cleanup unit S!'CT standby ~ gas treatnent suppression cha:aber spray
- i. SCS SGTS standby gas treattnent sysL<n SLCS standby liquid control systera
. S104 source range raonitor Sl'V safety relief valve O
f e 6 0 O e 0 0 0 l O L
[ a d'lh Appendix D ,
. i Abbreviations Used in the Variable Summary Table l N/A Not applicable l N/R Not required 90X-3 X refers to both units 90Y(Z)-7 Y refers to one unit Z refers to the other unit Cntl Term Control Terminal SWGR- Switchgear CUB Cubicle Sect Section MCC Motor Control Center MCR Main Control Room .4
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