ML20236P920

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Forwards Radioactive Liquid Effluent Sys Description Including P&Id,Design Criteria,Instrumentation & Control Measures to Support Evaluation of Proposed Amend 155
ML20236P920
Person / Time
Site: Rancho Seco
Issue date: 11/12/1987
From: Andognini G
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Miraglia F
Office of Nuclear Reactor Regulation
References
GCA-87-763, TAC-64735, NUDOCS 8711190086
Download: ML20236P920 (50)


Text

{{#Wiki_filter:. . . . . . . k g%dSACRAMENTO SMUDMUNICIPAL UTluTY DISTRICT Cl P, O. Box 15830, Sacramento CA'958521830, (916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA NOV 121987 GCA 87-763 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr. Associate Director for Projects j Philips Bldg.  ! 7920 Norfolk Avenue l i Bethesda, MD 20014 DOCKET 50-312 l RANCHO SECO NUCLEAR GENERATING STATION l LICENSE NO. DPR-54 RADI0 ACTIVE LIQUID EFFLUENT SYSTEMS DESCRIPTION

Dear Mr. Miraglia:

The District hereby submits the subject description for your review to support the evaluation of Proposed Amendment No.155. The description' package l includes piping and instrumentation diagrams (P& ids), design criteria, instrumentation, and control measures. 1 The District has significantly improved the capability' of the radioactive. liquid effluent systems. The District's objective is to operate Rancho Seco' within the 10 CFR 50, Appendix I ALARA guidelines. The following changes in hardware and operation significantly reduce offsite doses resulting from radioactive liquid effluents: Disposal of condensate polishing demineralized resins to reduce the- I radiological effluent source term. i l ' Installation of demineralization processing for secondary waste water to reduce effluent activity.

               -     Installation of effluent strainer processing for secondary waste l

water to reduce effluent activity.  ;

               -     Installation of a 100,000 gallon Regenerant' Holdup Tank (RHUT). to improve segregation of radioactive and non-radioactive effluents and                        !

thereby improve radioactivity detectibility, and increase the total waste water capacity.

               -     Installation of permanent piping from the RHUTs back to the primary side radioactive liquid treatment system to provide additional l

processing capability. b Y .yg RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road,' Herald, CA 95638 9799;(209) 333 2935 {-

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                                                                                                                                                     'GCA.87-763                                                    ;

Frank J. Miraglia, Jr. NOV 121987- l e-Installation of control devi$es to assure itHUTs A and B cannot be 8,h discharged directly offsite, thus providing improved contre) over 4 -5 radioactive effluent releases. > j

                         -       Increase in' plant effluent dilution flow to a minimum 5000 gpm to reduce firal effluent concentrations.

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  - /, ,..                       Installation of additional radiation monitor $ng capability to provide.                                                                                                            j g

increased monitoring and control over liquid releases 4 i 9 In addition, the District has recently initiated a purchase of more sensitive sample analysis equi .s Detectibility (LLDs)pment within atoreasonable achjeve the required Lower Limits of counting period. ,

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                                                                                                                                                 <,                                                    a         v l                    The hardware evaluation demonstrating the. plant's capabilities for limiting '                                                                                                     f f ..i l                    radioactive liquid releases will be submitted by Novrgber                                                                                                                   ,        Nf!

District will discuss present results of thistevalue, ion /30,' 1987. )The s f ' November 13, 1987 meetingyith NRC staff. t at.the(1' 4 l

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3 Please contact me if you hMe any questions. Memtwrs of your{ stvff with . W, i .e ., j l questions requiring additional information or clar9fication41ay antact' f < j  ! l Mr. David Conoton at (209) 333-2935, extension 4915 ,,s > LJ  ;

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Vi Sincerely, ,, - \ f i jf2' , 7 S l4-

                     . Car. Ando          ni                         ;                                                                                                               t              i/g Chief Execut ve Officer,                         '

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i Attachment i ycr, Fi s- a  % t y'i _ 4 s  ;

                                                                                                                       < .]' h cc:    G. Kalman, NRC, Bethesda                 w/atch(noP&                             ids)/(-                                                                                                 i A. D' Angelo, NRC, Rancho Seco . w/atch (no P&'10s)                                                    '

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                           >1. B. Martin, NRC, Region V w/atch (no P& ids)                                                                             q           (

G. Knighton, NRC, Eie?.besda w/o atch , C. Willis, NRC, Bethes,Ge w/atch ' s 1 s s_, , I G. Yuhas, NRC, Walnut j Creek w/atch

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     ,                                              RADIOACTIVE LIOUID EFFLUENT SYSTEM DESCRIPTION I. Radioactive Liquid Effluent Program risai                                ic. 0 8si a:t w n s ~i;r n + w i n m i , b i l a i9 a th: m" III. Historical Perspective IV. System Design l

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I. RADIOACTIVE LIOUID EFFLUENT PROGRAM-The primary objective of the program is to ensure. dose to the . genera 1'public.is maintained at' levels:whicn are As Low As 'l Reasonably Achievable-(ALARA).-lThe plant design'is adequate to-stay within the 10CFR50,. Appendix I numerical guides'.for design 1 objectives.under. normal. conditions. Rancho Seco was not and.is . 1 not designed to stay within' Appendix I-for all possible l operating events. Rancho Seco management's objective is'to operate-the plant within.the Appendix I ALARA guidelines. Appropriate actions will be taken and the NRC kept informed when dose projections indicate the Appendix I guidelines ~may be exceeded. These appr'opriate actions may include temporary I modifications, permanent modifications, and/or plant shutdown. A. Administrative Procedure The Offsite Dose Calculation Manual (ODCM) and'its implementing . j procedures provide methods for evaluating compliance with L 10CFR20, 10CFR50 Appendix I, and the Rancho Seco Technical  ; Specifications. The ODCM, its implementing procedures, and l related operating procedures provide the following i administrative controls on radioactive liquid effluent' releases: 1

1. Sampling from RHUTs and retention: basins,-prior to release j
2. Analysis of samples, prior to release H
3. Release Permit to authorize release
4. Post' Release Calculations and Land Use Census .l
                    -(Environmental Protection Analysis)
                                                                                                            .i Page 2 of 31' 1

I. RADI0 ACTIVE LIOUID EFFLUEWT PROGRAF 4 (Continued)

            'B.      Doeratina Fffzydpres and Trainina.           <

Operating procedures are'important for efficient and error free 4 operation of the equipment. 'They apply l precess,designifeatures, thereby minimizing' malfunctions and misoperation. For: example, overflows are. controlled by proper.. level monitoring, timely. processing..and automatic functions. These procedures are being finalized now as the construction and the testing are nearing: ] J conclusion.: Information and knowledge gained ~during'the.startup testing of the system equipment will. be incorporated into th's final operating procedures'now being prepared by the plant' staff. '

                                                                                                    ,j Appropriate operator training, including formal classroom training, wi:1 be provided by the. Training Department, I

coordinated with the system turnover to Nuclear Operations. C. P_toces s 1 Considerable investigation was conducted in the selection and design of the process operations'necessary to-deal with the type of lig! rids expected. The process objectives are: d

1. Reduction of discharged radioactivity. l
2. Provision for representative sampling, i
3. Flexibility to accommodate a varicty of inputs.
4. Process reliability.

q l Page 3 of 31 .

I. RADI0 ACTIVE LIOUID EFFLUENT PROGRAM (Continued) D. Hardware Proper selection, sizing. installation and testing of.the.

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various pieces of hardware. provide for efficient, flexible.:

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operation'and. ease'of maintenance. Process' instrumentation'and controls are provided for monitoring.and assuring proper performance of the system. Interlocks are provided.to prevent misoperation of the system. < l 1

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                                                 'Page 4 of 31 o

t-i II. DEFINITION OF "RADI0 ACTIVE LIOUID' EFFLUENT SYSTEM" During normal plant operations, radiochemically contaminated water l from primary side leaks is collected and processed through the liquid - Radwaste System and recycled into the Reactor Coolant Makeup System or otherwise reused in the controlled areas of the plant. Low level radioactive liquids that leak from the secondary side of the plant require processing and disposal to maintain the plant water balance. j i Secondary side leaks are collected and released from the plant in a- l controlled manner. Leakage of secondary system water (which may potentially contain radioactivity) is routed to Regenerant Holdup Tanks (RHUTs) A and B j and processed prior to being released. The Condensate Polishing i Demineralizers are operated in the resin throwaway mode during periods of secondary side contamination to reduce quantities of radiochemically contaminated water generated from resin regeneration. The Radioactive Liquid Effluent System processes the secondary side  : leakage and drain effluents. It is a part of the overall waste water. processing and disposal scheme'(which includes cooling tower blowdown) and consists of a number of large holdup tanks, demineralization and filtration skids, representative sampling, dilution and chemical treatment capabilities, retention basins and pH, conductivity, radioactivity, and temperature and flow measurement instrumentation. The Radioactive Liquid Effluent System is not described as a single system in the Updated Safety Analysis Report-(USAR) nor does it constitute the formation of a new system. A simplified process flow diagram is shown in Figure 1. Page 5'of 31

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II. DEFINITION OF " RADIOACTIVE LIOUID EFFLUENT SYSTEM" (Continued)- {u The Radioactive Liquid' Effluent; System is designed to. segregate :f { potentially radiochemically contaminated water from that .J containing chemical contamination only. Segregation of water l enhances the ability of the analytical equipment to detect any ] radioactivity by increasing the concentration in RHUTs A and B by not prediluting their contents with clean wastes. This j increased concentration improves the demineralization efficiency l for removing both radioactive and nonradioactive, species in the The entire system operates in a batch mode for

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process streams. better control of liquid releases. A list of,all sources of I water to RHUTs A, B and C are given below: A. Condenser Pit Sumo (Potentially Radioactive 1v Contaminated). 1 Sources of input to RHUTs A and B are listed below and in the l Section II.B. Additionally, Auxiliary Boiler Area Sump Pump P-306 pumps directly into RHUTs A and B.

1. Condenser Pit Sump Pumps P-964 A and B Seal Hater.
2. Turbine Deck Drains '

l 3. Turbine Building Ground Floor Drains

4. Condenser Water Box Drains
5. Condenser Pit Drains
6. Chemical Feed Area Drains
7. Diesel Generator Room Floor Drains Page 6 of.31' I

II. DEFINITION OF "RADI0 ACTIVE LIOUID EFFLUENT SYSTEM" (Continued) B. Condensate Polishing Demineralized Area Sumo (Potentially Radioactive 1v Contaminated)

1. Steam Generator Drain Booster Pumps P-309 A and B
2. Auxiliary Building Cold Laboratory Sink Drains
3. Drains from chemical laboratory and sample station room 327 I and T&R Building.
4. Turbine Plant Sampling System Sump Pump P-70B
5. Acid Injection Pumps P-75B A, B, and C leakage I
6. Caustic Injection Pumps P-756 A, B, and C leakage
7. Condensate Polishing Demineralized Regeneration )

Equipment and Area Floor Drains

8. Condensate Polishing Demineralized equipment and area floor drains
9. Silica Analyzer Catch Basin j
10. Floor and Equipment Drains from West Nuclear Service )

Battery Rooms

11. Floor Drains from Station Battery Room #218
12. Condenser Pit Sump Pumps P-964 A and B (See II.A. above)

C. Makeuo Demineralized Sumo (Extremelv Remote Contamination Potentia]l* The following sources of water flow into RHUT C.

1. Makeup Demineralized Regeneration Haste via Catch Basins
2. Conductivity Meter Drains l Each catch basin collecting Makeup Demineralized Regenerant Haste and equipment drains has a berm around it to prevent draining of potentially contaminated water. Potential for contamination exists in remote case of Turbine Building ground floor flooding from contaminated sources exceeding catch basin berm heights.

Page 7 of.31

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III. HISTORICAL PERSPECTIVE Prior to 1984, secondary side' leaks were directed into'one of " two sumps:. , A. Polishing Demineralized and Hakeup-Demineralized Area Sump. (now called Condensate Polishing Demineralized Area Sump). B. Condenser Pit Sump l i The Polishing Demineralized and Makeup Demineralized Area Sump. l l l received water from'the sources. listed in Sections II.A.-and 1 i II.C. It also received the Condensate Polishin'g Demineralized l l and Makeup Demineralized regenerant waste' and the area drains. l l The sources to Condenser Pit Sump were essentially the same as in Section II.B. The discharge from this sump was pumped to a

distribution box, then to the plant effluent oily water-l l separator and on to a retention basin. 'The alternate path for the Condenser Pit Sump was'to the Polishing Demineralized and .!

Makeup Demineralized Area Sump when radioactivity was detected. The normal flow path for the Polishing Demineralized and Makeup-Demineralized Area Sump water was to RHUT A or B (RHUT C did not. exist) for chemical treatment and sampling. The RHUTs were pumped to one of the two retention basins for further sampling, chemical treatment and subsequent release. Radiation monitor R-15020 was used to monitor discharges from the'RHUTs to the retention basins. I Page 8 of 31 1 i' La.

III. HISTORICAL PERSPECTIVE (Continued) l A major change in the plant operation to reduce liquid effluent doses was instituted in late 1984 following detection of primary  ; to secondary leakage. Previous experience with controlling liquid effluents during periods of primary to secondary leakage from 1981 to 1983 led to this change in secondary :;ystem operating philosophy. The Condensate Polishing Demineralized operation was switched froin a backwash / regeneration mode of' operation to a resin throw-away mode to minimize the radioactivity in the wastewater. 1 i A number of plant hardware additions to enhance liquid effluent treatment have been installed since plant shutdown in December 1985. These new additions are highlighted on the attached Secondary Side Liquid Effluent Flow Diagram, and are briefly listed below: l l A. Makeup Demineralized Sump and pumps for non-radioactively i contaminated water only. B. Tank Farm leakage collection sumps pumped to RHUTs A and B l via permanently installed stainless steel piping and valves. j C. Demineralized Reactor Coolant Storage Tank (DRCST) T-621 can now be pumped to the A and B RHUTs via permanently l 1 installed stainless steel piping and valves. D. RHUT T-950C with 100,000 gallon capacity for i non-radioactive liquid effluent. , l E. Additional pump P-6838 for discharging RHUT A and B. Page 9 of 31 ) 1

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                'III. HISTORICAL' PERSPECTIVE'(Continued)j F. Sluiceable' Demineralized skid. trains A and B,'each;      U containing a booster pump, one charcoal filter bed, two
                          ' cation beds, and.two anion beds with a filter at the '. inlet.

and a: strainer at the outlet. ~ G. Effluent Strainer Y-603 skid'with backflushable strainers to a set _of; disposable filt'er bags housed in the backwash

                          . tank V-602..

H. Radiation. monitors R-15017-A and B (R-15017.A replaces? R-15017). l l l Page .1Ci of 31 - - l

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  >' IV.. SYSTEM DESIGN Major functions of:the-system-design are described below:

A. Desian Obiectives 1 j. The Radioactive. Liquid Effluent. System is designed to segregate,: q

               . process, sample and dispose of potentially. radioactive water generated during periods of secondary' side contamination.      The objective of the. design is to-be able to process' contaminated-           '1 water such that the ALARA~ guidelines established by 10CFR50 Appendix I are not exceeded.                                           -

B. Desian Criteria and Bases

                                                                                             'l Regulatory Guides 1.26 and 1.143 apply to the entire system with 1

the exception of RHUT C and the Makeup Demineralized Sump which j i are not intended to contain radioactivity. Table SH-1 provides principal design parameters for- the major components of the Radioactive Liquid Effluent System. Design' considerations for -! recent plant. changes are provided below.

                                                                                             't 3

i Page 11 of 31 i-

IV.' SYSTEM DESIGN (Continued) B. Desian Criteria and Bases (Continued)

1. Makeuo Demineralized Sumo A sump with two sump pumps is provided to collect the Makeup Demineralized regenerant water and other water which does not have the potential of contamination under normal  ;

plant operation or during primary to secondary system leakage. The sump is not connected to the Polishing .

                                                                               .1 Demineralized Area Sump which potentially can be contaminated.

The piping from the sump is designed such that the water can be pumped to RHUT A, B, or C but cannot flow back from the tanks to the sump. The discharge point of the piping into the tank is located over and above the tar.k walls to l prevent any syphoning of one tank to the other or to the sump. l The two sump pumps P-966 A and B are each sized to handle normal inflows to the sumps. Level controls are installed 1 to initiate and terminate the operation of one or both f pumps, as necessary. 1 Page 12 of 31

(

l IV. SYSTEM DESIGN (Continued)~

B. Design Criteria and Balei (Continued)_ 'i j

2. Tank' Farm Sumps '

j A number'of small. sumps within the Tank Farm area are-

                                         ~
                                                                                 .i provided t'o collect'potentially radioactively contaminated!

water'from steam line. condensate. traps and equipment :j leaks.. Each sump is equipped with one pump' operated on a i level' controller. One additional portable pump ' serving all j 4 sumps is provided as a backup. The pi_ ping.has provisions . for attaching the portable pump to the discharge piping' j

                                                                                  .I routed to RHUT.A and B.                                          .

j

                                                                                  ~-

1

3. Demineralized Reactor Coolant Tank T-621 q

l 1 Tank T-621 has existed since'the plant was licensed; however, a permanent flowpath to RHUTs A and B has been~. J added for processing and. release into the plant effluent I system. A spectacle blind flange mounted in the line i I avoids unplanned water trancfer to RHUTs A and B. l

                                                                                   .j l
                                                                                      }

Page'13,of 31 l z

IV. S1SIEM DESIGN (Continued)  !

                                                                                                                   -i B. D.esian Criteria and Bases'(Continued)
4. Reaenerant Holduo Tank T-950C j The new RHUT T-950C is designed to receive non-contaminated water.via the new Makeup Demineralized Sump Pumps. Haste l generated from the regeneration process of'the Makeup Demineralizers and other non-contaminated streams which result from the sampling instrumentation of the Makeup Demineralizers are the inputs to RHUT C.

4 RHUTs A, 8 and C have a capacity of 100,000, 200,000 and 100,000 gallons, respectively. Each tank is lined with a high density polyethylene membrane. The tanks are constructed for outdoor service (open tops). The tanks are each equipped with an electric motor driven agitator for f tank mixing to allow for representative sampling prior to . releases. Four sample points at different tank elevations provide for laboratory sample analysis or local pH q measurement at the tank. Sample pumps are provided for each tank. The sample water stream is pumped past a pH

                                                                                                                    }

meter and returned to the tank of origin, j a l l l 1

                                                                                                                   .1 Page 14 of 31                                                         .

l

                                                                                                   'i IV. SYSTEM DESIGH (Continued)-

B. Desian Criteria and Bases (Continued).

4. Regenerant_Bolduo Tank T-950C (Cautinued)

The new RHUT C drains by gravity through the storm piping downstream of the Oily Hater Separator. The drainage is normally directed to Mixing Box Y-951A at the Retention Basin and then off site to Hadselville Creek. Flow can be manually diverted, and may be automatically diverted to the l Retention Basins Y-952 or Y-953 prior to release. Automatic diversion occurs when predetermined setpoints for pH, conductivity, or radioactivity are exceeded. 1 Piping is designed sur.h that the contents of RHUrs A and B cannot be transferred to RHUT C. Overflow from the three l l l tanks flows through the storm drains to the mixing box . Y-951A. Since the major source of water to RHUT C is from' l the Makeup Demineralizers, the water may range in pH from 3 l l to 11 depending upon the regeneration saquence. Provisions l 1 to add sulfuric acid and sodium hydroxide for neutralization are included for RHUT C (similar to RHUT A and B). Additionally, each tank is provided with a service j water connection f.or dilution as needed. l 1 l 4 Page 15 of 31 1 I l

IV. SYSTEM DESIGN (Continued) B. Dnian Criteria and Bases (Continued)

5. Additional RHUT Pumo. P-683B An additional RHUT discharge pump is installed, bringing '

the total number of pumps available for pumping the contmts of RHUTs A and B to two. The new pump is similar to the existing discharge pump for ease of maintenance and parts interchangeability. Each pump has a design flow of 1,000 gallons per minute at a discharge head of 40 feet. i l 6. Sluiceable Demineralizeri Dual trains of Sluiceable Demineralizers are provided to reduce effluent activity. Each train is located outdoors  ! inside a catch basin to contain any leaks from the system. Each train consists of six cartridge type disposable filters (3 micron opening) to remove particulate matter l

                                                                                               -1 prior to entering the activated charcoal filter vessel followed by two cation and two anion resin beds. The effluent from all the vessels flows through a 100 mesh (140 microns) wye strainer to catch resin fines.

The demineralized vessels each have a capacity of 25 to 30 cubic feet of macroreticular resin. Each train is designed to process 50 gallons per minute at 100 psig. Sample sinks are provided with each of the two trains. 1 Page 16 of 31

IV. SYSTEM DESI_GH (Continued) B. Desian Criteria and Bases (Continued)

7. Effluent Strainer Y-603 The self contained, skid mounted system is designed to remove potentially radioactive resins and rasin fines carried out into the RHUT A and B from either Condensate Polishing Demineralized resin regeneration or resin transfer during the throw-away mode.of operation. The l

Strainer system has the following design features: l a. The system accommodates the flow rate from a RHUT I Discharge Pump, P-683A or P-683B, and adequately filters particulate in the discharge stream without interruption of flow during a total RHUT discharge,

b. The system is self contained in its operation and physical location to ensure safe handling of potentially radioactive contaminants without uncontrolled discharges or spills.
c. The system can operate automatically with controls that operate the backwash feature of the filter on a l

high differential pressure signal, with an option to manually backwash. 1 Page 17 of 31

                                                                                                 ._J
       ':IV. SYSTEM DESIGN (Continued)-
             -B. Desian Criteria and Bases(Continued):                                             u
7. Effluent Strainer Y-603-(Continued)-
                      .d. Filter changes can be accomplished;during' operation:without..
                            -interruption of the holdup tank discharge,
e. Backwash water used -in the' filtration ; process is' contained '

in the system and transferred to the opposite, hold up tank automatically.

f. Provisions are made for discharge of water from the radiation monitor R-15020: sample pump'P-687.into.the filter discharge tank.and then to_-either. RHUT A or B.
g. The system uses compressed air for' dewatering l filter bags prior to removal,
h. The system has the capability of using a wide variety.of-disposable filter bagsiranging'in particle retention size from 100 to 500 microns.
i. The components of the system are constructed of corrosion resistant and weather proof components.

l

                                                 ,'Page 18 of'31
r. ,

f..

IV. SYSTEM DESIGN (Continued) i B. Desian Criteria'and Bases-(Continued)' -j

7. Effluent Strainer Y-603'(Continued) 1
j. The system <is contained in .a :10'~ square area.within a i concrete containment basin with a sump and pump.to. -c transfer spills and/or. rain water into either RHUT A or B.

l1 I k. The system can be bypassed to allow offsite discharge directly to'the. retention ' basins. d e 1

8. Radiation Monitors R-15017A and B-1 1

. Two new radiation monitors have been installed in'the-Radioactive Liquid Effluent System. . Design parameters.for both new radiation monitors and existing radiation monitor R-15020 are listed in Table SH-1. Monitor range' endpoints have been selected to be lay enough.to encompass the. required Technical Specification setpoints (10CFR20) and , high enough to monitor expected peak radionuclides l1 concentration under abnormal operating conditions.

                                                                                               -{

i I-i Page 19 of 31 i

IV. SYSTEM DESIGN-(Continued) B. Desian Criteria and Bases (Continued)

8. Radiation Monitors R-15017A and B (Continued)

The first new radiation monitor, R-15017A, is located downstream of mixing box Y-951B, and measures the activity contained in the outfall and releases from either retention basin (Y-952 or Y-953). This monitor will be the plant's , Technical Specification monitor when Proposed Amendment No. 155 is approved. R-15017A replaces previous radiation monitor R-15017 which was removed from service because of operational and maintenance problems. l Radiation monitor R-15017B is located at mixing box Y-951 A, and provides assurance that activity above a predetermined l value will be detected in the outfall leaving T-950C, I Cooling Tower blowdown, storm water drainage, or effluent 1 from the Oily Water Separator. This outfall can also be diluted with water from the Folsom South Canal. This , monitor is not intended to te a Technical Specification monitor; however, it does have identical setpoint alarms  ! and similar control actions as radiation monitor R-15017A. i l l 1 Page 20 of 31 l l

l

          'IV. SYSTEM DESIGN (Continue'd)

B. Desian Criteria' and Bases;(Continued)- 9

8. fladiation Monitors R-15017A and B (Continued)

Existing radiation monitor R--15020'is' the plant's Technical. Specification radiation monitor. unti_1 Proposed Amendment: i

                           -No. 155 is approved. It functions.to stop the RHUT           ,

transfer pump (s) P-683'A or 8, and to isolate: drainage from-i RHUTs A or B upon "Hi Hi Radiation" or " Fail" alarm signals ' i sent from the radiation monitor (Table SH-1 lists the i i action steps taken upon receipt of these alarms).- This- ]. monitor has been resized to respond to setpoint values' -) established by the Rancho Seco Offsite Dose Calculation Manual'(0DCM). j C. System Pinina and Instrumentation Diaarami

                                                                                           ,l i

i A set of representative P& ids along with control logic diagrams-l , l are included for indepth understanding of the modifications to the plant Haste Water System. A list of these P& ids.is provided. in Attachment 2. I i i Page 21 of 31 i j;

IV.' SYSTEM DESIGN.(Continued) l E. Process Description Two treatments have been added to the Haste Hater System since , 1985. l

1. Demineralization Demineralization of the contaminated water from RHUTs A and B can be achieved through either of the two trains. Each train is designed to process 50 gallons per j minute from either RHUT A or B and return it to either RHUT A or B (but not to. RHUT C). Each demineralized train is designed to perform filtration at the inlet by means of a disposable filter cartridge (3 micron opening) to remove any resins'or resin fines that may have been transferred i into RHUTs A and B from the Polishing Demineralized Sump.

After initial filtration, the water flows through a deep bed activated charcoal filter where a more thorough filtration and absorption occurs, removing suspended and organic matter. The next sequence of treatment is through the cation, anion, a second cation and a second anion resin bed, b Page 22 of 31 L

l IV. SYSTEM DESIGN (Continued) E. Process Description (Continued)

1. Demineralization (Continued)

Each of the five vessels in each of the two trains contains 25 to 30 cubic feet of media for providing ample ionic and

                                                                                              )

filtration capacity. The final treatment received is the further removal of any particulate material through a strainer in the effluent from the last anion bed. The cation beds will consist of approximately 5 to 7 cubic feet of sodium zeolite as a top layer over the strong acid macroreticular type of resin. The zeolite will be employed because it is more selective for cesium ions. The anion resin is of the quaternary ammonium group and the macroreticular, type. A granulated, activated charcoal bed, approximately 5 feet deep, is provided for improved filtration characteristics and protection of the anion bed from organic fouling. Each demineralized train has the capability to process 50 gallons per minute. Both demineralized trains can be  ; l placed in service at the same time to provide the i capability to process at 100 gallons per minute. i I l Page 23 of 31 i I,

I IV. SYSTEM DESIGN (Continued) E. Process Description (Continued)

1. Demineralization (Continued)

Initiation and termination of demineralization is through manual control. Sampling and analysis of influent and effluent quality and their comparison will determine the resin replacement after: exhaustion. Resins will be replaced based on the exhaustion with respect to the ions I of interest and not the normal chemical depletion. The exhausted resin will be sluiced out of the vessel and disposed offsite as solid radwaste.

2. Effluent Strainer The Effluent Strainer is available for filtration and removal of any suspended matter present in the water prior
to its release to retention basins Y-952 and Y-953.

Material collected in the 100 mesh (140 micron) stainless steel woven wire baskets is removed to disposable filter bags located inside the backwash tank (V-602). The filter bags are dewatered by introducing service air and forcing water out into the backwash tank. Filter bags are disposed offsite as solid radwaste. I l l Page 24 of 31 L l L - - - - - - - - - - - - - - - - - - 9

l

  ~IV. SYSTEM DESIGN (Continued)

F. Factors' Influencing Treatment

                                            ~

Factors influencing the two treatments, demineralization and

           ' filtration, are discussed below:

i

1. Demineralization Demineralization is accomplished both on the surface of an ion exchange media and through diffusion of the electrolyte inside the media. The ion exchange' kinetics are such that the bulk of the ionic exchange takes place on the surface of the resin particles and happens almost instantaneously.

The flow rate of process stream has little effect on ion I ei; change ability except when the flow rate falls too low. This can cause channelling or bypassing of part of the resin bed. High flow rates (above 40 gallons per square foot of vessel cross sectional area) tend to improve the filtration characteristics by reducing voids in the resin

                                              ~

bed. Temperature up to 150 F does not adversely affect the deionization mechanism; however, it can degrade the anion resin after extended exposure. Under normal operating conditions of process streams, no effect on the

j. efficiency is expected.

Page 25 of 31

IV. SYSTEM DESIGN (Continued)- F .' ' Factors Influencing Treatment (Continued)

1. Demineralization (Continued)-

One factor that significantly affects demineralization is the inlet stream composition and concentration. } Demineralization efficiency increases with the increase in the inlet concentrations. With the concentration of salts in the influent stream to the'demineralizers, the-- demineralization efficiency is expected to be very high.

2. Filtration After a short period of operation, the efficiency of filtration increases markedly with the loading of suspended matter and throughput through the filters. A mat of particles accumulates and acts as a finer filter. This i

increases the efficiency and particle retention l characteristics comparable to smaller than the openings in the filter itself. Very low flow rates do not affect performance of the basket type filter, but can reduce the efficiency of deep bed charcoal filters. Temperature changes have no noticeable effect. l Page 26 of 31 L I-

f,- 1

       ;IV. SYSTEM DESIGN (Continued)

F. Factors Influencing Treatment (Continued) 3 '2. Filteration' (Continued) The effluent strainer is a'100 mesh size which has an opening of 0.0058 inch. The resins have a nominal bead size of 30 mesh (0.0219 inch), approximately three-and-a-half times greater than the openings in the

l. effluent strainers. The strainer size can be changed, i

depending on the system pressure drop and the size of j i suspended particles.  ! l G. Flow Paths - Normal and Alternate-l '. Potentially Radioactive Liauid Effluents

a. Condensate Polishina Demineralized Area. Sump Haste water contained in the sump is transferred by Pump P-965 A or B to either RHUT T-950 A or B.

Provisions are made to allow.either RHUT to receive the waste steam from the sump to allow for system operational flexibility. l i l j i 1 Page 27 of 31 l f

                                                                                            .l

i 1 IV. SYSTEM DESIGN (Continued) G. Flow Paths - Normal and Alternate (Continued)

1. Potentially Radioactive Licuid Effluents (Con'tinued)
b. Demineralized Reactor Coolant Storaae Tank (T-621) and 4 Tank Farm Area Drains Flow may be directed from the Demineralized Reactor Coolant Storage Tank T-621 or the Tank Farm Area sumps into either RHUT T-950 A or B. This flow path bypasses the demineralized beds. The waste water from these sources is treated along with other waste water contained in RHUT A or B.
c. Reaenerant Holduo Tank Discharae (RHUTs A and B)

Sampling and analyses are performed for chemical and radiochemical activity prior to release from the tanks. In the normal configuration, the effluent from either RHUT T-950 A or B is pumped by either regenerant waste transfer pump P-683 A or B through the effluent strainer Y-603, past the effluent radiation monitor R-15020 and flow monitor FE-60327, j into the underground discharge header to either the North (Y-952) or South (Y-953) retention basin. Only j one RHUT may be discharged to a retention basin at a i time. l l l l 1 Page 28 of 31 I l l l < __ _ _ _-_ A

i b. g IV. SYSTEM DESIGN (Continued). G. Flow Paths - Normal'and Alternate (Continued)

1. Potentially Radioactive Liouid Effluents (Continued)'
c. Recenerant Holduo Tank Discharae (RHUTs A and B) . (Continued) l Alternatively. if determined that straining is not -
                                                                                                                                   )

required, the effluent strainer can be. bypassed. Also, the  ! RHUTs. can be gravity drained through or.around the effluent' strainer if both transfer pumps are disabled. lne RHUTs 1 can be gravity drained to the demineralized booster pumps l P-604 A and B, processed through the demineralized and then i returned to either RHUT A or B. Further, both strainer and demineralized processing can be used in series. If high radioactivity is detected in RHUT A or B, the contents can be pumped to Spent Regenerant Tanks T-689 A and B via the Sluiceable Demineralized Skid booster pumps P-604 A and B and the Condensate Polishing Area Sump. The processing. flow paths provide a wide range of operational flexibility, i l l i l Page 29 of 31 i

! 'IV. SYSTEM DESIGN.'(Continued) G.' Flow Paths - Normal and Alternate (Continued)

2. Non-Radioactive Liauid Effluents  ;
a. Makeuo Demineralized Sumo Hakeup Demineralized regenerant and rinse waste water contained in the Makeup Demineralized Sump'is transferred l

by pumps P-966 A or B to regenerant holdup tank T-950C. Cross-connections allow waste water to be transferred from , the Makeup Demineralized Sump to RHUT T-950 A or B; however, waste water in RHUTs T-950 A or B cannot be transferred to RHUT T-950C or to the sump.

b. Recenerant Holduo Tank Discharae (RHUT C) i Contents of the tank are sampled and analyzed for chemical and radiochemical activity prior to release. The effluent from RHUT T-950C is gravity discharged into the plant storm drainage system which then directs the waste stream into the first mixing box (Y-951A) upstream of the retention >

i basins. The waste water may be diluted with raw water from Folsom South Canal or diverted into either of the two retention basins. The waste water is automatically diverted to the retention basins on high conductivity, high or low pH, High or Alert Activity, or failure of either R-15017A or R-15017B and pump P-957 secured. Radiation  ! monitor R-150178 continually monitors the discharge from the mixing box. The mixed effluent is monitored in the final effluent basin by radiation monitor R-15017A. l l Page 30 of 31 j

 ./

IV. SYSTEM DESIGN (Continue')d

                .G. Flow-oaths -' Normal and Alternate (Continued)
3. Retention Basin Discharae-The waste water from the retention basin is pumped via~ pump P-957 (Retention Basin Recirculation Pump).into the second mixing box (Y-9518). There it is diluted with Folsom South Canal water and/or other non-radioactive plant effluents.
                         ~ The mixed effluent is monitored for radiation by radiation monitor R-15017A. When Proposed Amendment No. 155 is approved, radiation monitor R-15017A will become the Technical Specification monitor in lieu of monitor R-15020.

Flow device FE-95108 measures the final, total flow rate from the plant' and is located downstream and within a few feet of-radiation monitor R-15017A. FE-95108 is the existing Technical Specification flow monitoring device. The flows are indicated on H4RH (Hastewat6r Panel) and H4HH-in the Control Room. Associated flow recorder FR-95108 is located at the point of monitoring. FE-95108 will remain the Technical Specification flow monitor for the final, , total plant effluent flow rate with the approval of Proposed Amendment No. 155. l l Page 31 of 31  ! 1

q

     \                                                          ATTACHMENT.1 Page-1 of 9                           ,
                                . TABLE SH-1                                                           I i
                    -DESIGN BASES CODES AND STANDARDS-                                              1 l

RADI0 ACTIVE LIQUID EFFLUENT SYSTEM- j PRINCIPAL DESIGN PARAMETERS

   ' PIPING AND VALVES Design Codes-                    ANSI B31.1 Regulatory Guides 1.26                                        !

and 1.143 apply except to T-950C and Makeup Demineralized Sump i PUMPS ,

                                                                                                 'i Backwash Discharge PumD (P602A)

Number 1 Horizontal Type Centrifugal Design Pressure-(psig) 65~ Design Temperature (OF) 120 Design Flow (gpm) 125  ! 1 Design Head.(ft) 10 , Material SS Project Quality 2 Classification Hydraulic Design Code Institute Regulatory Guides 1.26 & l.143 1 Backwash Return l PumD (P6028) Number 1 i l Horizontal l Type Centrifugal Design Pressure (psig) 65 Design Temperature (OF) 120 l Design Flow (gpm) 125 Design Head (ft) 10  ; ! .-------_______________a

L ATTACHMENT 1 Page 2 of 9 TABLE SH-1 i RADI0 ACTIVE LIQUID EFFLUENT SYSTEM . PRINCIPAL DESIGN PARAMETERS Backwash Return Pumo (P6028) (continued) 9 Material SS  ; Project Quality 2 Classification Hydraulic Design Code Institute Regulatory Guides 1.26 & 1.143 Sluiceable Demineralized Pumos (P604 A & B) Number 1 per train Horizontal Type Centrifugal Design Pressure (psig) 100 Design Temperature (OF) Ambient Design Flow (gpm) 50 Maximum Flow (gpm) 75 Design Head (ft) 231 Material 316SS Project Quality 2 Classification Hydraulic Design Code Institute l Regulatory Guides 1.26 & 1.143 Regenerant Holdup Transfer Pumos (P683 A & B) l l Number 2 Horizontal Type Centrifugal 1

ATTACHMENT 1 Page 3 of 9 TABLE SH-1 RADI0 ACTIVE LIQUID EFFLUENT SYSTEM PRINCIPAL DESIGN PARAMETERS Regenerant Holdup l Transfer Pumos (P683'A & B) (continued) ] Design Pressure (psig)' 150 j Design Temperature (OF) 120 l 4 Design Flow (gpm) 1000 Design Head (ft) 40 Cast Iron Casing i Material Hith Bronze Impeller > Project Quality 2 Classification f Hydraulic Design Code Institute Regulatory Guides 1.26 & 1.143 MAKEUP DEMINERALIZED SUMP Number 1 Type Below Grade, Enclosed Design Pressure (psig) Atmospheric Design Temperature (OF) Ambient Design Flow (gpm) Inlet Flow 150 gpm Sump Volume (gal) 1200 i i

                  ;. ./'
                                                                                           '1 ATTACHMENT l'
                                                                           .Page 4 of 9 f-TABLE SH-1                                            I RAD'I0 ACTIVE LIQUID EFFLUENT SYSTEM
           !                     PRINCIPAL; DESIGN PARAMETERS l

Makeup Demineralized Sumo Pumos (P966 A and B) . . J Number 2 Submerged y Type Duplex

               -Design Pressure (psig)                   250                                    ,

i Design Temperature (OF) 180 Design Flow (gpm) 250 q l Design Head (ft) 60 Material Alloy 20 i Project Quality 2 C1 ossification-Hydraulic Design' Code Institute

                                                                                          'i TANKS
               'Regenerant Holdup Tank (T950A)                                                              'l Number                                   1 Type                                     Vertical Cylindrical                 !

u Usable Volume (gal) 100,000 Design Pressure (psig) Atmospheric Design Temperature (OF) Ambient Carbon Steel lined with Material High Density Polyethylene (HDPE) i i I Project Quality 2 Classification 1 Design Code API 650; Regulatory Guides 1.26 & 1.143 Agitator Motor (hp) 20 l~

ATTACHMENT 1 Page 5.of.9' TABLE SH RADIOACTIVE LIQUID EFFLUENT-SYSTEM PRINCIPAL DESIGN PARAMETERS Regenerant' Holdup LTank (T9508) Number. 1 Type Vertical Cylindrical Usable Volume (gal) 200,000 Design. Pressure (psig). Atmospheric Design. Temperature (OF) Ambient. Carbon Steel lined with Material High Density Polyethylene (HDPE) Project Quality 2 Classification Design Code API 650; Regulatory Guides 1.26 & 1.143 Agitator Motor.,(hp) 20 Makeup Demineralized Regenerant Holdup-Tank (T950C) Number- 1 Type Vertical Cylindrical Usable Volume (gal) 100,000 Design Pressure (psig) Atmospheric Design Temperature (OF) Ambient Carbon Steel lined with Material High Density Polyethylene (HDPE) l Project Quality 2 Classification Design Code API 650 Agitator Motor (hp) 15

1 ATTACHMENT 1 I Page 6 of 9 TABLE SH-1 RADI0 ACTIVE LIQUID EFFLUENT SYSTEM i PRINCIPAL DESIGN PARAMETERS SLUICEABLE DEMINERALIZERS Number (per train) 4 (2 Cation beds, 2 Anion beds) Deep bed f Type MR Resin Design Pressure (psig) 180 Design Temperature (OF) 250 Design Flow (gpm) 50 Material SS Project Quality 2 l Classification  ! ASME Design Code Section VIII; Regulatory Guides 1.26 & 1.143 FILTERS Inlet Filters (Sluiceable Demineralizers) Number 1 (per train) Type Six Hound Cartridges with Openings 3 micron Top Loading Design Pressure (psig) 150 { l Design Temperature (OF) 200 Design Flow (gpm) 50 I Material SS Housing Project Quality 2 Classification  ! ASME . Design Code Section VIII; Regulatory Guides 1.26 & 1.143 l 4 l

3 l ATTACHMENT-1 Page~7 of.9 TABLE SH-1 RADIOACTIVE LIQUID EFFLUENT SYSTEM .j PRINCIPAL DESIGN PARAMETERS-Outlet Filters (Sluiceable Deinineralizers) I Number 1 (per train) Hye strainer ' Type 100 mesh Design Pressure.(psig) 150 Design Temperature..(OF) 200 Design Flow (gpm) 50  ! Material SS Project. Quality 2 Classification j ASME l Design Code Section VIII; Regulatory Guides  ; 1.26 & 1.143 Charcoal Bed (Sluiceable Demineralizers) Number 1 (per train) Activated ' Type Charcoal Design Pressure (psig) 180 Design Temperature (OF) 250 Design Flow (gpm) 50 Material SS Project Quality 2 Classification . ASME l Design Code Section VIII; Regulatory Guides 1.26 & 1.143 , i

ATTACHMENT 1 Page 8 of 9

                                      .. TABLE SH-1 RADI0 ACTIVE LIQUID EFFLUENT SYSTEM PRINCIPAL DESIGN PARAMETERS EFFLUENT STRAINER (Y603)-

Number 1 Type Five Backflushable Elements (with 1 spare) 100 Mesh (140 Micron) Design Pressure (psig) 150 Design Temperature (OF) Ambient Design Flow-(gpm) 800  ; Material SS Filter ElemeMs Project Quality 2 Classi fication . ASME Design-Code Section VIII;. Regulatory Guides-  ; 1.26 & 1.143 i NEW RADIATION MONITORS (R-15017A & B) Type and Model Off-line Gamma Scintillation i Detector (GA RD-53) l Sensitivity (micro-curie /ml) Approximately 2.6 X 10 -8 CS-137-Range (micro-curie /ml) 1 X 10 -7 to 1 X 10 -I CS-137 Data Recorder Control Room or Panel H4HH j

ATTACHMENT 1. Page 9 of>9:

                                          -TABLE SH-1 l

l RADI0 ACTIVE LIQUID EFFLUENT SYSTEM PRINCIPAL DESIGN PARAMETERS TECHNICAL SPECIFICATION SETP0INTS AND ACTION (R-15017A)* i Hi Alarm Calculated in accordance Automatic termination of  ! with ODCM- retention basin discharge, and diversion of flow to a i preselected retention basin (open FV-95201 and FV-95301). Closure of FV-95103, CV-95101 and -1 FV-95401. Pump P-957 secured. Alert Alarm Calculated in accordance Action same as for with ODCM Hi Alarm Fail Alarm Action same as for .l Hi Alarm

     *R-150178 has same Setpoints and similar Actions as R-15017A but is not the                !

Technical Specification monitor. .j RADIATION MONITOR (R-15020) (Existing) Type & Model Off-line Gamma Scintillation Detector, (Victoreen Model 843-30) Sensitivity (micro-curie /ml) Approximately 2 X 10 -7 C0-60  : (

Reference:

USAR Table 11.3-2) l Range (micro-curie /ml) 1 X 10-7 to 1 X 10-2 CO-60 ' (

Reference:

Procedure AP.305-33) Data Recorder Control Room Panel H4MR f 4 TECHNICAL SPECIFICATION SETPOINTS AND ACTION (R-15020) Hi Alarm (Value as per ODCM) Close FV-95003 and FV-95008. Secure pumps P-683A & B, and sample pump P-687. Alert Alarm (Value as per ODCM) Action same as for '; Hi Alarm Fail Alarm Action same as for . Hi Alarm

7_ _ ATTACHMENT 2 Page 1 of 4 i i INDEX OF SELECTED DRAHINGS  ; FROM ENGINEERING CHANGE NOTICES A-4954 AND R-0775  ; __ TASK DRAHING NUMBER SHEET NUMBER REVISION TITLE

  • A-4954 M 563 3 0 Effluent Strainer (Sht 1 of 2)  ;

M 563 3 0 Effluent Strainer (Sht 2 of 2) R-0775A M 592 1 19 Miscellaneous Systems M 592 2 0 Miscellaneous Systems M 596 2 23 Miscellaneous Water Systems R-0775B C 136 0 16 Yard Plan R-0775E M 501 0 3 Instrumentation Symbols M 510 1 19 Radiation Monitoring System M 560 5 7 Coolant Radwaste System (DRCST T-621)(Two Sheets) M 563 1 25 Haste Water Disposal System 1 (Retention Basins) M 563 2 10 Haste Hater Disposal System (RHUTs T-950A and T-9508) (Two Sheets) M 563 3 0 Effluent Strainer (Strainer Y-603, Backwash TK V-602

                                                        & Sluiceable Demin.)(Two Sheets)

M 563 4 0 Haste Water System (RHUT T950C) P&ID unless otherwise noted. 1 I l

1 ATTACHMENT 2 Page 2 of 4 j 1 INDEX OF SELECTED DRAHINGS FROM ENGINEERING CHANGE NOTICES A-4594 AND R-0775 TASK 'DRAHING NUMBER SHEET NUMBER REVISION TITLE

  • R-0775E- M 571- 1 29 Turbine Plant Chemical Addition System L

M 590 1 34 Plant Air System M 592 2 0 Miscellaneous Systems (Makeup Demin. Sump and pumps) (Two Sheets) H 593 2 10 Miscellaneous Water Systems (Miscellaneous Hater Holdup TK -993) M 593 3 17 Miscellaneous Hater Systems R-0775G M32.04-1 1 0 Radwaste Demineralized System (Sluiceable Demin. Package) M32.04-3 .1 'O Demin. System (Installation Drawing) i R-0775H H 535 '1' 8 Condensate Polishing Demin. System M 541 2 4 Plant Cooling Water System (Two Sheets) i 1 M 572 1 26 Turbine Plant Sampling System l (Two Sheets) i M 592 1 20 Miscellaneous Systems (Makeup Demin. Sump and Pumps) i o P&ID unless otherwise noted. i

                                                                                                       - - - - - - o

ATTACHMENT 2 Page 3 of 4 INDEX'0F SELECTED DRANINGS FROM ENGINEERING CHANGE NOTICES A-4954 AND R-0775 i _IASJ DRAHING NUMBER SHEET NUMBER REVISION TITLE

  • i R-0775I M 563 1 29 Haste Hater Disposal System I (Retention Basins)

M19.44-2 0 Retention Basin Pneumatic' System f (Layout Diagram) I 594 4 0 Bistable Switch Diagram (Listing for Y-952 and Y-953) I 594 5 0 Bistable Switch Diagram (Listing for T-950 A, B and C. V-602 and T-762). I 199 67 3 Regenerant Holdup Tank T-950A (Level Setting Diagram) (Two Sheets) I 199 71 1 Polishing Demineralized Sump j (Level Setting Diagram) l 1 I 199 91 0 Regenerant Holdup tank T-950B. , (Level Setting Diagram) l I 199 92 0 Makeup Demineralized Sump I (Level Setting Diagram) I 199 93 0 Regenerant Holdup Tank T-950C (Level Setting Diagram) I 199 94 0 Effluent Strainer Backwash Tank V-602 (Level Setting Diagram) I 206 23 0 Demin. Sump Pump (Logic Diagram) I 206 30 6 Q.C./ Haste Water Discharge (Regenerant Tank T-950 and Retention Basins Y-952 and Y-953) (Logic Diagram) O P&ID un1Ess otherwise noted.

ATTACHMENT 2-Page 4 of 4

INDEX 0F-SELECTED DRAHINGS FROM ENGINEERING CHANGE NOTICES A-4954 AND R-0775
 -4
    -TASK    DRAHING NUMBER SHEET NUMBER REVISION              TITLE
  • a j r  ;
    'R-0775I       I'206         '31            0       RHUT T950A and B Outlet Valve (Logic Diagram)                                                                            q 1

I 206 32 0 Make-up. Demineralized Sump. Pump- i (Logic Diagram)  ! I 2410 4 0 Annunciator Hindow Box i H2SFA/H2SFB/H2X/H2HC  : (Arrangement drawing) l E10.11 1 0 Regen. Hater Transfer Control Panel l H4RH (Cabinet Arrangement Drawing) i i E10.11-27 1 0 Regenerant Haste Transfer. Remote Signal j Process Panel H4RHA '4 (Cabinet Arrangement Drawing)  : E10.11-28 1 0 Regenerant Haste Transfer Remote S'ignal Process Panel H4RHC g (Cabinet Arrangement Drawing) 1 E10.11-29 1 0 Regenerant Haste' Transfer Control ) Panel H4RH (Panel' Arrangement) l i i P&ID unless otherwise noted. 2 4 l

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