ML20042F183

Forwards Request for Addl Info Re Application for Certification of Advanced BWR Design.Response Requested by 900530

ML20042F183
Person / Time
Site:	05000605
Issue date:	05/04/1990
From:	Scaletti D Office of Nuclear Reactor Regulation
To:	Marriott P GENERAL ELECTRIC CO.
References
NUDOCS 9005070352
Download: ML20042F183 (10)

Text

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May 4,~1990 NM Docket No, STN 90-605 Patrick W. Marriott, Manager Licensing & Consulting Services GE Nuclear Energy General Electric Company 175 Curtner' Avenue San-Jose,-California 95125

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SUBJECT:

. ; REQUEST FOR ADDITIONAL INFORMATION REGARDING,THE GENERAL ELECTRIC COMPANY APPLICATION FOR CERTIFICATION b

OF-THE ABWR DESIGN During the course of the review of your application for i

4 certification of your Advanced Boiling Water Reactor Design, we m

have identified a need for additional information.

Our request-for additional information, contained An the enclosure, addresses the areas of SRP Section 11 reviewed'by the Plant Systems Branch,-

and SRP-Section 12. reviewed by the Radiation Protection B' ranch.

We request that you provide your responses to this request by May 30, 1990.

If.you have any concerns regarding-this request please call me on (301) 492-1104.

Sincerely,

/s/

Dino C.

Scaletti, Project Manager Standardization and' Life Extension Project Directorate Division of Reactor Projects - III, IV, V'

and Special Projects.

Office of: Nuclear Reactor Regulation

Enclosure:

As stated i

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175 Curtner Avenue s-San Jose, California-95125 s

Dear Mr. Marriott:

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SUBJECT:

REQUESTh0RADDITIONALINFORMATIONREGARDINGTHE-GENERAL ELECTRIC COh/ANY APPLICATION FOR CERTIFICATION OF THE'ABWR DESIGN During the course of the review of.your application for l

certification of your Advanced Boiling Water Reactor-Design, we have identified a need for additional information,.

Our request for additional information, contained 11'n the enclosure,.addressos the areas of SRP Section 11 reviewed by the Plant' Systems Br4ach,

-and SRP Section 12-reviewed by the Radiation Protection' Branch.

We' request that you provide your responses to this request by May 30, 1990.

If you have any'corcerns regarding this_ request please call me on (301) 492-1104.

-I Sincerely,

/s/

i Dino C. Scaletti, Project Manager Standardization and Life Extension Project Directorate Division of Reactor Projects - III, IV, l/

and Special Projects Office of Nuclear-Reactor Regulation d

Enclosure:

As stated DISTRIBUTION:

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Dear Mr.-Marriott:

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SUBJECT:

REQUEST FOR. ADDITIONAL INFORMATION REGARDING THC' s

GENERAL ELECTRIC : COMPAln' APPLICATION. FOR ' CERTIFICATION' OF THL ABWR-DESIGN-During.the course of..the review'of your: application fort i-x.s certification of your Advanced Boiling Water Reactor Design,\\ ve l-have identified a 'need for additional 4information.;.Our. request -

forEadditional information, contained' in-the enclosure, addresse's I

the-areas.of SRP Section 11 reviewed by'the Plant,SystemE= Branch, and SRP Section 12 reviewed by-the Radiation Protection' Branch.

l We request that you provide your reAponses to'this request by May 30, 1990.' If you have any concerns regarding(this request' l

, 492-1104..

1 please call me on (301) s-h 4

Sincerely,'

hpgA Y-.

Dino-C. Scaletti, Project Manager t

Standardization and Life-J Extension Project Directorate '

Division of Reactor Projects - III, IV, V1 and Special Project: 3 n

Office of Nuclear. Reactor ~ Regulation-a

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Enclosure:

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T' REQUEST FOR ADDITIONAL INFORMATION j

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'C STANDARD SAFETY ANAL'.(SIS REPORT (SSAR) i

' SECTIONS.11.2, 11.3, ANDill.4 FOR THE ADVANCED BOILING WATER REACTORi(ABWR)

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430)154 All, figures.in ABWR SSAR Section"11.2'except' Figures

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4 11.2-2a and 11.2-2B-are not. legible'.,.

Provide (11.2) '

enlarged-size legible versionss of the' figures. j s

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430.105 For each liquid radwaste cubsystem, provide the ' ' 3 (11.2) available margin for processing surge flows by comparing'the' expected normal-. daily waste generation 4

m rate with thecdasign flow rateEfcirithe limitingi.'

processingequipment;.{

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430.156x Provide specific information detailing h'w;ther liquid o

- (u.2) radwaste systema reet. Regulatory"Guidell.143' guidelines '(C.1.2.1 through C.1.2. 5), 'and C.4.1 through-C.4.5.

' Provide, layout diagrama as necessary.

Describe the indications provided to the operator?that a transfer from one storagextank to another (the design 4 basis sta::es that uponNhigh level: signals, inputa'are i

sautomatically routed to a parallel tank ABWR Section t

SSAR 11,.2.1.2.):has occurred.

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430.157 Provide information on the-following tems for the

( 11'. 2 )

liquid radwaste system:

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1. Reactor. coolant activity.(RCA) fraction for-each i

I aubstream of the low lconductivlty:wasteT(LCW) and high-conductivity waste-(HCW)1 streams;and)theieffective'RCA fractions for the LCW' dud HCW streamm-Integrate n

F ecxpected average 2 daily liquid radwaste: inputs'due to T

(

generation of chenical vastes,; ultirasonic resin v,a i

cleaning, cleanup phase separator decant backwash,innd p

unique design features cf thetABWR with other' inputs.

applicable to the LCW and MCW streams., ' Provide,the total expected average; da'D y input: toi the LCW and' HCW f

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I streams,.

Note that'ABWR SSAR Table'11;2a3,in n

incomplets. ' Some: of' the values. for wa tes. generated d

1 given :in the table-are significantly lower than those t

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given in~the report' ANSI /ANS-55.G-1979 or NUREG-0016p

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Rev.J1.

The values given'in these reports for1BWRa may H

be usedx but some minor adjustments for the ABWR' design l

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may be necessary (for err.ple, drywell equipment; drain input.of 3400 gallons per day (ejpd)iwbich includes 2200 gpdf ue to' recirculation pumpuseal; leakage atay;re" quire d

pl adjustnent for3the ABWK design)'. ' Alsod define theiterms CUW and CF mentioned'in Table 11.2 a.

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2. Holdup times associated with collection a.' processing of the LCW and HCW streams; holdup time assa31ated with discharge of the HCW stream.

3. Capacities of all tanks, including sample tanks (in gallons) and processing equipment (in gpm) consicered in calculating holdup times for the LCW and HCW streams.

Include applicable discharge pump flow rate.

State whether or not sample tanks are shared.

4. Clarify how the liquid radwaste system has adequate margin to preclude liquid radwaste discharge even under a wide variety of anticipated operational oc urrences.

430.158 For the detergent.aste subsystems, provide the (11.2) capacities of all tanks, flow rates of processing equipment and pumps.

Clarify rain sample talks.

(ABWR SSAR Section 11.2.1.2 states that these wastas are discharged from the hot shower drain receiver tank whereas Section 11.2.3.1 states that these are discharged from the shower drain sample tanks.)

Also, clarify whether the hot shower drain receiver tank has adequate capacity to collect the high volume of detergent wastes (31.3 cubic meters per day -

Table 11.2-3) and whether storm drain (s) is also an input to the tank (ABWR SSAR Section 11.2.2.3 does not include storm drain; however, Table 11.2-3 shows a volume input of 20 meters / day from this source).

430.159 ABWR SS?.R Tables 11.2-4 and 11.2-5 do not indicat.e that (11.2) detergent wastes, all of which are expected to be released untreated (note that the staff does not give any credit for radioactivity removal due to processing through a detergent filter), have been included in the table.

NUREG-0016, Rev. I has calculated a total of 0.09 ci/yr for the untreated release of detergent wastes.

Revise these tables to include the untreated reletse of detergent wastes.

Also, include expected tritium release via the liquid effluents.

Further, provide the basis for releasing the detergent waste via the liquid pathway untreated.

430.160 Limiting Valde of 200 gpm for discharge of liquid (11.2) radwaste to the discharge canal in conjunction with 1

minimum dilution volume of 1500 gpm given only a low minimum dilution factor of /

for a critical liquid s

pathway exposure i.e.,

fishing in the discharge canal.

The above compares with a dilution factor of 200 and much above that quoted by a number of operating BWRs in their periodic effluent reports.

With the expected k

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________._---___.-n release of high conductivity liquid wastes (can be up to 10 percent of the total high conductivity wastes) and untreated detergent wastes, it is not clear whether the dilution factor of 7.5 will be adequate to ensure compliance with 10 CFR, Part 50, Appendix I dose limits for 31guid pathways, even if an additional dilution factor of 5 is included between the canal and subsequent consumption or recreational activity involviag liquid effluent.

Also, it is not clear whether the low dilution factor will make it difficult to complete monitoring prior to release of liquid radwaste.

Address the above concerns by either decreasing the limiting value of liquid radwaste discharge rate or increasing the minimum dilution volume or doing both of the above.

430.161 Clarify wheths.r the seismic Category I steel-lined (11.2) radwaste building substructure (see response to Question No. 430.58 dated March 7, 1989) includes the base mat and outside walls to a height sufficient to contain the maximum liquid inventory expected to be in the building.

430.162 Regalatory Guide 1.143, Position C.2, provides that, for (11.3) a s, stem with a design pressure of less than 1.5 atmosphere absolute, the supports for the charcoal tanks and the buildings housing these tanks meet the seismic design criteria of Position C.S.

Clarify whether the charcoal adsorber vault meets these requirements.

Include a discussion of how the gaseous waste management system meets Position C.5 guidance.

430.163 Figures 11.3.1 and 11.3.2 have been reduced so that (11.3) positions of each of these figures are not legible.

Provide legible versions of these figures.

430.164 The combination of the design dewpoint (30 F, ABWR SSAR (11.3)

Section 11.3.4.2.7), the system operating 'emperature (100 F, ABWR SSAR Section 11.3.3.1) and the mass of charccal (12 tons, ABWR SSAR Table 11.3-2) gives a

significantly lowsr dynamic adsorption coefticiente for krypton and xenon, and consequently much lower holdup times for these gases in the offgas processing system than those given in ABWR SSAR Section 11.3.2.

Correu the values for aasorption coefficients and the holdup times as appropriate.

Note that the staff calculates the holdup times using the expression given in NUREG-0016, Ron 1 (page 2-35).

Also, note that the above parametrac values will result in substantially higher ngble gas releases to the environment (e.g.,

about 10 ci/yr for Xe-133) from the offgan treatment system.

Provide the dynamic adsorption coefficient and n

holdup time for Argon-41 also.

(In this context, the I

staff notes that GE provided tne same holdup times for

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l'.e.,-~42 days -and 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> j

respectively, in the SAR for GESSAR-II, which uses-a refrigerated charcoal delay bed system contaisiing 34.6 tons Jf' nctivated charcoal.)

Additionally,Ljustify the appar rl significant reduction in holdup time for noble gasies ror; an advanced design such as; ABWR.

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'430.165 Describe provisions to, control leakage paths to the-

-(11.3) environment after a hydrogen detonation within the*

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. gaseous wa'te :tanagemrnt.' system.

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430.166 Provide information on1the following items'.forfthe (11.3) gaseous' waste management; nyste:a:t

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.Hydregen concentration instruanntation ;and j

associated alarm provisions. : Discuss how the!ABWR-instrumentationJconforma'with applicable guidelines of SRP 11.3, Acceptance Criterion'II.B.6, _pages1 i

11.3-4 th, rough;11.3-6.

Also,: discuss'how theloffgas;

. system design compliesjwith GD0;3 astit relates.to j

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-providing protection to tha;nyatem=from the effects:of

>4 an explottive mixture offjydrogen-and oxygen.

B.

Holdup tium for. off-gassen.frtJa the main condenser s

-air ejechor off-gas, treatment system.,The< staff notes

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that GEidid nct provido a satinfactory responso'to the,.

above ques.tioi raised earlier,(seeiGE's response dated; l,

March 7, 1989 to: Question No. j60 4.7)~.-

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offgas system alarmed process parameters?(provide-1 in tabular form).

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Design holdup timesfor! gas: VdntedLfrom thei j

seal condenser, iodine' partition factor for thia gland condenser, and fraction of'radiciodine'reluased through I. - )

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Providecexpected3annualunoble gas;and L

iodine. releases to the environment f, including;the basis i

l' and. rationale) from the turbine gland seal system.

i resulting from use. of steam gennrated from mainLsteam and highcpressure heater 41 rain tanks for/ sealing the turbine < gland' (800. GE'n responuo Lto Question.No. 4 30. 83 yy.

datei February ~28, 1990)1.y

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ri Piosisions incorporated-to, reduce radioactivity,

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releasesithrough theLventilation systenri (turbin4 '

p building,- etc.) (e.gq fMEPA filter, chsrcoal-adsorbers il

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and"their thickneus).

Discuss how'ths ABWR systems,.

M, conforn'Vith tho' guidelines of Regulatory unide'1,140' l'

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with respect to'the trea.ttent systemnifor.the.se release.

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Release! points,. effluent flow rates.through them i

and their other characteristics (see NUREG-0016, Rev.

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Section 4.7, Item 4).

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-Provide a' discussion on compliance with GDCs-60 and 64 for all gaseous releases to the environment (do-not 1

limit:this discussion-to_the offgas_ system).

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Monitoring:of the individual performance of the equipment within the offgas: system.-

430.167 Thertotal annual noble-gas release from the offgas-(11,3).

treatment system.given in ABWR.SSAR Table 11.3-1 is

'7 incorrect.

Also, the table;11sts only releases,from'the offgas treatment system.

Provide a table listing i espected annual total = airborne release from all

'j nources_(offgas system, mechanical vacuum pump, gland, i

seal, building ventilation releases. including icontainment. purges) for noble gases,' including Argon-41,

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iodines, particulates,Lcarbon-14'and tritium during-l 7

. normal plant operation including anticipeted operational occurrences.

j 430.168 Novide a table comparing airborne effluent.

(11.3) ccncentrations for all radionuclides during periods of fission product release at design levels from the fuel

-with 10 C'FR Part 20 concentration limits. 0 169' Section,11.4.2.3.5'makes reference;to storage of containers until they can beLshipped.

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description of the storage facility for: solid wastes is I

provided.

Provideeinformation regarding these' T

storage facilities that;shows that these facilities will meet the guidance or BTP ETSB 11-3'.Part B.III and' Regulatory Guide 1.143.

L 430.170 Provide a table of expected waste volumer,, generated.

I (11,4) annually by each " wet" r.olid. waste sotwe"(normal and i

greater-than-expected surge waste voltmes) and;the 4

capacities ofcall tanks accumulatino spent' resins and filter sludges.

Provide the corre:,ponding. specific t

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activity fop each " wet" solid waste source.: These tanks should be sized so.as to meet the storage requirements of BTP ETSB 11.3, Part B.III.1; Pr' ovide'an' estimate. of

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expect'ed/ annual " dry" solid' wastes and the corresponding, curie.' content.

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430.171-Tgble 11.4.2 shows-a solid? waste generation rate of._97.3 (11.4) n / year.

Thic amcunt of, solid wasteiis significantly smaller (by an order of magnitude) than values used in previous FSARLs.for BWR's._

Provide the justification

,J for this reduction. in-wanice: production' or revise the b

y estimate for' waste production rates.

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v 4 3 0.17 2 l. _ Identify-which of the-design criteria from ABWR SSAR' (11.4)

Section;11.2.1.2 are' deemed-to be applicable to the solid waste system. 'Specifically,'the criteria of Sections 11.2.1.2.1-(Quality Classification, Construction and Testing Requirements) and 11.2.1.2.2 l

(Seismic Design) should be applicable to the solid waste system and shouldebe identified in Section 11.4.

430.173 Verify that the structures containing the solid waste

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(11.4) system meet-the seismic qualifications of Regulatory.

LGuide 1.143, Position C.3.1.3.

430.174-Section 11.4.1.2 (Design' Criteria) statesfin part that-(11.4)

" Proportional' amounts of waste and fixative are

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. incorporated.toLinsure that-no-free water = accumulates.in:

'the waste container."

Provide details:on the: procedures' needed to: insure proper mixing and:to detect free wate'r if still'present,after mixing.

1 430.175 Discuss compliance of the solid waste management system-i (11.4) with 10:CFR-Section 20.106, GDCs 60 and 63-requirements.

Include both " wet" solid wastes and " dry": solid; wastes in the discussion.;

I 430.176 Discuss how-the: solid waste-management system meets the.

1 (11.4) guidelines identified under " Additional Design; Features" in BTP ETSB 11.3, Part B.V.

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a REQUEST.FOR ADDITIONAL INFORMATION SSAR CHAPTER 12 L

The Radiation Protection. Branch ~ completed its review of the ABWR-SSAR, Chapter 12, Radiation, Protection on October-25,-1988, c'

and also more recently completed the review of the Radiation-Protection Section of. the EPRI ALWR Requirements Document.

It is L

our= understanding that the ABWR plans to comply;with the criteria L

provided in ALUR Requirements Document, 'We have the following.

request for additional information:

471.42 EPRI-ALWR Requirement Document;in Chapter 12:

Radioactive

[

Waste' Processing System (page 12.3-8), Section 3.2.l', Goal for GRWPS Radioactivity; Releases states that:

"The total radioactivity of gases released ~from:the plant;

'(excluding'the activity of released tritium)'shall not exceed the-following values:

BWR: 2,000' curies per year; etc. "'

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l ABWR, standard plant, in Chapter 12, Radiation Protection, in Section'12.2.2.1, Orc $uctior of Airborne Sources, last paragraph states that:

l "Approximately 'i,900 Ci/ plant / year of nobl'e.radi'ogases are released; one-half of this total is released-from the Li turbine building...".

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Please address this apparent discrepancy.

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