Text

Submits Comments on Proposed Revision 2 to Reg Guide 1.97. Comments Include plant-specific Design Summary,Current Generic Design Requirements & Specific Views on Proposed Revision 2.Plant Design Meets Intent of Guide
	ML19257D538
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	01/30/1980
From:	Novarro J; LONG ISLAND LIGHTING CO.
To:	Varga S; Office of Nuclear Reactor Regulation
References
	RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-OS, TASK-RS-917-4 SNRC-460, NUDOCS 8002040572
	Download: ML19257D538 (16)
	v • d • e

.

7 LONG ISLAND LIGHTING COM PANY

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_ /anrxewzars SHOREHAM NUCLEAR POWER STATION P.O. BOX 618. NORTH COUNTRY RO AD

WADING RIVER. N.Y.11792 January 30, 1980 SNRC-460 Mr. Steven A. Varga, Chief Light Water Reactors, Branch 4 Division of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Varga:

Submitted herein are Long Island Lighting Company comments on proposed Revision 2 to Regulatory Guide 1.97. These comments are in reply to your letter to Mr. Andrew W. Wofford, dated November 23, 1979, and subsequent requests resulting from the December 14, 1979 meeting with the NRC and near-term OL BWR Owners.

Our review of che proposed revision, and draft standard ANS 4.5 upon whicn it is based, confirms our observation that this is a _omplex issue. We recognize the motivations which led to the proposed revision and believe that many of these concerns have been, or can be, addressed in the Shoreham design. However, a more comprehensive evaluation of the proposed revision, as well as the technical basis of ANS 4.5, will be required to establish our optimum program for implementation.

Nevertheless, we have prepared a fairly detailed assessment of the current Shoreham design (Attachment 1) which we believe will be helpful to you in evaluating both the adequacy of the current design and the impact of full imple-mentation of the presently proposed revision. We have also stated several comments which we believe to be both signifi-cant and generic, and which should be addressed in the subsequent revision. Finally, we have indicated a number of suggested changes to the proposed revision (Attachment 2) which would be useful in " tailoring" the guide to plant- (

specific designs such as Shoreham should separate tables be provided for the various classes of plants.

gg 1866.346

,,, 80020405 7 2_

Mr. Steven A. Varga January 30,1980 Re: Comments on Proposed Revision Page 2 to Regulatory Guide 1.97 The potential impact of implementing this proposed revision in the present form on plants such as Shoreham is substantial. We estimate the cost for full compliance with the proposed revision to be about 12 million dollars. This estimate is based on a preliminary engineering interpretation and review of the proposed revision with regard to Shoreham-specific modifications. The preliminary costs include directs, distributables, indirects, A.F.I., and escalation. It should be noted that the estimate does not reflect the costs of any delay in commercial operation of the facility, a cost which could easily dwarf the direct cost of implementation. For this reason, it is essential to recognize that implementation of the proposed revision would, in some areas, constitute a major backfit to plants such as Shoreham which are in the final phase of construction. As indicated in the accompany-ing assessment, implementation of some portions of the guide would take as long as 36 months to complete. In the case of Shoreham, we believe that timely completion of construction, and all licensing activities leading up to and including issuance of an operating license, will not preclude the future implementa*4 on of this regulatory guide. Hence, li7ensing should proceed while giving careful consideration to the actual cost / benefit of the additional instrumentation required by Revisien 2 of Regulatory Guide 1.97 and subs,equent industry /NRC developments.

The enclosed table (Attachment 1) has been structured to provide as detailed an assessment of the proposed revision to the regula-tory guide as possible in the time available. The assessment was developed by means of comparison of the current Shoreham design to the proposed regulatory guide requirements. The table demonstrates the availability of the parameters and compares the ranges with those specified in Table 3 of the proposed revision.

Also presented is a comparison of current design parameters to the criteria stated in Table 1 of the proposed revision. In addition, we have included those changes we could identify as being needed to achieve full implementation of the proposed revision, as well as the associated cost and schedule impacts.

Finally, we have identified some of the existing alternatives and provided a number of clarifying remarks. As previously stated, we believe this information is useful in both assessing current designs and identifying the impacts of the proposed revision.

While developing the detailed assessment discussed above, a number of concerns became apparent. The following comments, generic in nature, apply to many plants and are applicable to many of the variables addressed in the proposed revision.

These gen,eric comments are:

1866 347

Mr. Steven A. Varga January 30, 1980 Re: Comments on Proposed Revision Page 3 to Regulatory Guide 1.97

1. The power source to the instrumentation used to monitor a given process parameter should not be required to be of

" higher" quality than the power source to the principle components of that system. In all cases, instrument quality should be directly related to the importance to safety of the function being monitored. The design criteria in these areas must be integrated with the existing require-ments (e.g. Regulatory Guides 1.29 and 1.75).

2. Regulatory Guides 1.97 should focus on providing information for the contro; ;oom operator. Variables whose selection is motivated by concerns such as emergency planning or management assessment can be located outside the control room to minimize confusion and avoid design impact. These should be addressed in conjunction with technical support center inputs being developed in response to NUREG-0578.

3. Although the motivation for extended ranges is appar'ent, the advisability of extending each range must be assessed individua;.ly.

The goal should be to provide measurable gains in the gperator's understanding and rerponse to a transient. These modifications should be weighed in terms of their cost and benefit. Specific examples of this concern are stated in the detailed assessment table.

4. Design criteria specified by Table 1 of proposed Revision 2 include the most recent industry /NRC standards. Although this is appropriate guidance for new plants, evaluation of existing equipment and consideration of backfit installations should be based on those standards and guidelines generally applied to the safety-related design of the plant being reviewed.

5. Some research and development activity will be required for a number of the variables specified in Table 3 of the proposed revisian, as measurement of these variables has not previously been provided in plant designs. Accordingly, the uncertainties inherent in a research and development program should be considered when establishing the implementation criteria.

1866 348

Mr. Steven A. Varga January 30, 1980 Re: Comments on Proposed Revision Page 4 to Regulatory Guide 1.97 In summary, our review of Revision 2 to Regulatory Guide 1.97 addresses three points of view; a surmary of the Shoreham design which includes our initial assessment of the cost and schedule impacts of full implementation, a set of generic comments which reflect current design requirements as described aSove, and specific comments on proposed Revision 2. We

~teve the Shoreham design substantially meets the intent of the guide and trust that this information will be a positive contribution to your effort. Thank you for providing this opportunity for early comments and input.

Very truly yours, J. P. Novarro, N Project Manager Shoreham Nuclear Power Station . ,

GFD/ RAH /cc Enclosures cc: J. Higgins (NRC) 1866 349

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' 2 g 5NPSI REG i f7 EEv 2 T ABLE I CE5tCN CRITERIA

5 m 0 R E a a a t a P 4 C T

.gN T TPE RANCE tata N0 5 RANCE 14 ]$ I 3 44 $$ 5 6 Fa I$ $ T I$ ll T F CQsT 4 NE D ERNa El REmaRE5 48 TEMP E 4eT TO UPCRacE TO EmERCENCT 5 51.800,12 la no R 5 sN aN EnERCENCT Data lS avait a8tE m THE aMaLOG FORA lJB *F Ponte EXTEND RANGE. 1sfusis0N CaTa a5 tm Int CC% TROL Room FOR Rus LO=EST SE TTER aCCURaCT. UPDATED EVERT F6FTEEN TEMP. EVER RECoaDEO af 33 PT. LEVEL PR0vl0E IMDeC& TOR IN asNUTES NOReaLLY tl GT CONTROL R00s UPDATE 0 NOURLT Lo*Eli TEMP. Evf a RECORED ON LONG 15L AND IS .2a*F. af a F T. L EvgL af waCo G RtVER R ANCE TO 40*P. APPEARS UNIIEa50NASLE of W E RTICAL E UPGRADE To f aERCENCY 515.005.1218 a0 Aml en am EaERCENCY

.9f *PF TO - DATA il avatta4LE us amaLOG FORA FA TFE T r uP. P0sER. PR0vl0E IND4C&10R SITUATION DAT A 15 CONTROL RCCs FOR THE Rs5 DIFF 144 FT. IN CONTROL N00s UPDATE 0 EvtRT FIFTEEN list ERVALS maMuTEL se0RaaLLT UPOaTED le0URLT 50 PREC2PITaT10N E RECORDING UPGR ADE TO EmERCENCY l44.908,1210 so EEt1 TING TELEPHO%E L*NE FRom MET.

R AM GUaGE power. T APPtNG BUCE E T TOWER TO CCNTROL A00m CaN SE UTL8210 wiTM RaNCE GAUCE REQUIRE 0 SNSTEa0 50F FICIF M T CP WELCH :aG auCEE T TO Ensure GUAGE provide a mEaNS ACCU 4aCT FOR GE TTING 0af a FR0s OF TOTAL MET. TC=ER TO THE aCCuanu. CONTROL ROCa. P90vCE L aTMN INoICATOR SM CONTROL vlTNIN 101 ROQa !

OP RECORDED i

vaLUE J 0l

RE50LUT401s L E C D*D 6CTaTON WITWN TASLt.

D f;m} r-

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) //// <[ffjij / s/

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44. PC=ER 500RCE FC4 IN5TRumENT LOCP L. Q

48. PC=ER SOURCE FOR D15Plaf INSTRUmEMy 3. CON TINU0ul ICE N TIF IC a T ON b 5 . OUT-OF.5ERWICE INTERwaL BEFCRE ACCCENT 4 09T OF SERvlCE INTERwaL SEFCRE aCC10iMT WILL $E ADCRE55ED 4 . POR Taste IN THE TECNNICAL SPECIFICaT10NS

@ Ta. QuaLITT assoRaNCE LEvfL FOR iN5TRumENT LOCP I* COLLECTON lilTEm NOT PCRTaBLE. SamPL E mU57 SE TaREN TO Lat.

78. QuattTT asscRANCE LEVEL FOR DISPlaT INSTR'.inENT 4. TMil PAA4stTE4 e5 PR15"NTLY Bema REvaE=ic IN RESPONSE TO TPE 8 . DISPlaf TTPE REQUIREmE1T OF NuMEG-3579 TME C05T i= PACT #RE5ENTS TME A00iTONal

9. DiSPlaf hETMOO COST PROJEC1ED FCR FutL CC=PLiaNCE maTN Titt GECULaTCRT GU:0E.

. 10. UNicut ICENTirtaTION IT DOE 5 NOT ENCL g si . PERicoiC TESTING PER REG. guide i.iis De TME RE0 ENT5 aire 0F UDE TME 845E COST a550ClaTED m TN tmPLEnENTaTices NuREG45is -

A , . .

f t

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8

Attachment 2 Table 1 DESIGN CRITERIA 1 CRITERIA INSTRUMENTAT!0N TYPES 2 A B C D E

1. Seismic qualification yes yes yes no no a per Regulatory Guide 1.100

2. Single failure criteria yes yes yes no no per Regulatory Guide 1.53

3. Environmental qualification yes yes yes 4 yes no 5 -

per Regulatory Guide 1.89 - % P a e"

zouw.e rtu,m-( ME*/*" .0/*ctf &S

4. Power source Emr6 CB7 CB7 Emr6 Emr6 cc m es od wcsarw

5. Out-of-service interval 8 8 8 9 to [j[ y before accident

6. Portable no no no ll no ti no ll g , <4 o'N

7. Quality assurance level 12 12 12 12 12 ]{JJ beg 4,q,,,,,,, 2 1 u-

8. Display type 13 Cont 4 Con 14 Con 14 0D15 ,0015 %I,f/'e

9. Display method Rec 16 Rec 17 Rec 17 Indt8 Ind18,19

10. Unique identification yes yes yes no no

11. Periodic testing per yes yes yes yes no 20 Regulatory Guide 1.118 IUnless different specifications are given in this regulatory guide, the specifications in ANSI N320-1979, " Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation," apply to the high-range containment area monitors, area exposure rate monitors in other buildings, ef fluent and environmental monitors, and portable instruments for measuring radiation or radioactivity.

2 Type A - Those instruments that provide information required to take preplanned manual actions.

Type B - Those instruments that provide information to inonitor the process of accomplishing critical safety functions.

Type C - Those instruments that indicate the potential for breaching or the the actual breach of the barrie'rs to fission product release.

Type 0 - Those instruments that indicate the performance of individual safety systems.

Type E - Those instruments that provide information for use in determining the magnitudo of the release of radioactive materials and for continuously assessing such releases, for defense in depth, and for diagnosis.

3 Radiation monitors should teot the requirements of ANSI N320-1979, Section 5.14 and/or Section 9.1.15, as appropriate.

4See paragraph 6.3.6 of Draft Standard ANS-4.5.

(Footnotes continued) 9 1866 355 .

, footnotes continued for Table 1 T' Qualified to the conditions of its oneration and ,

for radiation monitors.

ANSI N320-1979.

6 Emergency power source.

y 7 Critical Instrument Bus - Class 1E Power 8 Paragraph 4.11 " Exemption," of IEEE S tandard 279-1971.

9 Based on normal Technical $peci fication requirements on out-of-service for the safety system it serves.

10

) Not necessary to include in the Technical Specifications unless specified by other requirements.

11 Radiation monitnring outside containment may be portable if so designated in Tables 2 and 3.

12 Level of quality assurance per Appendix B to 10 CFR Part 50.

13 Continuous indication or recording displays a given variable at all times; intermittent indication or recording displays a given variable periodically; on-demand indication or recording displays a given variaole only when requested.

14 Continuous display.

15 Indication on demand.

tsWhere trend or transient information is essential to planned operator actions.

17 Recording.

18 Dial or digital indication.

1SEffluent release monitors require recording, including effluent radioactivity 2 monitors, environs exposure rate monitors, and meteorology monitors.

Radiation monitors should be periodically tested in accordance with the requirements of ANSI N320-1979.

i for Sh ore lo, Ue C Yo b & l m c lr.m e d d4s (se U~,,/errfas le ca. ice .nypl y ) .u free a.

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1866 356 Ov 10

Table 3 BWR VARIABLES Measured Variaole Range Type Purpose CORE Core Emit Temperature 150'F to 2300'F 8,0 To provide incore temperature measurenents to ident 's facitizeddm 4%LM W**

Not areas. TIAccroximately @ ,j y,g 4 D*45#'**"t5 6 6 _ . ,- . ,,,. ,j Control Rod Position Full in or not 0 To provide oosition indication that the full in control ec'ds are fully inserted.

(Minimum of 2 nours after accident)

Neutron Flux 1 c/s to L% pcwer S ANS-4.5, Secticn 6.2.2.

_ . - - - - - (at least one For indication of approaci to fission counter) criticality.

4 REACTCR C*CLANT SYSTEM s

I RCS Pressure 15 osia to 8,C ANS-4.5, Secticns 6.2.3, 6.2.4,

% psig 6.3.p.and6.3.5.

q/ N 'ill*'s d, beJv sce <d j For indication of an accident and to indicate that actions must te

[a r //fu)S au,,,A taken to mitigate an event.

Coolant Level in the Bottom of core- B ANS-4.5, Secticn 6.2.3.

Reactor support plate For indication of fuel sucmergency to aoove top of for a LCCA event, discharge plenum y,g p j g g,,, e ( o f/ p t f,, d,*c p bw1I d 3

[ a uq,i/qble s'e VaIweparden end l U

,' Main Steamline Flow 0 to 120% design 3 To provice an indication of the J

~ . _ _ _ - . - - - - - - s_ [Ci _ ._ . - integrityofthepressureboundaryj Main Steamline isola- O to 15" of water a To provide an indication of the tion valves' teasage O to 5 psic pressure bour.dary and containment Controt System Pressure Primary System Safety Closed-not closed 8,0 By these measare-ents, the operator M ,f **

Relief Valve posi- or knows if there is a patn Joen 'or .

tions, inctuctag 0 to 50 psig loss of coolant and if in event '

ACS or Flow Thrcugn may oe in progress. ,, ,

or Pressure in valve ,

Lives f *, ,11

'f,j co#"'-

s

\

busign flow - tr.e maximum flow JotiCipated in normal Operation.

21 1866-357 .

2_ i1 . ' -' w v 1m- -. mz mm .w - - -

s'- u

TaDie 3 (Continued)

Measured Variable Range Type Purcose REACTOR CCOLANT SYSTEM f (Continued) hq,rg e 7 40" 'g 4i f pyd on dcKeer18 V

Radiation Level in (!0 pCi/cc to) C ANS-4.5, Section 6.3.2.

Coolant t,10 Ci/cc _/ For early indication of fuei Cladding failure and estimate of extent of damage.

CCNTAIhMENT Primary Containment 10 psia pressure B,C ANS-a.5, Sections 6.2.5. 6.3.3, Pressure to 3 times design 6.3.4, and 6.3.5.

pressure: for con- For indication of the integrity crete; 4 times of tne primary contain-ent oressure design pressure boundary; to indicate the potential f;,g g g for steel for leakage from the contain: ent.

/

- @ ntainment and Cry *11 0 to 10% B,C ANS-4.5, Sections 6.2.5 and 6.3.5.

Hydrogen Corcentration (capability of for indication of the eded for and operating from a measurement of the performarce 12 psia to maxi- of the containment hycrogen recom-mum design pressure2 )

biner and to werify tre coeration of ,f the miting system.

V

/

via se// .

Cintainmen) and Cry-ell 0 to IC% B,C For indication of tne need for and a Oxygen Concentration (capability of measurement of the performarce of (for those olants coerating from the containunt ouygen elicunation

.ith inerted 12 psia to system.

containments) design pressure:)

.h Primary Contairment Closed-not closed B,D ANS-4.5, Section 6.2.5. *"P .

Isolation valve To indicate the status of centairrect F'",E Position , isolation and to provice infermition , " ' 1 ;,

j E om /ow,-J/ Ed, C S p., , p b O'C on the status of valves in process lines that could :arrv riaicactive 4-c r- '}* _ ,./,

materals out of conta'inment. >"

lf.n#"'

u orme <I , , . ,

-,~

Suppression Pool fiop of vent ton 3 ANS-4.5, Section 5.3.3.

water Level ~~ h tooofweir.w.e.l.l)

Suppression Pool 50'F to 250*F S To ensure proper temcersture for

'.ater temperature NP5H of ECCS. To serify tne iera-tion of tre ,aseuo system.

/

3rysell Pressure 12 psia to 1 osig " 3 AN5-4.5 5ccticn i.3.3.

'y 0 to I W,aesig, E Diagrnsis of me ic t af accicent on pressure crywell structure.

~

\ ..

?

fl1iS 95 s J t avy c. Q,f _p, ,m ( . ., [_ ,,, ,, p. y y ,, (

Ce* i p .: re s s ura - t*at v t ; ut corresponding ta 15'iE ce;e valu n :nat are obtairec at or celaw coce 31:a.ac t e Nterial lesign ,tras5 v a l uta s .

= 1866 358

~

_m

I

'a f Table 3 (Continued)

Measured Variaole Range Type Purpose Y '# # f#7 ##

CONTAINMENT M/A 'So h h m dbr m a wa dm l.

(Continued) 9n d w ifl b e d* h Y' S b/ C** 4D"

, 1 Orain Sumos Bottom to top B,C ANS-4.5 Se: tion 6.3.3.

Level (Icentifiec and Unidentified - ---

Leakage) _ _ . . . . - - - - "

- High-Range Contain- 1 to 107 R/hr 8,C To help icentify if an accident ment Area Radiation (60 key to 3 MeV has cegradec ceyond calculated photons with :20% values and to iadicate its accaracy for cho- magnituce i.1 orcs to determine tens of 0.1 to action to protect t. auolic.

3 Mev) [107 R/hr for pnotons is approximately equivalent to 8/'d" [(f2 [" Y 108 rads /hr huf ri L g

for betas and 3liorfb t" u g E" * *l / '

/dl # " g/

de 4' A/ ar t T

b i

PC'aER CCNVERSICN SYSTEMS

\'jer#

78 f

y .3, b#gA .

D ~ \ yhe-

._L~

. '4ain Feeawater Flow 0 to 1107. design E To indicate an adecuate source of flown water to tre reactor.

E a.*. ' s A2d .

. nsse.1 o n M t ussMe Condensate Storage (Sottchtotoo duiae yof g,c6,'u

~ de 4au # To r indicate available water for Tant Level core cooling.

/ea/

Aux!LIARf SYSTEMS g4 , y , ,, p g A [gg 7fg Containment Soray 0 to 110% cesign D ,

For indicatica of system operation.'i Flow flowl _ __, -

[5 tea 9 Flow to RCIC 0 to 11C% design E To verity trat acecuate stesa is flown availsole for t9e systa, to

'_/ rerform its function.

-Oeie le - Rc c yny //.< is a.ma anc,Cr wee.+as a c ,e e,s. e,s,-, .

0 to llc % design 0 For indication of system coeration.

RCIC Flow flown M System Flow 0 to 110% :r<.ign 0 for inoication of system eLeration.

flown 4H4 Heat Eacnarger 32*F to 350'F 3 For indication of system 0ceration.

Cutlet Temperatura 32*F to CCO*F 0 For indicat i on or system acecation.

4/ Service Cooling dater Teteerstore 1866 359 ,

0 Table 3 (Continued)

Measured VariaDie Range Type Purpose AU4!LIARY SYSTEMS (Continued)

Service Cooling 0 to 117% design 0 For indication of system operation.

Water Flow flowl

' Flow in Ultimate O to 11C% design 0 For indication of system caeration. 5""~ 's Heat Sink Loop flowl * ' ".r f. "'

-s *

. , , . e Temperature in Ulti-

. . c/o s.* J 30'F to ISO'F 0 For indication of system operaticn. '.

mate Heat Sinn, Loop

, ' 2 f' .'.# # 's, ,'

\ , , - * -c ultinate Heat Sink Plant specific 0 Toensureaceouatesourceofcool-/

glevel ing water.

SLCS Storage Tank Bottom to top E To provide indication of inventory Level for boron i.1jection for snutcown.

Sump Level in Spaces To corresponoing 0 To monitor potential for' failure of of Eoui nent Aequirea level of safety equipment in closed s aces cue to g

for Safety equipment failure flooding. ,

RAC'aASTE SYSTEMS High Ractoactivity Top to bottom E Available volume to store crimary Licuid Tank Level coolant.

Charcoal Delay Gas As recuired E To monitor performance of system.

Systes Gas Flow -

Radioactivity Level VENTILATIC'i SYSTEMS E**/4 hon

( r?raefor %2m K*a rg e ncy Venti 14t @ Coen-closed status 0 To ensure procer senti!ation uncer Camper Acsition accicent coaditions,

. y h o.e 50 b *- bfY Temperature of Space 30*F to 130'F To monitor environt ental conditions in' Vicinity of fouto- of equipment in closed scaces.

ment Required for Safety PC' ER st/%IES Status of Class 1E voltages and 0 to ensure an w ouate scuece of Power Sucolies and currents electric pc.ee for safet, systems.

Systems Status of Non-Class

E Po.ee Sucoltes Voltages 2nd currents t h

"\

To 19JiC3te m aceQu3te source of electric ;;*er.

(- .

anc Systems

$erms Q n trasona bN Y N$ ""

' ZGpe~ u b a fg

. . _ - - _ - = . _ _ _

J Taole 3 (Continuea)

Measured Variable Range Type Purpose e

8A !ATION EVPOSURE 8A*E5 INSICE 'ulLO!NGS C4 14E45 waERE ACCESS 15 *E;JIRED 'O SE4v!CE SaFEif-RELATED EG'JIP-YENT .

Raciation Exposure 10-8 to 10' R/hr E For neasure-ent of nigh-rsoge Rates fo'r pnotons raciation escosure rates at various locations.

(permanently installed moni-tors)

AI:E:t%EAD*Co TIVE .n AjuS IE.coe O= -

wa?IslALS RELEASE 3 cvsf^

F;;M THE PLANT (c e [//L!#

Effluent 4acicactiv- (Normal plus E ANS-4.5. Secticn 6.2.6 ity - NcDie Geses accicent range To provice operator ni(n informa-for noble gas tion regarcing release of racio-active ncole gas on a continuous

,,ym

'T . Containment , 10*' to 05 wCl/cc basis, f Enniust vent and Xe-133 ca ibration

'- ' Stancey Oas .

Provisions should be mace to monitor all Treatsert System potential path.ays for release of gaseous Vent radicac*ive materials to tre ea vir:ns in c:nformarce witn General :esign Critcrion 64

.Ctrer Release 10*' to 102 pCi/cc Note: Menitoring of incivic2il ef'Ivent Foints (includtag Ae-133 calibration strea s only is recaired -nere such streams are released directly to fuel naaoling cuilcing, aunili- (permanently tr.e environment. If t-o or more ary tuilcing and installed moni- streams are cc-oined orier to release tro, a ccm on discnarge turoine tuiloing) tors) point, monitoring af the CCroir.ed strea, is censicered to eet tre intent of tnis quice = rov'ceo Soca monitoring has a rance acequate to measure worst-case releases.

10-2 to 102 pct /cc To provice the crerator itn Effluent Racioactiv- E infornition regarding release of ity - Mi;n-44nge ,

Radicaalcgens ano '(p e r9anen tl y racicactive n11c(ens and carticu-Particulates installed mont- lates. Continuous collection of tors) representative sa Dies followed by conttoring (neasurerents) of sa* oles fcr raulohilogens and 'Or carticulates.

1- 1866 36F .

25

.eaegwe i eW

ML19257D538

Text

Dear Mr. Varga:

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