ML20005B479: Difference between revisions
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Y SEACTC4 C*CtANf 515f M I | Y SEACTC4 C*CtANf 515f M I | ||
RC5 Pressure 25 sia to 8.C ANS-4.5. Sectien: 6. 2. 3. 6. 2. 4 w.;sig 6.3.3, a o f.3.5. | RC5 Pressure 25 sia to 8.C ANS-4.5. Sectien: 6. 2. 3. 6. 2. 4 w.;sig 6.3.3, a o f.3.5. | ||
15'00 - 14. .s ,d b e .s y | 15'00 - 14. .s ,d b e .s y ((,r*. | ||
e For freicatica of an accicent end to inoica*e tsat ac*to.s *6st ce | e For freicatica of an accicent end to inoica*e tsat ac*to.s *6st ce | ||
[e r /7fWf cy,,,,f taaen to mitigate a' vent. | [e r /7fWf cy,,,,f taaen to mitigate a' vent. | ||
Latest revision as of 14:01, 15 March 2020
| ML20005B479 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/29/1981 |
| From: | Earley A, Reveley W HUNTON & WILLIAMS, LONG ISLAND LIGHTING CO. |
| To: | SHOREHAM OPPONENTS COALITION |
| References | |
| NUDOCS 8107080279 | |
| Download: ML20005B479 (6) | |
Text
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UNITED STATES OF AMERICA 4jffy 'f*bOf a 3 1- 9 NUCLEAR REGULATORY COMMISSION (1r %[qg w
\/ ec'( e y Before the Atomic Safety and Licensing Board h s
//dl'N In the Matter of )
) -E LONG ISLAND LIGHTING COMPANY Docket No. 50-322 [\\*riTp;k, (Shoreham Nuclear Power Station, ) /b \
Unit 1) ) ld - ) C .4 O. k LONG ISLAND LIGHTING COMPANY'S RESPONSE TO SOC'S JUNE 9 INTERROGATORIES - fk # D
,N f AND REQUESTS FOR PRODUCTION OF DOCUMENTS 4/
7 A LILCO will not satisfy all of the Shoreham Opponents Coalition requests, dated June 9, 1981, because they ser-iously disregard pertinent rules of practice. 50C Questions and Document Demands Nos. 1-6 and 8
- 1. Items 1-6 and 8, which implicitly make hundreds of requests, are objectionable because they concern a matter about which SOC has no contention admitted in this proceeding, that is, LILCO's compliance with the NRC's TMI requirements.
Until such time as SOC submits at least one particularized contention to the Board and the Board admits it under 10 CFR S 2.714, there is no basis for discovery concerning the matter. See, eg ., Allied-General Nuclear Serv. (Barnwell Fuel Receiving and Storage Station), LBP-77-13, 5 NRC 489, 492 (1977), which held: g
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.PDR ADOCK 05000322
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. . . . 10 CFR S 2.740(b)(1) only permits discovery of information or documents "rele-vant to the subj ect matter involved in the proceeding," and then further qualifies and limits the term "subj ect matter" to the con-tentions admitted by the presiding officer in the proceeding . . .
See also Northern States Power Co. (Prairie Island Nuclear Generating Plant, Units 1 and 2), ALAB-107, 6 AEC 188, 192, aff'd, CLI-73-12, 6 AEC 241 (1973) (petitioner is not entitled to discovery to assist in framing contentions).
- 2. Further, and equally debilitating, SOC items 1-6 and 8 are obj ectionable because they are too sweeping. They ask indiscriminately for documents related to LILCO's compliance with TMI requirements. As such they constituca a " fishing ex-pedition" rather than focused inquiry about discrete issues.
The rules do not tolerate such unfocused, burdensome requests:
"In no event should the parties be permitted to use discovery procedures to conduct a ' fishing expedition' . . . ." 10 CFR Part 2, App. A at IV(a) (1980). See also, e.g., Illinois Power Co. (Clinton Power Station, Unit Nos. 1 and 2), ALAB-340, 4 NRC 27, 34 (1976):
In this connection, Professor Moore has ob-served that "[a] blanket request for pro-duction of all ' books, documents, papers and records which are relevant and relate to the subject matter of [an] examination . . .' is obviously without merit." __ . _ - . . _. . _ . . ~ _ _ . _ ._ ~ . _ . _ _ _ _ _ _ . . _ _ , . _ _ _ _ . , _ . _ - . . _ _ _ . -._
- 3. LILCO has already sent to SOC 3-1/4 inches of documents describing the Company's compliance with the NRC's TMI requirements. See letter from Charles A. Daverio to Stephen B. Latham, dated June 17, 1981, with attached docu-ments SNRC-557, 563, 568 and 579. This material will become part of the FSAR. Taking into account these SNRC's and the Commission's TMI requirements, SOC can shape a proposed TMI contention or contentions to which other parties can reply and on which the Board can rule. If and when such contention (s) are admitted, ten there may be an occasion for properly focused discovery concerning them.
SOC Document Demand No. 7
- 4. This request does concern an admitted SOC contention.
It falls afoul, however, of the " fishing expedition" pro-hibition noted in paragraph 2 above. The request is for "all correspondence and documents between LILCO and the NRJ related to the requirements in Regulatory Guide 1.97, Revision 2." Despite the fact that this request is overbroad, the Company will answer it. Attached is the only pertinent LILCO com-munication to the Commission: the Company's January 30, 1980 comments (SNRC-460) on the Staff's proposed Revision 2. Per-tinent NRC communications to LILCO have concerned the development of that revision and been generic in nature. They are a matter of public record. LILCO's willingness to satisfy this overbroad
~
document demand does not mean that the Company will reply to similarly flawed requests in the future. Respectfully sabmitted, O W. Tay1
/WReveley, III Anthony . Earley, Jr.
Hunton & Williams P. O. Box 1535
- 707 East Main Street Richmond, Virginia 23212 DATED
- June 29, 1981 i
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In the Matter of LONG ISLAND LIGHTING COMPANY (Shoreham Nuclear Power Station, Unit 1) Docket No. 50-322 CERTIFICATE OF SERVICE I hereby certify that copies of Applicant's Response to SOC's June 9 Interrogatories and Requests for Production of Documents were served upon the following by first-class mail, postage prepaid, on June 29, 1981: Louis J. Carter, Esq. Jeffrey C. Cohen, Esq. Administrative Judge New York State Energy Office 23 Wiltshire Road Swan Street Building, Core 1 ' Philadelphia, Pennsylvania 19153 Empire State Plaza Dr. Oscar H. Paris Administrative Judge r Jay Dunkleberger M'. Atomic Safety and Licensing New York State Energy Office Board Panel Agency Building 2 U. S. Nuclear Regulatory Commission Empire State Plaza Washington, D.C. 20555 Albany, New York 12223 Mr. Frederick J. Shon Howard L. Blau, Esq. Administrative Judge 217 Newbridge Road Atomic Safety and Licensing Hicksville, New York 11801 Board Panel U. S. Nuclear Regulatory Commission Ralph Shapiro, Esq. Washington, D.C. 20555 Cammer and Shapiro, P.C. 9 East 40th Street Secretary of the Commission New York, New York 10016 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 David J. Gilmartin, Esq. Attn: Patricit A. Dempsey, Esq. Atomic Safety and Licensing County Attorney Appeal Board Panel Suffolk County Department U. S. Nuclear Regulatory Commission of Law Washington, D.C. 20555 Veterans Memorial Highway . Hauppauge, New York 11787 Atomic Safety and Licensing Board Panel Mr. Marc W. Goldsmith U. S. Nuclear Regulatory Commission Energy Research Group, Inc. Washington, D.C. 20555 400-1 Totten Pond Foad Waltham, Massachusetts 02154 Bernard M. Bordenick, Esq. U. S. Nuclear Regulatory Commission Washington, D.C. 20555 4
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Stephen B. Latham, Esq. MHB Technical Associates Twomey, Latham & Schmitt 1723 Hamilton Avenue 33 West Second Street Suite K P. O. Box 398 San Jose, California 95125 Riverhead, New York 11901
/
W. Taflog Revdley, III Hunton (/ Williams 707 East Main Street P. O. Box 1535 Richmond, Virginia 23212 Dated: June 29, 1981
e br LONG ISLAND LIGHTING COM PANY h,P)h sHOREHAM NUCLEAR POWER STATION
, ,, ,, P O. BCX 618. NORTH GOUNTRY ROAD e WADING RIVER. N.Y.11792 January 30;.1980 SNRC-460 4N\
Mr. Steven A. Varga, Chief g Light Water Reactors, Branch 4 / Doeg 70 %g D. vision of Nuclear Reactor Regulation k 9-Mr 3 h2 U. S. Nuclear Regulatory Commission JUL y ;gg, , Kashington, D. C. 20555 g off7c y
\g Coac:Q e*tym f.E ' ""3 8 Shoreham Nuclear Power Station - Unit 1 D Docket No. 50-322 o, P
Dear Mr. Varga:
Submitted herein are Long Island Lighting Company comments on prop'osed Revision 2 to Regulatory Guide 1.97. These cor:nents are in reply to your letter to ::r. Andrew W. Wofford, dated November 23, 1979, and subsequent requests resulting from the December 14, 1979 meet.tng with the NRC and near-term CL BWR Owners. Our review of the proposed revision, and draft standard ANS 4.5 upon which it is based, confirms our observation that this is a complex issue. We recognize the motivations uhich led to the proposed revision and believe that n.any of these concerns have been, or can be, addressed in the Shoreham design. Houever, a more comprehensive evaluation of the proposed revision, as well as the technical basis of ANS 4.5, .<ill be required to establish our optimum program for inplcmentation. Nevertheless, we have prepared a fairly detailed assessment of the current Shoreham design (Attachment 1) which we i believe will be helpful to you in evaluating both the l adequacy of the current design and the impact of full imple-n.catation 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 l of suggested changes to the proposed revision (Attachment 2) which would be useful in " tailoring" the guide to plant-Si 'r.cific designs such as shoreham should separate tables he pavided for the various classes of plants. av h4,9 l ,. ih' . r su ecem
I 9
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January 30,1980 Mr. S;even A. Varga Page 2 Re: Cc~ments on Proposed Revision to Regulatory Guide 1.97 . The potent'ial impact of implementing this proposed revistan in We form on plants such as Shoreham is substanti;.. the present for full compliance with the propcsed revision estimate the cost This estimate is based on a to be about 12 million dollars. preliminary engineering interpretation and review of the proposed The revision with regard to Shoreham-specific modifications. indirects, preliminary costs include directs, distributables,It should be noted that the es A.F.I., and escalation. i
-does not reflect the costs of any delay in commercial operat on of the facility, a cost which could easily dwarf the direct costis essential to recog For this reason, it of that implementation. implementation of the proposed revision would, in some area constitute a major backfit to plants such Asas Shoreham indicated which in the are accompany-in ingthe final phase of construction. implementation assessment, In the caseof some portions of the gu of Shoreham, take as long as 36 months to complete.
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 licensing shouldimplementation proceed while of this regulatory guide. Hence, giving careful consideration to the actual cost / benefit o Guide 1.97 and subsequent industry /NRC developments. (Attachment 1) has been structured to provide
- The enclosed tableas detailed an assessment of theThe proposed revision to the re assessment tory guide as possibic in the time available.
was developed by means of comparison of the current Shoreham The table design to the proposed regulatory guide requirements. demon ranges with those specified in Tabla 3 of the proposed revision. Also presented is a comparison of current design parameters In to the criteria stated in Table 1 of the proposed revision. 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 As alternatives previously and provided a number of clarifying remarks. stated, we believe current designs and identifying the impacts of the proposed revision. a While developing the detailed assessment Thediscussed above, following comments, number of concerns became apparent. apply to many plants and are applicabl generic in nature,to many of the variables addressed in the proposed revision. These generic comments are: 1 e
. January 30, 1980 Mr. Steven A. Varga Page 3 Re: Comments on Proposed Revision
- 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 toThe design criteria safety of the function being. monitored.in these areas must be inte ments (e.g. Regulatory Guides 1.29 and 1.75) .
- 2. Regulatory Guides 1.97 should focus on providing informationVariable for the control room operator.
motivated by concerns such as emergency planning or management assessment can be located outsideThese the control shouldroom to minimize be addressed confusion and avoid design impact. in conjunction with technical support center inputs being developed in r'esponse to NUREG-0578. the 3. Although the motivation for extended ranges is apparent, a The goal should be to provide meas:trable gains in the operator's understanding and response to a transient. These modifications Specific should be weighed in terms of their cost and benefit. exmmples of this concern are stated in the detailed assessment . table.
- 4. Design criteria specified by Table 1 of proposed Revision Although 2 include the most recent industry /NRC standards.
this is appropriate guidance for new plants, evaluation of installations existing equipment and consideration of backfit 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 of these in Table 3has variables of the notproposed previously revision, as measurement Accordingly, the uncertainties been provided in plant designs.
inherent in a research and development program should be considered when establishing the implementation criteria.
i . . , I
.e ,,
January 30, 1980 Page 4 Mr. Re: Steven A. VargaComments on Proposed Revision to Regulatory Guide 1.97 In summary, our review of Revision 2 to Regulatory a summary Guide 1.97 of the Shoreham addresses three points of view; design which includes our initial astessment n, a set of of thegeneric cost and schedule impacts of full implementat, comments which reflect current design requirements asWedescribed above, and specific comments on proposed Revision 2. believe the Shoreham design substantially meets the intent of the guide and trust that this information Thank will be a this you for providing positive contribution to your effort. opportunity for early comments and input. Very truly yours,
- ?3 -
.\
/ ) .) g*! % > W J. P. Novarro,
Project Manager Shoreham Nuclear Power Station GFD/ RAH /cc .
Enclosures cc: J. Higgins (NRC) t l l i e l ' l ( ', j . L
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Attach:nent 2 Table 1 . 1 DESIGN CRITERIA a '.' CRITERIA INSTRUMENT AT!N TYPES 2 A B C D E yes yes yes no no 3
- 1. Seismic qualificatior, per Regulatory Guide 1.100 yes yes yes no no
- 2. Single failure criteria per Re~gulatory Guice 1.53 no 5 Environmental qualification yes yes yes* yes
- 3. j".{
per Regulatory Guide 1.89 m~~ :.-n. Emr6 c.:- o : N Emr' C8 7 CB7 Emr6
- 4. Power source n c cis :
a s v 10 e w e r. r - s g,. , ,, w ,
, 5. Out-of-service interval ,
before accident no!! no 32 no 23
- 6. Portable no no 9 "y m .- , e 22 22 in 22 12 gg ,,. g.
- 7. Quality assurance level , .,
t3 Con 24 Con 14 Con 24 OD15 ODIS "$'la , g -
- 8. Display type Rec 1G Rec 17 Rec 17 Ind i s Ind25,19
- 9. Display method yes yes yes no no
- 10. Unique identification Periodic testing per yes yes yes yes no 0
- 11. -
Regulatory Guide 1.118 , IUnless oifft: rent s;;ecifications are given in this regula .ory guice, t.te specifications in A.'GI N320-1979, " Performance Specifications for Reac:ce Emergency Radicicgical Manitoring Instrt. entation," apply to the hign-rsn;c containment area monitors, area exposure rate monitors in other cuildings, effluent and environmental monitcrs, and portable instruments for measurirg radiation or radicactivity. 2 Type A - Those instruments that provide information required to take preplanned manual actions. Type B - Those instruments that provide information to monitor the process of accomplishing critical safety functions. Type C - 1 hose instrt.ments that indicate the potential for breaching or the the actual breacn of the barrie'rs to fission product release. Type 0 - Those instruments that incicate the performance of individual safety systems. Type E - Those instruments that provide informatien for use in determining the magnituda of the release of radioactive materials and for continuously assessing such releases, for defense in depth, and for diagnosis. 3 Radiation monitors should reet the requirements of ANSI N320-1979, Section 5.14
/ and/or Section 9.1.15, as appropriate.
. 45ee paragraph 6.3.6 of Draft Standard AN5-4.5.
(Footnotes continued) O 9
. 7Qualifict! to the conditicns of its op2 ration and, fCr radiation monitors.
' ' ANSI N320-1979.
GEnergency po cr source. . g.[(7CriticalInstrunentBus-Class 1EPower '
. sParac,raph 4.11. " Exemption," of IEEE Standard 279-1971.
OBased on normal Technical Specification requirem,ents on out-of service for the safety system it serves soNot necessary to include in the Technical Specifications unless specified by other require ents. 11 Radiation monitoring outside containment may be portable if so designated 7 in Tables 2 and 3. . 12 Level of :;uality 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 varia01e only when req:.,ested.
** Continuous display.
! 15 Indication on cemand. .
! 15Where trend or trantient information is essential to planned operator acticns.
17Recorcing. isDial or digital indication. 18 Effluent release conitors require recording, including ef. fluent radicactivity monitors, environs e/.posure rate monitors, and meteorolcgy monitors, l roRadiation monitors should be periodically tested in a:..ordance with the 1 requit ants of ANSI N320-1979. for D.Cech ,, //c I
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Tante .3 SWR VAR!ABt[5 Measured Variante Range Type Purpose CORE Core Emit Tetserature 150*F to 2JCC'F B.C To provice locare te cera*.ure gg , eessure ents t2 it=* *> b:tlitec . no t a r e a s . fD:: r: s i a t e l y Q ' jf. ",' .],{* (reasureents)J - ch.e y c g er. Control Rod Positio.- Full > , or not 0 To provice essition incication tnat tr.e full in control rics are f ul'y insectee. (Minina of 2 reurs af ter ac;tcent) I g Neutron Flus 1 c/s to 1* ce=er S AN5 4.5. Sectica 6.2.2. g
# (at least cae for incication of a:;roaca to fission counter) criticality.
Y SEACTC4 C*CtANf 515f M I RC5 Pressure 25 sia to 8.C ANS-4.5. Sectien: 6. 2. 3. 6. 2. 4 w.;sig 6.3.3, a o f.3.5. 15'00 - 14. .s ,d b e .s y ((,r*. e For freicatica of an accicent end to inoica*e tsat ac*to.s *6st ce [e r /7fWf cy,,,,f taaen to mitigate a' vent. Coolant Level in the Bottes of core- 8 ANS 4.5. Secticn 6.2.3. . Reactor support plate For insicatism of fuel 56:~er;emey to acose tes of for a LC*A e.ent. discharge plenum g, g , 7 g,, e 4 o p, f r y d,*c e /,m f [f {.Meik h k..ld Yo ly e fo'byd l C ' Main Steanitre Flow 0 to 12C* cesign 8 To provice an insication of te a ficw n. integrit-,
.f the prensweeteu-cacyj Main Steamline !sota- O to 15" of water a To proeice an insication of te tion valves' tesaa;e 0 to 5 psia pressure cowacary anc containeent Control System Pressure , ,
Primary Syste9 Safety Closed-not closed 8.D By these *easare ents tne cotestor Y Relief Valve post- or kno.s if trere is a cat's seen *ar , . . ,; , . , tions, inciumiag 0 to 50 psig loss of costant a s if an event .,5 A05 or Flo Threwgi may be in progre;s. g ,e j ie ~ er Pressure.in valve . Lines - (*
- 8 ' , te cs .
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- 21
~
- Tatic 3 (Conti.nwec)
Purpose Measured varia:le Aange Tyg.e REACT 04 CCOLANT $YST[M (Continwec) 24.s$f N8" fj # f upd on docc hl0 Radiation Level in i/cc t C AN5*4.$, 5tCtion 6 3.2. Coolant . (10Ci/cc For early te:Mation of f 6el clad:teg failure ans esticate of . eatent of ca a;e. CONTA N INT Prirary Containtent 10 psia pressure 8,0 AN5 a.$, Se:tio*s 6. I. 5, 6. 3. 3 Pre s su 'e to 3 tir.es cesign 6.3.4, as: 6.3.5. pressure: for cca- For indicati:n of tre iet g rity crete: 4 ti es of the pet arj ::ntair er.t serssw ee e design C etsare tow.cary; to tr:'este t** ::tv-tial fp fg for steel for leasa;e from t.e contair ent.
- M a h tj aac ~ry.*11 0 to 10% 8,C ANS 4.5, Se:tf:rs f.2.5 aac i.3.5.
for incteat un of t e *ee: far sea Mycrogen C:ncentration (caseDility of operatics frc, a resswee ent of t.e :erf:e a :e of the certai- c-t N :r:;en e::-.- 12 psia to mazi-eum cesico biner and to .erify t e c:eratica of
/"
pressures ) the mining systen. \. Gle t well
/Te~n
't7t D arc Orywell 0 to IC% 8,C For indicatic' of t*e reed fo- a-3 a Caygen Co :entration (capaoility of eesswre eat at t e :e ':*-ar:e sf the contairrent osygen etisisat:an (for these clanti ccerating frc, system.
with inertes 12 psia to containecnts) c sign pressure:) Pritary Contairment Closed-not Cicsec 6.D ANS 4.5. Section 6.2.5. * " ' . "" ."#" .
! solation valve To ircicate tse status of ec-taie ert r- ' .
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A.NS-4.5, Section 6.3.3. Js t '! ! Suppression 8 col Top or sent to ' E
~'~~~
Water Level _topof*cirme,II.) e To ensure prece- te-ceritura for Suppression Pool 50'F to 250*F B Water Ter.;eratw ee hP5M of ICCS. To verifj the :cera-tion of tr.e mJaewo system. Orywell Pressure 12 psta to 3 as M 3' AN5-4.5 Secticn o.3.3. N ( O to 110* Jesign E Diagensis of &pict of acetcent on ) arywell structure. pressure: __-j ( N'Ia Ic - rh1r is & s t .., e. a.r p.,,,,,y u..,f...;..,,,f f,, yg
,,,,,.u 4 g ,,
- (
30esirn gressur e - tnat value corresponding (J ASM( Coje waIwfs inJL Jre S3taieed at or Delww Code-sils.JDie asterial design strass values. 22 l l
., e ' .
e
,4g. (,
Table 3 (Continued) Range Type Purpose Measured Variante
" * ** 'l CON 1 Alt."treT & T An d wj// be stolt lfd b crabo / s.e anl 43ol<lskn dlltr we acco'e4nl, (Continued) 1 Crain Su-os Bottoe to tcp S.C AN5 4.5. Section 6.3.J.
Level (Icentifiec pandUnicentified e..a e) High-Range CJeta69- 1 to 10' R/hr B.C To tel: Icentiff if an at:icent sent Area Ractatten (60 kev to 3 "el has Cegra.*d: ceyon2 calcJlatec
- photons witn :2;% values arc to ircicate its accura:y for ono- mag,ituce in creer to cete mice tons of 0.1 to actica to protect tne ;walie.
3 Hev) (13' R/hr for pmatens is apprcatrate;y / ecoisaient to dind" l* fl f# 10' ra:s/hr / ./ I ## #' -g
,,, d C #
for Detas and j , j[ior/ *** j
'*~' /
,aser a j,,f',sff**
j o e!' yeos ' b'<n - re.tR C:w t;5::n # ', .h 't' e !""' , er f/ f 5f 5T E." 5 c\ l'ho' y b e m g
ain Feec.ater F:ow 0 to 11Ci cesign E w f _o se:icate an a:e:.*te scu rce of fic ,8 =ater to tre rea:ter.
~. _
3 . +* . 2~..oe9
.~ w e
,t
. tea.se,) o a &A e wJef.,le e ,4 r.~e 4.s,.,' c To incicate available water for
. Condensate Stora;e Tant Level
@" tte-t to tcp v4/
. io. vic g,cw f.,, core c:oling.
e lewe/ Aux!LIARf 5f 5t!"5 2 //M [/rd,,, 7~/ew l',, _
,f g fg . g,, c ,, ,
Il Containeent Scray 0 to 110% cesign D , For tecicaticn of syste,c;eration,. t rio, fio.i -- '6. % Steen Flc to C IC 0 to 11 *. cesign [ To .ert ry t at nec. ate steam is ; il flow 8 availsole for tne syste, ta l- m
- e e r: , . t s *.-e *. n , .
t
? *
-Dele / c . tc :c . :p i'/.
f is a. -ces a na.c.a. we.,e n.z., 6 ,, ,.,- ,,,,,,a,,., . O to 11C*. design 0 for indication of system c eration. 1
- RCIC Flow flour 8 f
l BHR Systen Flow 0 to 110% de.lgn e 0 for inoication of system everstio.- flowl l p
^
RMR Heat tien.seqer 32*F to 350*F D For indit.ation of system ocerJtion. h Odtlet femcerature OO* Service Cooltag 32'F to 200*F 0 for incicat*on of aste s oeveJtiv afJtcr Tv peratwee ( b
e
, e C
Table 3 (Continwed) Messered Variable tange Ty pe
- Purpose AutILI4Rf S;5ftw$ .,/ ---
(Contin.ee)
- Service Cooling 0 to 1 C* cesign D For indication of systes cceraticn.
Water Flow flow' Flo, in Ultieste o to 11C: cesign D For indication of systes operation. N ' ~~ ' Meat Sink Laco fle.' **i . g.,, ;, . s . - s
- . e.k : =
Teeperature in Ulti- 37'T to 153*F G . eate Vest Stet L:cc For indication of systes operatica. \ Mf ; ** Sy: c.-C Ultimate Heat Sint flant specific *O Toensureacecatesourceof: col-/ (Level *ing water. 5LCS Stora;e Tant Sotto. to tep E To provice ircicatio,cf fraest:ry Level for toron injectics for sr.vt::.n. Svan Level de foa:es To corresscrefes 3 To coniter potential 'or fail.*e of ,.. of Ecaf: eat t'sut ec te,el of safety envio ent in cteses s: aces ne to [\ for Safety I fautp ent failure ficoding.
, s RAc.ASTE SYSTEN Migh Racioactiety Top to bottcm E Availaole voice to store priaary Liquid Tank Level coolant.
- t Charcoal Celay Gas As recuired E To ronitor performance of syste'.
Systes "as Flo. er Radicactivity Ledel l VEftTILATION SYSTE*5 l , Reac h e a'n;2.eg &c/4 /wn E'-~erge ncy _.ca t a t e t ?) Caen-c1csed stati,s 0 To ensure 'r::e venti'atica .n=er Ca per icsation acticent c.aditions.
,3 J,o Id b e + tie P Te+rerature of Soace JC*F to 130*F To conitor e vtror ental cenettia-s in Vicintty of icwic- of equigeent in closeJ Scaces.
bent Recuired for Safety . Nutt SUPPLIES Itatus of Class ;! yoltages and 0 To ensure an aJeQuate source of Po6er Sa:pties and currents
electric po.ee for sarety s.s s te,s.
ly s te.ss 1 5tates of Non ClJss Voltages and h To inJICJte Ji aceduste sou*ce Jf IE Poeer Swcaties currer.c
- ~
s electric c =er. and Syste.s S u nst knttw n 64 N I*ff"' % e U 1f*pc-a b a s.a.,, .C f ryn' 'm
v
..' ., *a *
- 5 m
, = .
a
. Table 3 (Continweg)
Features % vaDie Range Type purpeg, o s:3 tai!0% ItP;5stt C;;Il %$!*E tu:L;!% 5 C4 at!4! waii! A*:!$5 15 4!*>it!3 'O Siiv!CI
- 52rg;e.ag;A;g3 gr.stp.
Fisi Raciation [s;osure 10*8 to 10' R/hr E Estes for photons For nessure ent of niqm-reage radiatico es:osure rates at
* (p e rr.a me ntly warlows lo:ations.
installed conia
- tors) ~
4::::t .! u3:c::f r.t e:: t::ts tit!tst3 T2:9 int PLAsf ' ,/A /JucIG" e [/,"clJ (c Ef f16 tat ta:icactiv- (Normal plus ity - N;31e Cases accicent ram;e E ANS-4.5. Secticn 6.2.6 far roble gas' To provice peratcr .itn inf:r a- ,,9% tion regar:tes release of ra:te-4Clive f.cDie ;45 Cn a Contin.cws
.Costaireent ,
10*' to .05 %Ci/c: [anewst tent ans basis. Staa:ty *as r e-133 ca isration Treattert 5fsten Provisiens stow 14 te ace to monitor all vent potential patt.ays fer e esse of ;sse:6s racica:tive tater als is t?e r a vir:rs ta
.Cteer telease 10*' to 10 peifce ccnforma ce -ite Geaeral est;3 te-Paints (ine:sdia; Xe-13J calieraticn n3:,: peni or,3g er ir:t,,o,,, ,r,te-*:,{:.
;.,et fuel na :lia; stres s only is e :. ire: *ere 5.c?
bwilcin . aweili- (permanently strea s are releaseo : Meat:y is ary tuti:e g. arc installed een(- tr.e e9.irce e9t. *t !.o or sre twroir.e twil;t e;) tors) streens are cc 3 rec :*i: P 1; relesse tro, a c:- :a Jisc er c point ncnitcrie; Of :Pr c s re: strea, is ceasicerec to *eet 1 e intent el tFis qwice :r:..:e: ..c3 monitorieg nJ, a ran e aie;. ate o etasure worst Cest releases. Efflueet ta icactiv- 10 2 to got uti/cc ity
- Nf;n 7ange ..
E To provice tee e erator .itn Iacioealcreas ae.o '(per anently Information regar:ing release of Particulates installed eeni- radicactive ma re gens JmJ :Jrticu-tors), lates. Cantie.ows :alle:t en of representative sa D'ss 'slic=cc y by cont to-ing ( easureatsts) of sarales for racice.aio;e95 and 'Jr
- particulates.
D e- . B '%g
- sl 25}}