ML20039F251

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Requests That List of Publicly Available Documents Relied Upon in Preparing Core Performance Branch SER Input,Be Compiled & That Reproducible Copies of Referenced Matl Be Transmitted to Records Facility Branch
ML20039F251
Person / Time
Site: 05000561
Issue date: 04/02/1977
From: Parr O
Office of Nuclear Reactor Regulation
To: Check P
Office of Nuclear Reactor Regulation
Shared Package
ML111090060 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201120271
Download: ML20039F251 (10)
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b UNITED STA US 3f t GUCLEAR REGut ATCf.'l CGMMISSlCN { WASHINGTON D. . 20555 m.. s, Docket No. STN 50-561 MEMORANDUM FOR: P. Check, Chief, Core Performance Branch, DSS FROM:

0. Parr, Chief, Light Water Reactors Branch llo. 3. DPM

SUBJECT:

SER IfiPUT FOR BSAR-205, FROM CORE PERFORMANCE BRANCH of The January 31, 1977 CPB SER input for BSAR-205, by M. Tckar - d W. Brooks, is remarkably comprehensive in reporting the gen ic evaluations of B&W fuel assemblies done by the staff over a period of.several years. The Fuel Section discussion by M. Tokar includes many r terences to original source documents initiated by staff members B&W indicating that a thorough review of pertinent raterial has been completed. We intend to use the references supplied with the CPB report in a separate reference section at the back of Section-4.0 of the " Report to the ACRS", which document will become, later, a NUREG issue titled " Safety Evaluation Report". A number of the references are NRC internal documents or generic correspondence between B&W and the NRC. USNRC Bulletin No. 3201-2, issued January 14, 1977, presents guidelines for referencing source material in NRC documents, and particularly in NUREG reports. Our DPM procedures incorporate some of the requirements of this bulletin. In order to properly present your SER input and references, and to i assure the availability of those references to readers having a legitimate interest in same, we are requesting that you complete two actions: (1) Check the distribution on each of the references (other tnan Topical Reports by B&W) to determine that it should in fact be availacle in the PDR. The reference list in the Report to ACRS will include a general statement, applicable to all citations, that says "Available j in NRC POR for inspection and copying for a fee". An internal paper such as a technical memo should not be referenced unless it is already available in the POR or will be made available in the PCR prior to i issue of the Report to ACRS (in mid-May 1977). g .C 8201120271 810403 ~ ~ ~ PDR FOIA MADDEN 80-515 PDR,_

r A-1 i (2) ~ Assemble a file of reproducible ccpies of all referenced documarts other than Topical Reports. Transmit this file to :nis office ~anc 4 we will in turn transmit to to the Records Facilities Branch prior to the final NUREG. report issue of the Safety Evaluation Report. This will assure the availability of letters and memoranda which,'while nominally available in the PDR, are more readily retrievable if also located in our Central Files with the other original material indexed to a_ specific NUREG~ report. [0}x &.h JTan~ U. Parr, Chief Light Water Reactors Branch No.~3 Division of Project Management cc: 'R. Heineman R. DeYoung R. Boyd 1 W. Brooks M. Tokar R. Meyer D. Fieno . c. T. Cox. g ' ' i I l l 1 I I I I l t

~ c.- . t(& 7 cr' ~ 7?lt5 /\\ ({'cp Q 4 l tli ?\\ t [ TS dhM 15A/ } h$kk Z O [. \\ ~i I 03l28 - y.,. 1 'TA .<w gjff1j) ' R r~ M mentic.en: ' covN s*[b.") 'J'A1 \\ inc e:Uncci [tWAwariw - REsA R LM M su.altre: lwn oy say letter uatec ip J, ifiu, you were sent a copy or revig.xa atanuaru Kaview rian, icction v.s.1, "Pire erotection," cal /y nay 1, iv lu. 'rais revisen J.s 9.d.L containdo new guiuelines torMne~drU ',)]7 atact evaluations or rire pt atectica in our revicu'or nucJ ear posar 4,4 plant construction per. nit apistications docketeu atter July 1,197b. . j@M i 'ine letter stateu (1) tnat to tae extent reasonaola anu practicaule

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'gg tue u evaluating tire protection prov>31ons or operating olants, applica-fg tions currently unuer revic.t tor ' construction per.aits ano operating '.gQ licenceL, anu tuture app 11.;etions ror operating 12censas tor pir.nts . < : p; now unuer construction;. anu (2) tnat. yod Wou1O oe Kept iallori.Co ot Y> j gj 000 progre.23 as de uuvelopad' aiare cetinitive criteria or,acuestavle .f.-g.;p[ altern?cives for tne application at tne Stw 9.d.1 9divelines to tne ff< e ,O revies or tnese plants.

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t.nclosure 1 is npgenaix. A to oranca recunical cosition RPtou s.3-1, N15 "Guldelines Ivr Fire erotection for Juclear rouar Plants occKateu crior to July 1, 19 /u," Valen giveJ alternative guidance anu criteria acceptaale to tne stai.t to De utilizeu la a re-evaiuation o.t tue tire 'g g i proteccion provisions oi nucicar stea.a generating plants.

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..e require tnat you davalcate tue rire protection criteria currently 'fi incluveu in your stanaara nuclear'ste' supply scope, una iraposau on Q - tue ualance or plant (dup) uc31gner, ',1 cne applicaole guiuelines !) k in : J ~'.m.. Appenou n. Provlue couitivaal criteria as .--.2 s t i necessary to enaule tue.oJF uesigner to meet tue require.aents or b f C - Appenaia A inJhls ac3ign ot -tue plant tire pro- ~ coetion systesa. iour evaluation'snoulu taoulute all ites.s or equisent in tae.Mscope ot supply tnut con icitute a signiricant tire na:: ara citner oecause toe ite.a is a -p tential source ut ignition, or oecause tae. iteia contains comusciole ac.t'erials, or cotn. Typical exc uplea t f k, _( } or 3' t1 74 & A-l 'y m M- \\- g -w- .s... ... ~....,_,._ .g. A

l \\ T' l s e ,s i l wou2u ce. eicettical eqdip.. eat anu aasseiateu insui,ition i. uteri.ns,- ~ - W-$ ano pu..pa vita luc.ricating oil copy 11ea. Tne tavlc naoula iuentity ....:j .,?f,',j 0' tne ita.a or couponent, a piping ano 1natrumate.cien.olagraa lacation,. ir apt.cepriate, anu 'ene. raterial(cf tnat conaticute tue tire nazaru'. ~ 'y,Qj scovu.e tne quantitles or comust,1bic noteciais. (e.g. gaifo.p ot - (;6q Auuricating vila in reactor cooruac pu..ps; tne typ2(s), tae a.>unt(s) .:q ano tne tire rating of cuale(s). %p ,3 . Please reqenu witnin 20 ouys or receipt or cais letter to intor.a us- .. 'r + wnen you will suuait 'tne reauesteo intorniation, torty (40) copies "h$8 or wnica will oe requireo t:. : -statt. review. ?? 4 4 s. Tnis request for generic intormati5n was approvea oy 4\\a.u.aier -a. W @d" olankat eiearance nui.wr J-louaza (sou?a). Yais cleacance e::pires - ',M July.si,12 // - %'s 1 sd c .H2 s. S' pincerely, ,,. f he . ea;s 5 3 ,I,.*J. # *d ~ n.l;. . h p (llk ,? s l-[,. ] ' ..,. r, c ? ' (y i.$ i.- 0,* n -~ Ur.vt.Mt i IM2..).?nt ......M '~ UIt h L ^2 -__._r ' 2 %r Ka'g,uist.ign. J.@ @,. ~ ,,.?.. s .. r,,7 Enclosucus: YC p..t

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1 1 1 l Sd-W r 70 01N ( 0l?-7 /d gggg70fjy 2)f72ED q M e V /4,/97b a. ... ~,, ~ ~ 012.42 Section 9.5.1 contains the B&W fire protection interface re- . ;:. :X i; -~y1 ~ (9.5.1 ) quirements on the 80P designer. Provide a tabulation of the W5h: itanis-of equipment in the BSAR-205 design scope that constitute I a significaat fire hazard; e.g., pumps with lube oil supply, 4[d[. - electrical cabinets, electrical cables, or.other equipment ~ Mi;,fi # containing combustibles. The table should identif the itent + b;> l -or component, the P&ID where shown (where possible and the $Ws - material or fluids which constitute the fire hazard. Provide 4% quantities of combustible fluids (e.g., lubricating oil in .d*' 4 reactor coolant. pumps) and types and fire rating of cables used li ~ by B&W as part of the NSSS scope of supply. ' Mv.., q mn, i 'r <r,.q t.- ~',Q/ ?.3, \\ Lk,'5* 4; 99 '

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f fp, g _) (gespg,Jf st28ns a-saa-2m l nmend..' p j \\ A 012.42 Section 9.5.1 contains the B6W fire protection interface' requirements - i I on the BOP designer. Tabulate.the items of equipment in tSe NSS scope: of supply that constitute a significant fire hazard, e.g., pumps with _ j lube ~ oil supply, electrical cabinets, electrical' cables, or other 2rmI equipment containing combustibles. The table should identify the item c.z or component, the.P&ID where shown (where possibJe),.and the material:c WP or.flutds that constitute the fire hazard. Provide quantities of coor-SK i bustible fluids (e.g., lubricating oil in reactor coolant pumps) and i' u a;. ; 94 p types and fire rating of cables used by B&W as part of the NSS scopelfflg;d. i of supply, Wy{g

Response

lt . v. N.h.,. Section 9.5.1 has been revised to include the req.uested information. It'shotild5 J -g 5 be noted that B&W. does not include cable.in-the B--SAR-205 scope of design. ..r., .,,4 w .i$ # _. b1 , ;tl-N: l [h m-+C) . Q . m.: n j!p4 's 2 _h s ^'[, . *f k s t; j.,q.;%gp

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[ M l t y j ' / C 2 0 1976 i 4 m.rd 2 ..,. M, D. B. Vassallo c - ~ .a.... j .3.. Plant Design for Protection-Against. Postulated Piping Failures in a,. i jQ Fluid Systems Outside Containment 3 4. Pressurizer Relief Tank: ~ [ffj%[(? ~

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Y .~ N W - 13. Auxiliarye Feedwater System W ,.[@ Th" ;' The following areas.hav'e not been resolved:

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' W Section 9.1.1 anti 9.1.2 - _New and Spent Fuel Storage Racks.

1. p:y B6W has not provided all ' he necessary interface information for the hh t new and spent fuel storage racks,-i.e., rack dry, and loaded weight, C$ and rack wall tie'and foot interface information. B6W has committed ' 'g' %;k to provide this information in a later amendment. .NY wM Section 9.2.1 and 9.2.5 - Service Water System and' Ultimate Heat ~ Sink 'O c 2.' B6W has not pr6vided 'a~11 the necessary NSSS heat 16 ads to enable 1 J utility / applicants' referencing B-SAR-205 to design an acceptable service water system and ultimate heat sink. B6W has committed ta -( f rovide the additional information in.a.later amendmen.t. i. m. 3. Section 9.5.1_- Fire Profection System + N B6W is being ' requested to re-evaluate Ee fire protection' system Ok interface requirements and criteria and to identify. B-SAR-20S equip-- ment containing combustible materials in conformance with Branch Technical Position APCSB 9.5-1, '" Guidelines for Fire Protection for ,._ s Nuclear Power Plants."- ~ 1 - -.-.

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Fire Protection System - Interface Requirements - -Z. y ~ :s % ;KQ The fire protection system 1.4,the responsibility of.the applicant and is dis Nh" n l cussed in his SAR. B-SAR ' scope.-of-design systems impose the following' in .[ face requirements on the' fire protecelon systein: ' zh,'C. '4 1 l -^ fi?W } . l., ' Facilities _shall be provided for detecting 'and alarming the presence of

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~ 2.. Facilities shall be provid'ed for extinguishing potent'ial,. fires.; .# h M ..- g 3.- B&W designs its systems and components to minimize fire potential to thei -.-x . extent. practicable. To fully. implement the defense-in-depth concept for^. + . fire protection,. t;he applicant should also stress the prevention of fires'J .y i 'through the_use of fire-resistant andinoncombustible materials whenevert.f g practical and by minimizing the exposure of combustible materia a hazards. y j; p ygg 4.- Fire protection ' systems and theirf operation shall not adversely affect 'JdM the functional and structural integrity of safety-related structures, - ~ ?ji? systems, or components, - @.$.u$ Jdd e s

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3 5. Fire protection systems shall be designed so that their rupture or inadDN ) .vertent* operation will not impair the capability of safety-related struci?j tures, systems, or components -to' perform their safety functions,' Q:qgig

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6.. The following items'.in the B-SAR-205 scope of design should be carefully' sN

/M. considered in the design of the fire protection system: ~Il ../ Syst'em/ item (quantit'y)' Fire hazard li ' N m 76 s RCS. J,, .- % }j - ~ RC pump motor (4) / 426 gal lube oil.per pump. and" motor. ~ * - ~ ~ (( 'E ^ k ggp Makeup pump (3). N52 gal. lube ' oil'per pump, inci pump, motor, gears 'Purif'n deminer'alizer. (3) "} 50 ft3 resin per-demineralizer ?- Filter cartridgesi' ' Filter material when dry 84 Purif'n demin'r prefilter (1) s: Purif'n. filter (2) Feed filter (1)

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DH DH pusp (2). [ %3 gal. lube oil per pump and motor v \\ CA&BR Demineralizer(a): j, Evap. distillate (2) 10 ft3 resin each. f --.n,.--- ~~~ y * - - - - - - - - - - ~ ~ 4 .- J-i f.;. .A-- ..w 4

l l --+ -- l l 1 1/15/77 B-5AR-205 Amend. S r \\ { System / item (quantity) Fire hazard l .s a' dW RC bleed evaporator (2) 40 ft3 resin each . d.^.,... ' ' d, Deborating (3)- 65:ft3 resin each +- - ~ ' Boric acid filter cartridges. (2)(*) Filter material when dry ~ IE[4 $4 s -n , - 1, b w;G ;44 y ,j ,;KPS '.y,,S;(. r ~

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o . bay' cabinets (4) ~ Cabinet wiring. %[ 2:2 )gg .l(24'x 85.5 x 24/ bay) ~ 3d t..q ;c q a n., +, y ESFAS c;34 1

System cabinets (8)(b)-

~ j;. ' ?g 4 5'M 7, Cabinet wiring (24 x 79 x 30/ cabinet)'. _ s Mr # -l ~ s. t.Mk! i$dy) l -SRCf i l - '3-bay cabinets (2)(b) Cab'inet wiring ,_'f 7,y ' dy ~ (24 x 85.5 x 24/ bay) ~ y;5 Q % :b, ,L x;5q } 'CRDCS. m; XX I Y1 0' . Power and control cabinets (18)(b). Cabinet. wiring - '. 4 9M 3 (, 24 x 96 x.38/ cabinet) (b)~- -Cabinet wiring . *dQ W'$j?" ".i M. . '.ISystem logic' cabinets (2) J M $. 4L )

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A. -.Transformercabine'ts(2)(b) Q>,3 Qs t-A+ Cabinet wiring t. (56.x 64 x 38/ cabinet) >g:W.fQ Trip breaker cabinets (4)(.b)~. Cabinet wiring f ~ . W#4 ? I (60x91(x20/ cabinet). 'c k.g i L., 4 ~. ICS' [ Ng ~ ~ I . (b) . Cabinet wiring Y[ j1

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_5.- 2 g- .~. - ~ ..w (4)Not combustible when in use. 9 . c; (b) Number and dimensions of cabinets are typical values.only and are subject to change during the course.of detailed design. Dimensions i { specify width x height x depth-of cabinet units in inches. y [7.. The' fire protection system design.should also consider items or support-A. ing systems that complement the Babcock-205 scope of design. pecific s e I i dise'ssion will be included in the applicant's 'SAR. Typ1 cal examples to u be. considered are the following: e Flammable gases such as hydrogen or hydrazine ~used in the MU6P system. .a. r j b. Paint on fluid system components. - _f l l i s r- - --., -g-,y. ' - - - ---,----:---------~,~-- - -- -~~{

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