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Amend K to C-E Std SAR - Design Certification
	ML20126J052
Person / Time
Site:	05200002
Issue date:	10/30/1992
From:	Newman R; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, ASEA BROWN BOVERI, INC.
To:	;
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ML20126J045	List: LD-92-122, Forwards Amend K to C-E Std SAR - Design Certification; ML20126J052;
References
	NUDOCS 9301060021
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{{#Wiki_filter:. - _--_ _ ___-______ _ .i ATTACllMENT 1 l ABB-CE TRANSHITTALS OF CESSAR-DC REVISIONS PRINTED IN AMENDMENT K i L LD-91-012 3/15/91 LD-91-066 12/17/91 LD-92-006 1/24/92 LD-92-007 1/24/92 LD-92-016 2/12/92 LD-92-020 2/14/92 LD-92-024 2/18/92 LD-92-050 4/15/92 LD-92-063 4/30/92 LD-92-078 6/15/92 LD-92-113 11/18/92 I 9301060021 921221 -PDR -ADOCK;O5200002 A' PDR.

ATTACIIMENT 2 CESSAR-DC CilANGES IN-AMENDMENT K NOT PREVIOUSLY TRANSMITTED i h I t 1

i Summary of Attachment,l Chapter 1: Minor changes were made to the general arrangement drawings in Section 12, based on an internal consistency review. Those changes do not impact the responso to any RAI or DSER opon item. Chapter 3: A small sub-soction was added to Section 3.5 to indicate why no missilos aro postulated to bo genereated by the emergency foodwater pump turbines. Chaptor 4: Minor changes were made to Section 4.5 to clarify materials specifications, based on an internal integrated review of CESSAR-DC. It is noted that the change to the material ins also the subject.of DSER issues.pection program is Chapter 6: Changes were made to Section 6.2.5 (Combustibio Gas Control In Containment) to address NRC staff commento made during preparation of the DSER and to address intograted review comments. Chapter 9: Section 9.4.5 was revised to reflect an increased capacity for the subsphere ventilation system. Section 9.5 was revised to reflect NRC comments on diesel generator support systems which arose during preparation of the DSER. Chaptor 11: Revisions were made to remove powdex-technology-components from the Solid Waste Management System in order to be compatible with the bead-resin of the-condensate polishors in Chapter 10. The ALWR Utility Requirements Document' requires bead resin for the condensate polishers. Chapter 12: Changes were made to provide additional detail on design features for radiation protection in response to NRC comments made during preparation of the DSER, Changes were also made to reflect a lower source term _ due _ to. removal of the powdox equipment from the Solid Wacte Management-System. Appendix A A minor change was made to the resolution of USI A-- 45 to indicate that containment isolation will be initiated upon _ detection of loss of decay heat removal. v '( -,n, .,n.

!!ncionuro 1 i DRAWING NUHDER RINISION NUMBER 4248-00-1607.00-G001-01 2 4248-00-1607.00-G200-01 2 4248-00-1607.00-G200-02 2 4248-00-1601.00-G200-02-01 1 4248-00-1607.00-G200-03 2 4248-00-1607.00-G200-04 2 4248-00-1607.00-G200-05 2 4248-00-1607.00-G200-06 2 4248-00-1607.00-G200-07 2 4248-00-1607.00-G200-09 2 4248-00-1607.00-G200-10 2 4248-00-1607.00-G200-11 2 4248-00-2507.00-G200-12 2 A ren 7 e me i-c m u.3, 7 f f.J e.- &n (4 m r,~ cesna-oc, sci-

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CESSAR Eninem D. Industry pump designs are such that ( and servico history shows) no occurrences of impoller plocos penetrating pump casings. A Add. EMe& 1 3. 5.1.1. ;lk, Valves Thoro are no missiles postulated from valvos for the following reasons: A. All valvo stems are provided with a backsoat or shoulder larger than the valve bonnot opening. D. Hotor operated and manual valvo storrs are rostrained by stem threads. D C. Operators on motor, hydraulic and pnoumatic operated valveu provent stem ojection. D. Pneumatic operated diaphragma and safety valvo stems are restrained by spring force. E. All valvo bonnats are either pressure coaled, threaded or bolted such that there is redundant rotontion for provention of missilo generation. 3.5.1.1./9 Proesure vessels All pressurized vossols are considered moderate onorgy (275 poig) or loss and are designed and constructed to the standards of the ASME Code. In addition to the ASME Codo examination and testing requirements, all vossolo will receive periodic in-servico inspections. Where appropriato, those components are provided with pressure relief devices to ensure that no pressure buildup will exceed matorial design limits. On this

basis, moderato onorgy pressure vossols are not considered credible missilo sources.

3.5.1.2 Internally Generate ( Missilon (Inside Containment) Tab *1c 3.5-1 lists postulated missiles from equipment insido containment, and summarizes their characteristics. Included are major protonsioned studs and nuts, instruments, and the CEDM missilo. Other items which woro considered and specifically excluded because of redundant rotontion fonturce are valvo stems, valve bonnets and pressurized cover platos. Amendment D 3.5-3 September 30, 1988

INSERT 1 CESSAR-DC; Pace 3.5-3 3.5.1.1.2 Emergency Feedwater Pump Turbines There are no postulated missiles from the Emergency Feedwater (EFW) pump turbines for the following reasons: A. Turbine overspeed protection; electrical trip at 115% of rated speed, and mechanical trip at 125% of rated speed. B. Assurance of turbine disk integrity by design and inspection. C. Enclosure of the EFW pumps and turbine drivers in a reinforced l Concrete room. 1 m f ,.w-.r ? y e----- p y

CESSARnahiou 4A P Q j / i -The following-in a list of-the major components of;the reactor [ internalu together with their material specificationcs A. Coro nupport barrel assembly 1. Typo 304 austenitic stainlocs stool to the following specifications: sn - a. I '5M-A-182 ,h m.e- -A m % -A,13=

b. Ar; 5A AMH-%-24 0 c. J.lf g ?f ?" *-479 t

I i 2. Precipitation hardoned stainless stcol to the following. specifications: AL.:SA j a. A-453, Grado 660 b.. ' ""'" 4-6 3 8, Grade 660 -SA r i D. Upper guido structure assembly 1. Type 304 austenitic stainless stool to the following / specifications: e

a. SAMT4-A-182

b. SAMTM-A-2 4 0 c.Sn.ASqM-A-213 d.50 AST& A-479 D

Precipitation _hardoned stainless' stool to the following 2. ,_ specification: gn

a..

AMH-A-638, Grado 660-I fdf;& h rt Coro snroud a]ssemblywiedhL WLS 5j" j 4 j q p //,s / 3-Tyt 3Q f a.^ A-4' 71 ~ C. L. 54-3/1-1. Typo 304 - austenitic stainless stool to the following specifications: Sn. a. -ACT:4-182

h. % ASTM-A-240

~sA _/- D.- IIolddown ring. A SA -l St-- 4 U0>' F6 U/Y) v 0 1 rL_ x amendment D '4.5-7 September. 30,. 1988- ,-.___..-_..-,.._..-._..._._,..._.~.;._.-_._.._...

wd ac~y rhdn CESSAR !!!Mi,%,ou-1 (CinL PAFM OkWL ~ Gt) 4'19 $ 286% (TCAM Wh>nc Nu lgovic (,cd i s vatid

t, i CCint tippa lA Tie %s A gris; rkt, G A llh<

q t _ 24 l 11ol t and pa n ma m,0 tTIO Arte Ot' Sf Rt*Q. ASTM-A-4S3 and ASTM-A-638, Grade 660 material (trade name A-2 tl 6 ) in uned for bolting and pin applicationn. Thin alloy in heat treated in accordance with the ASTM opecificationu by precipitation hardening at 13 00 -14 00

F for 16 hourn to a D

minimum yield utrength of 85,000 pui. Itn corronlon propertien are nimilar to those of the Type 300 nerien auntenitic ntainlenn steclu. It in auntenitic in all conditionn of fabrication and heat treatment. Thin alloy wan used for bolting in previous reactor nyntemn and tent facilities in contact with primary coolant and han proven completely natinfactory. F. chromr- )lating and hardfacing G G9 @ chrome latjpg hardfacing are employed on or reactor cos 59Fr, owd interifak Yomlonents i or portions thereof where required by function. Chrome plating complien with Federal Specification 11 0 QQ-C-320. The hardfacing material employed in Stellite 25. D All of the materials employed in the reactor internaln and in-core instrument nupport nystem have performed natisfactorily ?s in operating reactorn such an Palisaden (Docket-50-255), Fort ~ Calhoun (Docket-50-285) and Maine Yankee (Docket-50-309). 4,5.2.2 Wel d i rig _Accepia nc_e_n_t a n13 Welds employed on reactor internals and core support structuren fabricated in accordance with Article NG-4000 in Section III, are and me'et'the acceptance standards delineated in article NG-5000, y Section III, Division I, and control of welding in performed in accordance i.fith Section III, Division I, and Section IX of the ASME Code. In addition, consistency with the recommendationc of Regulatory Guiden 1.31 and 1.44 in doncribed in Section 4.5.2.3. 4.S.2.3 Fabrication and Procenn_ing_of Austenitic StainlenJ1 lit;itel The following information applien to unntabilized auntenitic stainless steel an used in the reactor inter..als. 1 4.5.2.3.1 Control of the Une of Gengi.tJAed Auntenitic Stainlonu Uteel p, y 3, J. The recommendationn of Regulatory g'Gu ide 1.44, an doncribed in Sections 4.5.2.3.1.1-through 4,4 2JA2mS, are followed except for the criterion used to demonatrate freedom from nennitination. (il l "Tpe7;AS)7f/ W 7t7pi nr-Tc7(t]u,, un 0]1/i-~77eu j or'7tt307)dT f(47p77-i l ryehod gM, dertun 6t -to 3 7 ( l , dv(n. _~._-. - ni((mens t rak_ rhe inmabm i Amendment F 4.5-8 December 15, 1989

i CESSAR nn"lCATION -r \\ foerifiThi f cated notahl))lec auch it.ic ta ple s (ny,tn,fp o tpeAor Ms d' 6oQn,/f) (i h en tl'o, ptpdl i l f cxec1'l copro'ladio h'e /{c ~ 'p6/of[y o r6s on 9,u6 /d , 'bpdat e _ fd}mitg56d 41 M'es s s te :f. V steh y 4.5.2.3.1.1 solution Heat Treatment Roquirements All raw austenitic stainless steel material, both wrought and cast, employed in the fabrication of the reactor internals is supplied in the solution annealed condition, as specified in the portinent ASTM or ASME B&PV Code material specification (i.e., 1900 to 2050*F for 0.5 to 1.0 hour per inch of thickness and rapidly cooled to below 700*F). The time at temperature is determined by the size and the type of component. Solution heat treatment is not performed on completed or partially fabricated components. Rather, the extent of chromium carbido precipitation is controlled during all stages of fabrication as described in Section 4. 5. 2. 3.1. 4. 4.5.2.3.1.2 Material Inspection Program Extensive testing of stainless stcol mockups, fabricated using ~ production techniques, was conducted to determine the offect of various welding procedures on the susceptibility of unstabilized Type 300 series stainless steels to sensitization-induced intergranular corrosion. Only those procedures and/or practicos demonstrated not to produce a sensitized structure are used in the fabrication of reactor internals components, f The ASTMI [Mr.andarA708 (St"ausu Tus' } --is --- Uto-Crit'EfiEIT U"t!Mo dptorm{ne intergran lar corrohion. This test hds shown s ecepti lity to ext llent orrelat n with a orm of lo'calized corrpsion heculiar // i to s nuitiz d stain ss steel. As such,\\ ASTM A700 isutilizedasQCh, a go/no-go shndard f r-accepta ility. As a result of the above tests, a relationship was established between the carbon content of Type 304 stainless steel and weld' heat input. This relationship is used to avoid wold heat affected zone sensitization as described in Section 4.5.2.3.1.4. 4.5.2.3.1.3 Unstabilized Austonitic Stainless 8 tools The unstabilized grade of austenitic stainless steel with a carbon content greater than 0.03% used for components. of the reactor internals is Type 304. This material is furnished in the i solution annealed condition. The acceptance criterion used for this material, as furnished from the steel supplier, is ASTM i A262, Method E. 4.5-9

mL pc-pa C ES S A R "En,"ICATION ( material is presently being used in operating reactors such as Maine Yankee (Docket 50-209), Calvert Cliffs (Docket 50-317) and St. Lucie Unit 1 (Docket 50-335) and has performed natisfactorily for the name application. 4.5.1.3 pgAtrol of t.be Une of Dennitiz_ed Austenitic d St.ainlenn SteA Control of the use of sensitized austenitic stain 1 css steel is consistent with the recommendations of Regulatory Guide 1.44, as described in Sections 4.5.1.3.1 through 4.5.1.3.3, except for the criterion used to demonstrate freedom from sensitization. The ASTM A708 Strauss Test is used in lieu of the ASTM A262 Hethod E, Modified Strauss Test, to demonstrate freedom from sensitization in fabricated unstabilized austenitic stainless steel. The former test has

shown, through experimentation, excellent correlation with the type of corrosion observed in severely sensitized auctonitic stainless steel.

4.5.1.3.1 Bolution Heat Treatment Requirements All raw austenitic stainless

stcol, both wrought and

cast, employed in the fabrication of the control element drive mechanism structural components is supplied in the solution i

x annealed condition, as described in Section 4.5.2.3.1.1. 4.5.1.3.2 Material Inspection Program Extensive testing on stainless steel mockups, fabricated using production techniques, has been conducted to determine the effect of varipus welding procedures on the susceptibility of unstab'ilized Type 300 series stainless steels to sensitization-induced intergranular corrosion. Only those procedures and/or practices demonstrated not' to produce a sensitized structure are used in the fabrication of control gelement drive mechantnm structural components.( Tne AS tandarc 3708 (StraussNt) is tne critorion used t determi4fc susceptibi ify to inte anular corro" <ff. This tp t has s (o w /J excellen correlatio with a form o ocalized co osion pc lia CUkg to senn tized stal. ess stcols. s such, ASTM 700 is 9 111zet as a go/no-go stafidard for accgptbbility. / 4.5.1.3.3 Avoidance of Sensitization J Homogeneous or localized heat treatment of unstabilized austenitic stainless steel in the temperature range 800-to 1500'F is prohibited. 4.5-4

CESSAR E!n%mou AL4-yd I k 6.2.5 COMBUSTIDLE CAS CONTROL IN CONTAINMENT I Following a design basis Loss-of-Coolant Accident (LOCA), control f Q)of combustible gas concentration in containment is provided by the Containment Hydrogen Recombiner System (CHRS). Ilydrogen may v 5I be released to the containment atmosphero following a LOCA by 'Tradiolysis of water, corrosion of containment materials by the \\ ch:ontainment spray, reaction of the zirconium cladding with steam V and dissolved hydrogen coming out of colution from the reactor coolant and pressurizer steam space. The CIIRS provents the o concentration of hydrogen from reaching the lower flammability t limit of 4% by volumc4 The system is designed in accordance with the guidance provided by Regulatory Guide 1.7 and as required by i 10 CFR 50.44, 10 CFR 50.46 and General Design Critoria'5, 41, 42 and 43. In addition, this system provides the capability for [ controlled purging to aid in post-accident containment atm'osphere .s l + .; cicanup with filtration of the dischargo provided by the annulus 4 ventilation filter trains. 4 wk of 'j " During a degradedhore accident, hydrogen will be produced at a c greater rate thanAthe design basis LOCA. The Hydrogen Mitigation l System (IIMS) is designed to accommodate the hydrogen production from 100% fuel clad metal-water reaction and i..c c t ai.daverage hydrogen concentration f linit of-10% in accordance with 10 CFR 50. 3 4 ( f) for a degraded core accident. These limits are imposed to preclude detonations in containment that might jeopardize containment integrity or damage essential equipment. The HMS consists of a system of ignitors installed in containment to promote the combustion of hydrogen in a controlled manner such that containment integrity is maintained. 6.2.5.1 Design Bancs 6.2.5.1.1 Containment Ilydrogen Recombiner System (CIIRS) A. The CHRS is an Engineered Safety Features (ESP) System designed to maintain the hydrogen concentration within the containment atmosphere below its lower flammability limit of 4% in accordance with Regulatory Guide 1.7. The system is designed to be manually initiated prior to hydrogen I concentration reaching 3.5% by volume. B. Two independent, full capacity, parallel loops make the system fully redundant and enable it to withstand a single active failure and still perform its design function. C. The CHRS is designed to provide sufficient suction points insido containment to eliminate stagnant pockets of air where hydrogen could accumulate, t -Amendment I n -., - t. ,nnn j:

'CESSAR1E%nce Aw (246[ f D. Recombiner inlet connections from the In-containment Refueling Water Storage Tank (IRWST) are provided to remove hydrogen produced by sump radiolysis in the IRWST. E. Components of the CHRS are designed to sustain normal and Seismic category I loads as well as temperature and pressure transients from a LOCA. F. The hydrogen recombiners are protected from damage by missiles or jet impingement from pipo ruptures. G. Components of the CHRS located in containment Vill be designed to meet the appropriate environmental requirements specified in Appendix 3.11A. H. System equipment located outside of containment will' 'be arranged to preclude failure of the CHRS due to failure of other non-Category I systems. I. CHRS components will be designed in accordance with ASME Boiler and Pressure Vessel

Code, Section

III, Class 2

requirements. J. In the event of offsite power

loss, power to the Containment Hydrogen Recombiner System will be automatically supplied by the Class 1E ficctrical System which is supplied l

by the emergency diesel generators.f 60 VAC AuviUary O'*'" K. The system valves and components will be designed in accordance with ANS Safety Class 2 requirements. L. Access and shielding are provided to the areas where the portable hydrogen recombiner and control panel skids are to be placed along with areas where coupling operations are required. M. Capability will be provided for a controlled purge of the containment n*re ghnrn- ?n aid Jn _ post-accident ___ containme t I cicanup.Qh:s e,e tio n ,4 we ,,,, 4, _ is ~ o m. fa,4 y c e u,A N. Redundant hydrogen analyzers provide hydrogen concentration measurement of the incoming gas from containment as well as the recombiner discharge for monitoring of recombiner performance. The hydrogen analyzers are independent of the-hydrogen recombiners and are permanently installed to allow hydrogen concentration monitoring throughout the accident. Amendment I g ,_ac nn-n%,, .ane

CESSAR8ln% m hp w,[ hydrogen production analysis. The parameters which determine the amount of hydrogen produced during the design bacio LOCA are listed in Table 6.2.5-2. Design basis LOCA hydrogen generation assumptions are discussed in the following sections.

6. 2. 5.1. 3.1 Core Solution Radiolynit.

Radiolysis of the emergency core cooling solution occurs as a result of the decay energy of fission products in the fuel. The hydroger, production analysis by core cooling solution radiolysis is based on the TID-14844 release model. Per Regulatory Guide 1.7, it is accumed that all of the beta energy is absorbed within the fuel and cladding with a maximum of 10% of the gamma energy being absor%1 by the cooling solution in the . core A conservative nydrogen yield of 0.5 molecules per 100 eV was assumed for both core and sump colution radiolysis. Al1 noble gases are assumed to be released to containment. The assumptions for hydrogen production due to radiolysis in the core and sump solutions are listed in Table 6.2.5-3. 6.2.5.1.3.2 Sump Solution Radiolynio Radiolysis of the sump solution occurs due to the radiolytic decomposition of the containment sump water by the fission products. The TID-14844 release model is assumed where 50% of the total core halogens and it of all other fission products, excluding noble gases, are released from the core to the sump solution. The total decay energy from the released fission products is assumed to be fully absorbed in the sump colution. The containment sump includes areas in containment (i.e., dup volume, horizontal surfaces, etc.) and the IRWST. Si 50+ *et of 5 the containment sump water is enclosed in the IRWST the sump radiolysis is assumed to occur in the IRWST. N i 5 7 */. 6.2.5.1.3.3 Corrosion of Containment Materials Corrosion of metal surfaces, primarily aluminum and zinc, are significant contributors to hydrogen production in containment during a LOCA when subjected to the borated containment spray. The inventory of aluminum and zinc in containment is minimized to the extent practical to limit these hydrogen sources. The inventorico used in the hydrogen production analysis are conservative in that they are the maximum limit of aluminum and zine to be used in containment. The actual inventories are anticipated to be lower. l Amendment I 1 6.2-48 December 21, 1990

CESSAR !!nLmu pp g i 5 4, n o ( ;,... a x adX.sg s "r * * " j 1 % corresponds to 5% of thef'Y,' $r c 2irc21cr ' "' ""'n; rc2cting to ferr N drogen. Por Regulatory Guido 1.7, the nydrogen is annumed to be released into containment over a 2 minuto period from the start of the transient. 6.2.5.1.3.5 Dissolved Ilydrogen in Reactor Coolant The maximum equilibrium quantity of hydrogen in the reactor coolant is 3890 scf. This quantity includes both the maximum ~ allowable hydrogen concentration in the primary coolant water at 100 cc (STP) per kilogram of water and the equilibrium hydrogen in the pressurizer steam space at the maximum concentration of 2/10 of 1% by weight of-steam. The entiro 3890 scf of hydrogen is assumod to be released immediately into containment at the initiation of the LOCA. 6.2.5.1.4 Design Basis LOCA Ilydrogen Accumulation Besides containment, the IRWST is the only other enclosed compartment which could experience hydrogen pocketing. liydrogon recombiner inlet connections are provided for the _IRWST which account for one-half of the 100 cfm flow to each recombiner. To account for single

failure, only one of the 100 cfm recombiners is considered in the analysis.

The flow split por recombiner is 50 cfm from containment and 50 cfm from-the IRWST. liydrogen concentration versus time is shown in Figure 6.2.5-2 for containment and Figure 6.2.5-3 for the IRWST. These figures show hydrogen concentration without recombiner flow and with a single recombiner started 72 hours after the LOCA. 6.2.5.2

System Design

6.2.5.2.1 Containment Ilydrogen Recombiner System The CliRS consists of two redundant loops. Within containnont, I cach loop of the CllRS is comprised of a. suction header (influent piping)- with motor operated valves and a ~ discharge-header (offluont. piping) with a check valve. Outsido-of containment, in _each loop consists of influent piping, manual -the Nuclear Annex, and motor operated. isolation valves, sample piping, a L hydrogen analyzer, a mobile recombiner and control panel _ skid, - test and calibration connections, an; isolated nitrogen supply connection, an isolated rervice air connection, a safety valve,.and effluent' l

pining, ie+<ument The recombiners and control panels are skid-mounted, self-contained units.

Planged piping connections are used-for ease of Amendment I 6.2-50 December:21, 1990

CESSAR Unincuin hLU[A# ({h TABLE 6. 2. 5-2 ITYDROGIUi PRODUCTION PARAMlfTIUIS Paramotor Valun Reactor Power (Full power plus 2% uncertainty), MWt 3876 Reactor Operating Time, Months 18 3 6 Containment liet Froo Volume (Minimum), ft 3.377 x 10 3 IRWST Frooboard Volume (Design basis LOCA), ft 1.032 x 10 Initial Temperature, 'F 110 Initial Pressure, psia 15.1 Initial Relative Humidity 10% a d 4 v e-4 ue l) 56, l CladdingZirconiumMacrf,(Jaereundin) lbm 52,122 Dissolved Ilydrogen in Reactor Coolant (Maximum), cc (ST1') por kg of water 100 Dissolved Ilydrogen in Pressurizer Steam Spaco (Maximum), by Weight 2/10 of 1% Amendment I Decemhnr.71. Soon

[1-p (2. - 96 h( 1 i 1 i i 9 ~ D ~ 7 ~ 6 WITHOUTitECotADitJER ~

t 5

4 WITi(RECOMDitlER / 2 3 1 I f I l i I tid ( O 100 200 300 400 500 600 700 TitaE, HOURS R c p\\ n c. c. Wie / Fo ll o w,n g Py e. Amendment i December 21,1990 F%u r e-l ~ / cot 4TAltJMEt4T liYDROGEti cot 4CEt4TRATIO!1 vs TIME AFTER LOCA (WITilOUT RECOMBit4ERS At4D WITil A ~ Jgg j flNGLe RECOMBir4ER START TIME OF 72 liOURS) 0.2.5 2 l g

\\ % E mL% 00 8 m_0 0 7 R E N I B M OC 00 E 6 R HT IW N w0 R E B'/ 0 1 I 5 M O C E R S R T U U 0 O OH 0 H 4 T W E I M I T i 003 00 I 'j 2 00 1 pC Irr tLL [ r tk 0 0 9 8 7 6 5 4 3 2 3 o 1 e t; d

h bsJf s \\fh / Ng ~ N / 9 0 ' WITHOUT HECP9 BINER 7 G 5 8 4 WJITH RECOMBINER / 2 1 t. I 1 l l l t 0 100 200 300 400. 500-600 700 8 TIME, HOURS 4

f. R c pl a c e.

Wit h F o ll o wi n <3 Page

AmendmentI' December 21,1990 AFTER LOCA (WITHOUT RECOMulNERS AND WITH A _

Ftgure-IRWST HYOROGEN CONCENTH ATION vs TIME RECOMDINER START TIME OF 72 HOURS) . 6.2.5C il SIN t-1.11A - -__L_-_-_______---

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CESSAREnMemw earthquake, and are able to withstand the effects of appropriate natural phenomena such as tornadoes, floods, and hurricanes (GDC 2). The essential mechanical equipment room cooling systems are protected from the effects of internally generated missiles, pipe break effects, and water spray (GDC 4). The Subsphere Building essential HVAC System is designed to limit the offsite and control room dose following a LOCA or DBA within the guidelines of 10 CFR 100 and Standard Review Plan Section 6.4 respectively. Radiological consequences ar" .scussed in Section y 15. 00% The Subsphere Building Ventilatio Systems are separated according to Divisions with each -64 xhaust system containing a filter train complete with particulate filters and carbon adsorbers and two fans as shown in Figure 9.4-5. i 5 0 V. The essential mechanical room cooling units are shown in Figure 9.4-4. 9.4.5.1.1 Codes and Standarda Equipment,

work, and materials utilized conform to the requirements and recommendations of the codes and standards listed below:

A. Fan ratings conform to the Air Moving and Conditioning E Association (AMCA) Standards. B. Fan motors conform to applicable standards of the National Electrical Manufacturers Association (NEMA) and the Institute of Electrical and Electronic Engineers (IEEE). C. Essential equipment, fans, coilu, dampers, and ductwork will be manufactured in accordance with ASME/ ANSI AG-1-1988. D. Ventilation ductwork conforms to applicable standards of the Shoot Metal and Air Conditioning Contractors National Association (SMACNA). E. Cooling coils in the esbential cooling units are designed in accordance with the ASME B&PV Code, Section III, Class 3. F. High-efficiency particulate air (HEPA) filters conform to I ERDA-76-21, " Nuclear Air Cleaning Handbook." G. Carbon filter

media, Nuclear Grade as defined by the Institute for Environmental Sciences.

/ Qhh 9.4 -December-21r 1990

s. A J t u o r e >.

CESSARNEnce ( A. Motoe-driven cmergency fccdwater-pump-roomar =P. E tcam-dwivon-omorgenoy -fcedwatree-pump-rooma, 9.4.5.2.1 Component Description The essential mechanical equipment room cooling units consist of chilled water cooling

coil, direct-drive centrifugal recirculation

fan, and dampers and controls to achieve the desired operation.

The chilled water coils are served from the essential chilled water system. The essential mechanical equipment room ventilation units contain intake filters, direct-drive centrifugal supply and exhaust fans, and dampers and controls to achieve the desired operation. There are heating and cooling coils to temper the outside air as required. ' j{ (p $. g ' fl p ",. A y 9.4.5.2.2 System Operation one /00N /I 3 e y +-Dur4ng norma-1--eperat4en of the---Seneral vent 44-e.t4en cycte -ou tsid o-o4&ls-su pp44ed-by--two-504-ce paeit-supp-1P-un-i-t+-ond-two- -G o t capacity cupp4y Mno-,-- The air in filtered and then conditioned as needed by the heating and.co.oling coils. Th is processed throughg~wo-So& cap 6 city filter train [e exhaust air I complete with particulate filtord ~and carbon -adsorbers and. is ' discharged to the unit vent by two 50% capacity exhaust fans. Supply and exhaust fans are electrically interlocked such that the building will always remain under a slight negative pressure..o In the event of a loss-of-coolant-accident, the general ventilation equipment will continue to operate normally as long as offsite power is available. On LOOP, the exhaust fans will be powered from the Class 1E diesel generators. l-Thie-mad-ntaine-the-cubophere--pump-coomo-at c slight -negat-ive-pr-oosure to direct all releases through the exhaust filter train.I-Duct tc crean--wit-h-ncn-ccsentia1 e c e 1 i n9--un-i-t c ui11 be- +oohted te cnaMe-proper operat-len--e&--the-emeegency cquipmenti Normal operation of the essential mechanical equipment room cooling and ventilation units is with th c = cqu i pnont--opera ti ng-as required to maintain space temperatures. The cooling systems will operate based on heat load as indicated by room temperature. In the event of a LOCA or DBA, all units are automatically started and will operate --at full capoei-tp throughout the event. -I-nd444dua4--r-oom-u n-i-tc wi11 a t-a et--wh en-the-eq ukpmen t-4n-the-coom- -sta r-to, The. L fsp!,ern. Ba;l Veddaffan Sy, fem }g umpejge-/ J -fuo fj,$,.,'m/f S* par $, AIly reh Ad vc.cl.'/ din sys&c m t.tsl caprllC of lely ym nog capae;-fy apply uif ad k so? g ded ~ u de <e b 4c;l7 vyp y A r p c h viri.m. k' n [ g g & l P 3 Amendment ( 9.4 ._ December-21,-1990 l e, L, s,, ,e , c c p.

.0 Ib V /.J /v r av3" TABLE 9.4/4 4." INPUT FOR RELEASE ANALYSIS FILTER EFFICIENCIES Design / Maxieza Testing Ventilation Recirculation Charcoal ifEPA IIEPA In-Leakage Area Identity Standard CFM* CFM* (Elem.) (Particulate) (Organic) CFM Control Room RG 1.52 2,000 4,000 95 99 95 10 14.,,2 CO Subsphere RG 1.52 . 000-N/A 95 99 95 N/A Annulus RG 1.52 18,000 18,000 95 99 95 1,000 Fuel Building RG 1.52 25,000 N/A 95 99 95 N/A I Containmem. RG 1.140 30,000 60,000 95 99 95 N/A

Ventilation CFM is shown for each Division.

Amendment d -Dec & ber-2.1 199u 0N/J 3 0, / 69 &

./ I W S hq .c ft t' ) TABLE 9.4 (Cont'd) [ 0 (Sheet 8 of 12) 1 HVAC SYSTEM DESIGN PARAMETERS S Flow Rate / Unit Operational Mode Area or Type Heat Load Air Cool Water No Units Power Location Nomal Essential System Btu /hr CFM gpm % Capacity Supply __ Equipment

ontainment X

High Purge 30,000 1/100 Filter flormal Filter train Exhaust j 2/100 Fan 460V and 2 fans, l 100 HP i Containment X Low Purge 1,250 1/100 Filter riormal Filter train Exhaust 2/100 Fan 460V and 2 fans, 5 HP I;,000 So subsphere X Heat / Cool , 000-2/4E4 120/160 Prefilter, Vent. Sup. I Fans 7.5 HP cooling heat coil, fan Subsphere X Heat / cool 11, 000 50 w,000 2/MG 120/460 Prefilter, Vent. Sup. II ~ Fans 7.5 HP cooling heat coil, fan I 13,200 60 Subsphere I X Exh. to 5,000-2/400-120/460 Filter train Vent Exh Unit Vent Fans 20 HP 13,2 M go Subsphere IP" X Exh. to 5,000-2/M4 120/460 Filter train Vent Exh 1 Unit Vent Fans 20 HP Fuel Pool Heat X X Recirculating 150,000 3,200 25 1/100 Train D Cooling coll, l-Div. II AHU [17] 120/460 fan, filter 1.5 BHP l Amendment I _ Drember-91 90-A. U n 1 as .CC W

CESSAR Eny.cung [\\tvJ P M ht k' l ,/ DIESE!. G10lKilATOR 131GINH VUEI, 0I14 SYSTIM 9.S.4 9.5.4.1 Donign llanos E The Diosol Generator Engino Fuel Oil Syntom la donigned to seven-day supply of fuel oil for each provido for storago of a diocol generator engine and to supply the fuel oil to the engino, as necessary, to drive the omorgency generator. The syntom is doolgned to moet the single failuro critorion, and to withstand the offects of natural phenomena without the loan of operability. in,dicut fuel shr9 Wocwe a Seinmic Category I atructure (diosol generator buildinc except for -the4ue4-ol4-y ;'7$ All components and piping are locator otorago--tankr,-a nd-a portion of the piping from the fuol oil storage tanks to the day tank, which is coismically qualified and All ossential componento and piping gro, fully protected. internal missiles, protected from floods, tornado misallo damago, pipo breaks and whip, jet impingement and interaction with non-noicmic systems in the vicinity. 9.5.4.2

System Description

The Diocol Generator Engino Fuel Oil System is shown in Figuro 9.5.4-1 (Shoots 1 and 2). 9.5.4.2.1 Conoral A separato and completo fuel oil storage and trannfor ayatem la provided for each diosol generator engino. Two -undorground-g% storage tanks provido fuel oil for each

engine, which is sufficient to operate at full load for a period of timo no loss than savon days plus a margin to allow periodic testing.

Typically, thin requires a combined usablo volume of 135,000 The nito-specific SAR chall verify that this is gallons. adequate for the diocol generatorn purchased. by'Cthcs.v'.kgo-fuel-nibtransfer-pump-f rom the h Fuol oil la transferred storage tanks to the day tank which in located within retaining-valls inside the diosol generator building. -The -tue4 oH- ! b- -t ra ns fe r-pu mp-i s-a l so-J ooa ted -i n-the-d issol-genera tor-bu l l-d -i ng-The day tank has a sufficient end-4*4ypM44y-sized for E9pmv dional generator engina in capacity of fuel oil to operato the excess of 60 minutes at full load. Typically, tl.in requires a The site-specific SAR shall verify that -fuo-1--o44-transfac.-pump-r4ow-ond-day tank capacity gre-adequato {p day tank of 900 gallona. 13 for the diocol generatorn purchased. I\\ [Wd hMEst 5 -> i /j,, y: l Amendment I ..1990 9.5-S1 Doc.omber-21,

CESSARnahou fut ^# _ - R $ $ U J _ _ _ ~ _,the A-oet-of-lcvc1 c ' ' i tchoo-l oca tod-w l t h i n-t-ho--d a y-ta nk-co n t ro l-ope ra t ion-o f-tho-f uel-oi-1-tra ns f er pump t-st art ing -tho-pump-a t-daf bank-low-levol -stopping -tha-pump-at-day-tank-high-level High t and-low-levol-alarms-aro also-provided-both-on-the-storage-tanks-and-on-tho-day-tank.-Jn-tho-ovent-of-a-tranpror-pump-f ailuro-to, -otart,-the-day-tank low-level-alarm,-indioAting-60-minutea-of ' fuel-reserve-at-ful1 load, allows-tho-operator to-tak4 -oorrootivo action,-In-the-ovent-of-a transfer-pun,turailure-to-stopr-an-ov e r f l ow-1 i no-i n-p rov i d od -on-t h o-d a y-to nk-to-d i ve r t-tho-exces s K, fuel-oil-to-tha day tank-containment-(or-back-to-the-fuel---oil storage-tank-do onding-upon storago-tank--elevation-relativa-to -tho-da y-ta nk ),- During normal operation, fuel oil is pumped from the day tank to the engine by the engine-driven fuel oil pump. The motor-driven fuel oil booster pump is normally isolated both electrigally and mechanically, but may be operated if required during maintenance. The day tank provides sufficient positive suction to both the motor-driven fuel oil booster pump and the engine-driven fuel oil pump. Each pump is provided with a duplex suction strainer and a dischargo pressure rollef

valve, and an engine-mounted dual element fuel oil filter is provided on the common dischargo hendor.

pressure gauges are located on tho inlet and outlet sides of both strainers for local l'ndication and an alarm is provided with each strainer to alert the operator of high diffocontial pressure. Differential pressure indication and a E high differential pressure alarm are also provided with the fuel oil filter. Two fuel oil drip headers, one located on each bank of the diesel generator

engine, contain unburned fuel leakage within the engino.

The unburned fuel is removed from the drip headers through a piloted valve and ejector driven by the pressurized fuel oil return from the bypass headers to the day tank. The main circulation headers are fitted with a relief valve which prevents the engine fuel oil pressure from exceeding a certain maximum and which discharges back to the day tar.k. The day tank is surrounded by a fire wall which serves as a containment in the event of leaks or ruptures. The containment drain line is isolated by a normally closed, solenoid-operated valvo. A high level signal from a level transmitter located within the containment opens this valvo, allowing the oil to drain to the suction side of the lubo oil transfer pump which is simultaneously activated and delivorc the oil to a waste oil storage tank. 4

~

Amendment I 9.5-52 December-21, 1990 4, /g 3r 49d}

t bu) 0 8 i t l CESSAR-DC Attachment (Refer to page 9.5-52) v INSERT 1 i s j A set of level switches located within the day tank control the position of the fuel oil transfer valve: opening the valve to allow .) fuel to flow to the day tank at low level and closing the valve to shut off the supply of fuel at high level. !!igh and low level alarms are also provided both on the storage tanks and the day tank. In the event of a transfer valve failure in the closed position, the day tank low level alarm, indicating 60 minutes of .M fuel reserve at full load, allows the operator to take corrective l' action. In such an event, a bypass line allows for manual filling of the day tank. In the event of a transfer valve remaining.in the open position, fuel oil would continue to flow from the storage. tanks to the day tank until the system reached hydrostatic equilibrium. Since there is no day tank overflow line, oil would rise in the-Safety Class 3 day tank vent pipe to an elevation { equivalent to that of the fuel oil in the storage tank but well below the top of the vent. The day tank vent is missile protected. r A 1 ~.w.ver-v +w.v---ie c--ev,, .s.n-,r -~,,,y ,,.,..m .. + w+=--- n.--+. ---m, u ,e a a--.

CESS AR naib. jV' -4 Y woe"ho s g, Y ~ c (" ,q ADD N5g To -p reve nt-s et4Lingr-stra t i f-ica t ion-a nd-dete riora t ion-of-tho-f uel o i-1-d u r i ng - e x te nd ed -pe r-i od s,-a -s y s te m -i s-p r9v-i d ed-to-reo i rcu l a t e-o&t ra ns fer-f-14 tered-fuel-oi-1, Four-f41el-oil-ta nks-{two-ha-14 capacity storage ta nk s--pe r--re d u nd a n t---d ie s el-)--a re-c e n t ral-ly loc a t ed -a nd -i n t eg r-a 11 y-con nec t ed -w i t h -n orma14 y-olosed-is oittien v a l ves-a nd --oh eck-va lves-to-p r o ve n t-ba ck f411 ing-a nd--po ss i ble t contamination--of-fuel-oil betwoon-tankt A manually-operated, po s i t i ve-d i o pla ceme nt-rac i rcu l a t-lon-pu mp-ta kes-ouot ion-f rom-the -f l u s h - m ou n t ed -s a m pl e -co n ne c t i on-o n-t he-bottom-o f-th e-sto ra g e-t a nk a nd -d isch a rg e s-the--fu e l-o i4-th roug h a simplex-f-i-lter-w t a-lterna te-b ass-11nsdo-tha--storage-tank-f411-con eot4en. The 'ffItErfits an rhfitMW on a ank by tank basis with the frequency of operation dependent on the results of a fuel oil inspection program. Since two half capacity storage tanks are provideo per diesel, one tank will be aligned to supply fuel oil to its respective diesel, while isolating the second tank through administrative control. The contents of the isolated storage tank would be filtered anc recirculated. Prior to realigning the tank to its respective diesel, a period of not less than 24 hours is required to allow E any stirred sediment to settle. Should the recirculation system be operating in the event of a

LOCA, a

redundant, safety related interlock is provided to shutdown the recirculation pump to prevent possible stirring of sediment. A redundant safety-related interlock is also provided to shutdown the recirculation pump should the fuel oil in the storaga tanks drop below a level to preclude loss of fuel oil in the event of a recirculation system pipe rupture. These two safety-related and redundant interlocks protect the Diesel Generator Fuel Oil System during operation of the recirculation system. They assure uninterrupted operation of the essential emergency diesels in the event of a Loss of offsite Power or LOCA. Fuel oil amenders are added as necessary to extend oil life by preventing oxidation and stratification. A sample is used to inspect the oil for water content or degradation and if degradation is determined, the oil may be pumped out for disposal. Accumulated water in the fuel oil storage tanks will be removed by the recirculation system through a sample connection provided on the recirculation pump discharge. , W N~w j Th e-- d a y-t a nk-ve n t-a nd -f u e l-o i l-s t o ra g e-ta nk-v en t s-e nd-fiti f oonncotions-which-are-exposod-outdoors + -are-protected-f rom V,p tornado-missilos through-the-constructrion-of-the-vents-using { heavy-gau ipe-and-are located-above-the-nrobsb e-max-imum-f4ood -leve- 'fUl'NnYsM e with a loc Tng do's D ap I {- Amendment I 9.5-53 December 21, 1990

Lt. CESSAR-DC Attachment-(Refer to page 9,5-53) INSERT 2: To-prevent settling, stratification, and deterioration _of. the_: fuell j oil during extended periods, a system is provided-to recirculate or : [- _ ',' transfer filtered fuel oil. A separate and complete recirculation. system is provided for each set of half capacity _-fuel oil storage tanks. Each set of storage tanks shall be; integrally. connected with normally-closed isolation valves and-check _ valves to prevent-- backfilling and possible -' contamination of the fuel oil - between tanks. A manually operated positive displacement pump provided-for each set of storage tanks takes - suction from the flush mounted- ~ sample connection on -the bottom of the' storage tank and diacharges-the fuel oil through a simplex filter with alternate _ bypass line to ~ the_ storage tank fill-connection. INSERT 3: The day tank vent and fuel oil storage tank' vents- - and fill connections which are exposed outdoors-are constructed using-_ heavy {i. ga'uge pipe to provide protection against: tornado missiles. These = vent and fill ~ lines are located above the_ probable maximum flood k - level. E 4 __.__.-_-___..u__

CESSAR na%mos Atx 4 ~ T and each vont line is down turned. The storage tanks can be filled and vented through the manway should the fill or vent lines become impaired. Compnent Description 9.5.4.2.2 y -Fuo-1-io-roolrculated-wi-thin--the--stora e-datriorstiondy~a-a:eo2rsnetM:2uz - The motor-driven fuel oil booster pump is normally isolated, both electrically and mechanically, but may be operated if required during maintenance to deliver fuel oil to the diesel. E 9.5.4.3 Safety Evaluation The Diesel Generator Engine Fuel Oil System is a ANSI Clasu 3 piping system with the exception of the Fuel Oil Recirculation System and the fuel oil storage tank fill line strainer which are ANSI Class 4 piping systems. The Fuel Oil Recirculation System and the fuel oil storage tank fill line strainer are separated from the essential Diesel Generator Fuel Oil System by normally closed ANSI Class 3 isolation valves. An ANSI Class 4 flexible rubber hose is used to connect the ANSI Class 4 fill line strainer to the ANSI Class 3 fuel oil storage tank fill lines. The diesel engine and engine mounted components are constructed in accordance with IEEE Standard 387. The fuel oil system is designed and constructed in compliance with ANSI Standard N195, I I in regards to the flame arresters on the storage tanke exce t a gne do y +W< ed e.sclu ding Mi references h Me.n l diese$ grog he.gbnerator unit is housed separately in a seismic ogcc o Each Category I structure. Diesel fuel oil 2D, as specified by ASTM D975, is normally delivered to the site by private carriers. The fuel oil storage E capacity is based on continuous operation of the diesel generator engines at rated load for a period of seven days. A 10 percent margin in storage capacity is provided to preclude the necessity of refilling the tanks following routine performance testing. The exterior of carbon steel tanks and other underground carbon steel components is coated. In addition to being coated, the external surfaces of buried metallic piping and tanks are protected from corrosion by an impressed current cathodic. l protection system in accordance with NACE Standard RP-01-69er oN e st+c. specioc cona:nns. o deemed accoF;.4e. base 2 on enmns The interior of the fuel oil storage tanks are not coated since the presence of fuel oil will act as a deterrent to internal corrosion. Requirements assure that the fuel oil storage tanks are maintained essentially full to provide a seven day supply. W AmendmentjIi 9.5-54 'DodembEr 21, 1990 %f,f 7.- oe

_ _ ~. + pg /YM 'CESSAR-DO Attachment (Refer to page_9,5-54) INSERT 4: Fuel oil is recirculated by a recirculati.on pump - within each storage facility to prevent deterioration. 1 + 4 1 I j =.

CESSAR EnMcuieu h a2 47T The starting air receiver tanks also supply air at reduced pressure to the engine control panel instrumentation. Air enters the engine control panel where it is filtered and a self-contained pressure regulator maintains constant pressure for the diesel automatic safety shutdown system. The automatic safety shutdown system is made up of a network of vent on fault pneumatic devices which monitor the engines parameters, tripping the engine when a manufacture's recommended temperature, pressure, overspeed, or vibration set.o t has bet m ded There are two types of ep ine trips Group ' ATC_tr-ips-are-act ve -onTfGGFiW We 4, TrTodfo g'stEg o%the-dlesel-to-prevent-damage-te C -to-t he -e ng i ne-a nd -a re-l ocked -eu t-d u r i ng-the-eme rg e ncy-mode-(-i, e,, a Loop-or-LOCA)--allowing-the-engine-to-continue-to-run, Group-ttAl' t ri p s-i nc ludo-a nd -a r e-a c t i va ted-u pon s--l-ow-1pbo -o il-pres su re,--low p $ def t-and-right-turbocharger-oil-pressure, high crankcase e x ce s s i v e-eng i n ew1 bra t4c n, --h ig h-lu be-o i4-t empe ra tu r e, h, g pressurer - h i-g h--t e mpe ra tu r e--ma4 n-be a ri ng s, a nd-h igh-high jacket-water-o tempera ture, Group nBn-tr-ips-remain-act4ve-dur4ng-the-emergency- @ -mode-to-ohutdown-the-engine-should-a-setpoint-be-exceeded,-Group-u a n-tri p s-i nclud e--e nd -a re-a c t-iv a ted-u po n 1-e ng i ne-ove rspedy -low-low-lube-oi4-- ressure and-9,enerator-d1f fe e t4a1, /Ke i 4 ow-low ue oil pressure trip conta na reduncfant wo out of three) logic which must be affected to activato a diesel E chutdown. The pneumatic logic for Group "A" and "B" trips consumes negligible volume, operating on pressure rather than flow capacity. Sufficient air pressure remains available for operating he neumat' o D1 owin h egiv start a gttem ts. ,In-a ~ lon7-the-s artIng-air-compressoro -aDryers, r (21-tercoo ers, piping and--valvoo are seismie Gategory-I, se i sm ica ll y-qu ali-f4ed-to-r emain-o pe ra bl e-f ollow-ing-a-de s ig n-ba sis-. earthquake. The-s ta r t-ing-adr-comp res s ore-a nd-ale-d rye ro-r eceivo. C - Class-1E-power-f-rom-their-associated-diesel. ( i Relief valves on the compressor discharge line and on the air rocciver tanks protect the starting air system from overpressurization. 9.S.6.2.2 Component Description AO lu SER.T '2. ~ h,h e-s ta r t ing -a ir-compre s so r s -ere-d ri-ven-by-e4eo tr i o-motors -wh ich ('.- 18re--pyv3-f-rom-the-Essentglyuxigiarg-gSu ply [,ach compressorMscharges compressed air and the heat of compression is removed by a water-cooled aftercooler. The component cooling water system provides cooling water on the tube side. To minimize the accumulation of moisture, the diesel engine starting air system is ei]uipped with -a multi-stage drying and filtering unit -located in line between the af tercooler and the receiver ta nk.. The air is first -thrown-through a cyclone-type (+u song Mr A (1. mud h b p M <xA \\ee M io*F l owe.e b- .% gc // h \\ owed e.9tA ed %bied 4 e qc c edee. Amendment E '1F p/f' ~ ~ (/' ' 4 5 9.5-64 ,_ December-30 r1988 .ch (y _J % =. (_j J,a y, td 4 L

d6 ^t &^ CESSAR-DC Attachment (Refer-to-page 9.5-64)- INSERT l_1 t Group "A" trips are active only during the periodic testing of the diesel to prevent damage to the engine. These trips are locked out-during the emergency mode (i.e. LOOP or LOCA) to allow the engine to continue to run should alarm conditions exist. Group "A" trips include and are activated upon the following: 1. Low Lube Oil Pressure. 2. Low-Left and Right Turbocharger. Oil Pressure. 3. High Crankcase Pressure. 4. Excessive Engine Vibration. 5. High Lube Oil Temperature. 6. High Temperature Main Bearings. 7. High-High Jacket Water Temperature. 8. Generator Instantaneous Overcurrent Protecton. \\C- ' 9. Generator Loss of Field Protection, l-10. Generator Reverse Power Protection. 11. Generator Ground Protection. Group "B" ' trips remain active during all diesel generator operational modes (test and emergency) to _ shutdown the_ engine should a setpoint be exceeded. Group "B" trips include and are-activated upon the following: 1. -Engine Overspeed. 2. Low-Low Lube Oil Pressure. 3. Generator Differential. 4. Generator Voltage-Controlled Overcurrent (Protection from external faults). INSERT _2: k q\\ - The starting air compressors are powered from a non-Class lE' motor control center. During a loss of offsite power,.the. starting air i compressors-are powered from the alternate AC (AAC)-power _ source.

hL u emy CESSAR ots,en ccouncuion 9.5.6.5 Instrumentation Application Each starting air receiver is equipped with a set of pressure switches which control the operation of the air compressor on its associated train; starting the compressor on low pressure and stopping the compressor on high pressure. Pressure gauges are i(p located on the tanks for local indication, with-a-low-pressura

ala rm.

A separate pressure switch on the engine control panel alarms if the air receiver tank pressure falls to a low setpoint. If the starting air pressure to the starting air manifold drops to a specified value with the engine failing to start, an E automatic lockout will prevent further start attempts and an alarm alerts the operator to take corrective action. The automatic lockout ensures there will be sufficient reserve for a manual restart. All starting air system alarms are annunciated separately on the local diesel engine control panel and signals a general diesel trouble alarm in the control room. The periodic testing and maintenance of all diesel engine y starting air system instruments is controlled by a preventative maintenance program. This program insures that instruments are E periodically calibrated and tested, assuring reliability. ^ Anedace is pewided o.h the_ bccd diese.l genere-.%c cc m 4co l p a.n e l b cdec+ person n e i LA e-n he. cuc pres 50ce. c!cets below ce pre sef scJue. v e,/ ,p .e. n 1 f V {J i M"+ Amendment <I 9.5-66 December 71 M 996 c i <. m.,~

CESSAR Embuou /bemM 9.S.7 DIESEL GENERATOR ENGINE LUBE OIL SYSTEM 9.5.7.1 Design Bases The Diesel Generator Engine Lube Oil System in designed to deliver clean lubricating oil to the diesel generator engine, its bearings and crankshaft, and other moving parts. By means of E heaters, the lube oil system is designed to deliver warmed oil to the engine during standby to assure its fast-starting and load-accepting capability. The system also provides a means by which used oil may be drained from the engine and its components, and replaced with clean oil, essenkt A114 components and piping are located within a Seismic Category I l[ structure (diesel generator building) and all essential I components are fully protected from

floods, tornado. missile damage, internal missiles, pipe breaks and whip, jet impingement y

and interaction with non-seismic systems in the vicinity. 9.5.7.2

System Description

The Diesel Generator Engine Lube Oil System is shown in Figure rs 9.5.7-1 (Sheets 1 through -4). 9 9.5.7.2.1 General Iveshed Each diesel generator unit utilizes the " dry sump" lube oil system, in which the supply of lubricating oil for the engine is {p stored in a separate sump tank, independent ' of, and %et-at a lower elevation than the engine crankcase. As oil accumulates in the crankcase, it drains by gravity into the sump tank. Additions of clean oil are made to the sump tank from a storage tank located underg round and outside the diesel generator (M

building, and used oil is removed from the sump tank via a y

eneuder he.s a. g transfer pump to a used oil storage tank. EacA Cese]f r complete. clem tube. on w ud hh od &es sy stem. sepr.ae ed engine-driven lube oil pump picYs'dNIDfrom the sump tank The through a built-in suction pipe with foot valve and delivers the oil in sequence from the pump discharge first to the oil pressure regulating valves which limit the maximum pressure on the pump discharge, and then in series through the lube oil cooler, the full-flow lube oil filter and finally to the full-flow lube oil strainer. From the strainer, the oil enters the engine internal circulation system. During engine standby, the motor-driven prelube oil pump operates continuously to ensure complete filling of the lube oil system. Oil which is circulated by the prelube oil pump passes over a set of thermostatically controlled electric heating elements before p Amendment F 9.5-67 December-21,~1990 rlL 3C,! G9 7:

CESSAR1ln h ou Mh9W ^ leaving the sump tank 'to maintain ~ the engine in aEwarmed - state. From the _ prelube_ _ oil pump, : the ; oil passes - in series through the prelube- _oll' filter, the prelube oil" strainer and enters the: engine internal circulation system. A separate._ drip lube system provides a continuous, metered ' flow of oil to the turbocharger-bearing? during engine standby to ensure-adequate bearing lubrication for startup. The diesel generator engine crankcase is vented to the atmosphere-through the roof of the Diesel Generator Building. The lube oil filters and strainers are also vented, but into the room itself. The lube oil sump tank is vented to - the atmosphere-through' the roof. The crankcase is equipped with ' blowout panels to prevent high pressures from damaging the engine. ME L ~ =- T o f-th e-l u bo-o i-1-s tor ag e-ta nk-lo-prov id ed -w ith-a n .i nd iv id u a l-f-ill-a nd-ve n t-1-i n e-l oca ted -ou td oo rs, To-prevent, 3!- -entra nc e 4 f-wa te r-i n to-th e -s torag e-ta nk s-the-ve n t-a nd-f-141-14nes 4 -ter m i n a t e-a bove-g ra d a-e leva t l on. The-fill-connectlon is-prov.ided -with-a-locking-dust-4 Each diesel is provided with a lube oil sump-tank. The sump tank is equipped with a low-level alarm which is: set below the normal-7 operating level. With an established oil consumption at full. E-load, this volume is sufficient ' to operate the - diesel rin excess of seven days without requiring replenishment. Should it become necessary to make additions of lube oil to the

diesel, lube-oil is available-in a'

storage tank located winderground-and, outside: the-Diesel Generator Building.- A-manually operated, positive displacement _ clean ~ lube oil pump takes suction from the storage tank -- and discharges - lube. oils through' a simplex filter to tho' intended diesel. The-pump suction is rais_ed above the storage tank floor to prevent any- --accumulated water from entering the ' diesel. lube : oil sump tank.- Accumulated water in the bottom of the storage tank is removed through a sample connection flush on the bottom'of storage tank. The lube oil in the clean lube oil storage tank 'is inspected . monthly'to determine the purity of the_oll. Parameters monitored include viscosity, neutralization

number, and percentage of water.

'Any accumulated water detected in.the bottom' of the l storage-tank will be removed. _If degradation of the oil is-detected, the oil may be pumped out for-disposal. Lubricating oil leakage is detected by: A. Routine surveillance Amendment E' 9.5-68 December 30, 1988._ r d.;, f 30: A9% ._,u_

,b L Q)1 Af'? ? CESSAR-DC Attachment (Refer to page 9.5-68) INSERT 1: The clean lube oil storage tanks are provided with individual fill, drain, and vent lines located outdoors. The used lube oil storage g# r tanks are provided with individual drain and vent lines located l outdoors. All vent lines terminate above grade elevation and are down turned. The fill and drain connections terminate above grade elevation and are provided with a locking dust cap. _---_a

LCESSARj8annemou /bg-vW w The used lube oil transfer pump transfers oil from the used lube-oil storage tank to a truck or tanker for disposal.- The pump is7 driven by an electric motor. J The clean and used lube oil transfer pump motors are powered-from the Station Normal Auxiliary-Power Supply. 9.5.7.3 Safety Evaluation The Diesel Generator Engine Lube Oil System is an ANSI Class 3 piping system with the exception of the Clean - and 'Used Lube - Oil Transfer System which is an ANSI Class 4 piping system. The two systems are separated by ANSI - Class 3 isolation valves. The diesel engine and engine mounted components are - constructed in; accordance. with IEEE Standard 387. Tho' off engine essential-equipment and components and the nonessential-(i.e., ,Cle.an. - and -- Used Lube Oil Transfer System) equipment and components _ are; designed in accordance with the requirements of the ? applicable codes. ADD 14SE T 2. -The-exter4cr-of-carbon-steel tanks-and-othor-underground-earbon -steel--componente ic -candblested-te a GGPG-6P10-63 -Near-White-7 -Metal-Blast-C4eaning1 ?. coal-tar-epoxy-coat 4ng-which-meets-the enquirements-of Oorps-ef--Engineers Specificet-is C= 2OO-a nd-Government Speci-f4 cation-HIL-P 23236--is app 14ed to-extericr 1 E .surfaoos-at-e-dr-y-f-ide-thickness-of 15 mi4sr-This-coal-bar - cpoxy-4 s-als o-a pp14ed-to-the-exte rior--o f-sta-isless-e teel-pipi ngs -I n-a d d 1-t ion-to-being-coa t edr-th e-exter nal-s u rfaces-o f-bu r-led- -mete 444e-piping-and--tanks-are-protected-from-oor-rosien by an-F 4epressed-our-rent-ca thod io-prote ction-system-in-a ocorda nce-with- -[ -NAGB-6tandard-RP-01-50 Pordedie-mon-itor-ing, 00 deser-ibed-by-the- -maintenance-procedure, ui4-1-rencyc any-accumulated-moisture-furom (JJ? -the-tanks, ~ The governor lube oil coolers on the. diesel generator engines are located at an elevation below the governor lube. oil -level,- thereby,_not affecting the-starting reliability of the engines. The interior of the clean lube oil' storage tank is -- not _ coated since the presence of lube oil will act - as a deterrent to internal corrosion. During the surveillance intervals for -sampling the lube oil-in the storage-tanks, any accumulated' water will be removed. 9.5.7.4 Inspection and Testing Requirements System components and piping are tantad to pressures designated by appropriate codes. Inspection and functional-testing - are performed prior to initial operation. g /} tpf f-Amendment,E 9'.5-70 Decembe r-3 0, -19 8 8-N([k 3 OddD

= -QS-09 N CESSAR-DC-Attachment (Refer to page 9.5-70)- INSERT 2: The' exterior of carbon steel tanks and other underground carbon-- steel components is coated. In - addition to~. being coated,-- the external surfaces of buried metallic _ piping and-tanks are protected-from corrosion by an impressed current cathodic protection system / in accordance.with NACE Standard RP-01-69 or other means as deemed-- appropriate based on site specific soil conditions._ Periodic monitoring, as described by the maintenance-procedure, will_ remove - any accumulated moisture from the tanks. i

CESSARJ!n%mer AWeWp7 9.5.7.5 Instrumentation Application Each -diesel generator enginc. _is provided: with sufficienti instrumentation and alarms to monitor-the. operation of.the lube _- -oil system. All-alarms are separately annunciated on the local diesel engine control. panel which-- also L signals _ a general diesel trouble alarm _ in the control room._ _ The - lube oil system is provided with the following instrumentation and alarms: The lube oil sump tank is equipped with_a-local-level _ indicator-along with a low level annunciator to alert the operator to take corrective action. The full flow filters are equ'ipped with locally-mounted'_ pressure gauges. A high diffcrential pressure alarm alerts the-operator to manually switchover to the alternate clean filter; there is~_ng bypasslme. ,4 The engine mounted-full flow straine s are -equipped with a high differential pressure = alarm which alerts the operator _ to manually 3 switchover to the alternate clean strainer; there is no bypassline. Q f su<r - t The diesel generator engine is equipped with both temperature and pressure monitoring systems with separate alarm and' trip' switches- _$~ l to alert the' operator - ' of abnormal operating conditions. p If -. a shutdown setpoint/ alarm is exceeded while_the engine.is op4 rating-during the test mode, a diesel trip _will automatically ' shutdown E-the engine to prevent incurring any damage.

However, if such a

shutdown / alarm--is _-received during the emergency mode (i.c., LOOP - or LOCA) _ the-; trip is lockedTout L and the engine continues to.run. The ; alarms _ alert. the operator. to prepare to-switch;over to the redundant diesel fortpower. Only as low-low engine lube oil pressure :-shutdown / alarm -will trip - the engine regardless of the diesel operating mode.- The engine inlet and outlet lube oil - temperatures are _ also recorded by-a multipoint recorder and may be monitored-by-a multi-channel pyrometer (in, manual. mode). Both the recordercand pyrometer _ are located ' on~ l the generator control panel: in; the diesel generator:-building. { The periodic testing and. maintenance of all diesel engine lube: oil system instruments -is controlled by a-preventative -maintenance program. This ' program insures that- -instruments are periodically calibrated and tested, assuring-reliability. A 9h > ~

a6 1

. / c Amendment E^ b .9.5-71 cDecember-30r 1988' A LC. 'la, m t

CESSAR nn%mos / hse a F+ 9'.5.8 DIESEL GENERATOR ENGINE AIR INTAKE AND EXIIAUST SYSTEM 9.5.8.1 Design Bases E The Diesel Generator Engine Air Intake and' Exhaust System is designed to supply clean air for combustion to the diesel generator engine and to dispose of the engines exhaust. The system is housed in a building designed to withstand the effects of natural phenomena and credible missiles. All components and piping are located within a Seismic Category I structure (diesel generator building) and all essential components are fully protected from

floods, tornado missile damage, internal missiles, pipe breaks and whip, jet impingement and interaction with non-seismic systems in the vicinity.-

t 9.5.8.2

System Description

The Diesel Generator Engine Air Intake and Exhaust System is shown in Figure 9.5.8-1. 9.5.8.2.1 General Each diesel generator is provided with a two pipe combustion air intake system < Combustion air is drawn in through in line air filters prior to entering the turbocharger. Each diesel generator is provided with a two pipe exhaust system. The waterjacketed exhaust manifold discharges directly into the engine-mounted turbochargers. The exhaust piping then joins to E pass through a single exhaust silencer and exits-the building. Outside air intakes are located at one end of the building and exhausts (both Diesel and-Ventilation System) at the opposite end of the structure. The intake and exhaust structures are separate for each diesel building and are similar in design. Each intake and exhaust structure is served by a -ISO 4-capacitt floor drain. 1P-In addition a sump, formed by the curb at the bottom of the intake and exhaust structures, provides capacity for preventing accumulation of snow, ice, or freezing rain from interfering with emergency diesel generator system operation. 9.5.8.2.2 Component Description The turbocharger, driven by the hot exhaust gases on one side, compresses the intake air on the other side and forces it through the engine aftercooler. p Amendment ( 9.5-73 December ~21, 1990 'O -{@f '}C, s' T T-t

r i CESSAR nai"icariss .hapa P The aftercooler removes heat from the compressed intake air, E decreasing the air temperature. Cooling water flows through the tube side and its temperature increases. There are no active components in the air intake and exhaust i system. 9.S.8.3 Safety Evaluation The Diesel Generator Engine Air Intake and Exhaust System is an ANSI Class 3 piping system. The diesel engine and engine mounted-components are constructed in accordance with IEEE Standard 387. The off engine essential components are designed in accordance with the requirements of the applicable codes. The intake E p, filter, intake silencer, and exhaust silencer are+ASME Section f~ III Class 3 code approved. These components are seismically qualified by shaker table tests or analysis performed

by 'the manufacturer.

The components are installed in the diesel generator building with Seismic Category I restraints. not-The intake air plenum and the exhaust gas plenum for each diesel generator unit are at opposite ends of the diesel generator building. This fact and site-specific analysis of the diesel I generator engine exhaust will establish that the rise of exhaust gases is suf ficient to preclude the possibility of recirculation to the point that system integrity is jeopardized. Normal ventilation flowrate is 5% of the diesel run mode ventilation flowrate. Normal ventilation is filtered to maintain engine room cleanliness. All diesel generator building-interior surfaces are painted to minimize concrete dust. Diesel intake air is taken at E 3 a height of +O feet above grade to minimize the intake of dust. 20 P r-i ma r y-f-i-re-proteot-ion-is-prov-id ed-by--a n. automat-ic--carbon t b -dioxide-system. Thwystem-is-a c t-iva ted-by-t empera tu re-d etector -~ -which-a-lar to-in Onsite storage of gases is discussed in Section 9.S.10. These gases are stored at a distance from the diesel generator building such that there is no threat to the proper operation of the y diesel engines. 9.5.8.4 Inspection and Testing Requirements System' components and piping are tested to pressures designated by appropriate codes. Inspection and functional testing are E performed prior to initial operation. 9.5.8.5 Instrumentation Application Each diesel generator engine unit is provided with sufficient instrumentation and alarms to monitor the combustion intake and N Amendment J i l 9.5-74 Dece_mber 21,-1990 u Y Af V;(9l~

CESSAR !!ahnen Au~'s aR exhaust system. A multipoint recorder on the local generator control panel records the individual cylinder exhaust temperatures and the inlet and outlet turbocharger exhaust temperatures. A pyrometer, also on the local generator control

panel, automatically monitors each cylinder temperature and compares it to the average temperature of the other cylinders.

The pyrometer will annunciate a high/ low temperature alarm on the local diesel engine control panel and signal a general diesel trouble alarm in the control room if a cylinder temperature exceeds the average temperature differential setpoint, with the E pyrometer automatic sequencer stopping to display the out-of-tolerance cylinder. A high or low exhaust temperature 7 will not+ef-fect-a trip on the engine. A manual advance is also b provided on the pyrometer to allow each individual cylinder to be checked as well as the inlet and outlet turbocharger exhaust temperatures. The turbocharger temperatures do not affect the cylinder temperature averaging circuit. - ini &d e. -ph - fe e /r Amendment.E' (,' } 9.5-75 De ce_mber-3 O','19 8 8 >,Lk ' )bb y

i t u s

Insert'B k

' k'- r i 11.3.7 GASEOUS WASTE MANAGEMENT SYSTEM LEAK OR FAILURE -11.3.7.1 Identification of causes and Accident Description The Gaseous Waste Management System (GWMS), as discussed in-section 11.3 designed to. collect, monitor, and store radioactive waste gases which originate in the reactor. coolant - system.and require processing by holdup for decay prior to release. The GWMS utilizes ambient temperature charcoal adsorption beds to provide suf ficient decay of noble gases. The accident is described as an -unexpected and. uncontrolled release of rad. Tactive Xenon and Krypton gases from the GWMS resulting f rom - an inaavertent' bypass of the main decay portion of the charcoal' adsorber beds. It is assumed to take as long as 2 hours to isolate or terminate the release. 11.3.7.2 Analysis of Effects and consequences A. Bases 1. The assumptions and methodology are consistent with guidance provided in Branch Technical Position ESTB 11-5, 2. An ef fective holdup time of 30 minutes is assumed for the bypass flow to account for transport time of the gases through the GWMS components via the release point to-the' nearest exclusion area boundary. 3. In accordance with ESTB 11-5, the Waste Gas System maximum design capacity source term (at sustained power) is assumed to seven times the source term considered for normal op6tation, including anticipated operational-occurrences, PWR-GALE is run for a 30 minute decay case and the results are multiplied by seven to calculate-the maximum design capacity source term. 4. The total _ source term is equal to.the maximum design basis source term plus the normal operations source term. shown in Table 11.3-4. 5. Particulates and radiciodines are assumed to be removed' by protreatment, gas separation, and interiaediate radwaste treatment equipment. Therefore, only the whole body dose is calculated in this analysis. W Page 1 of 2

y,Y +9 Innort-B (cont ' d) 6. In the absence of site spe ific meteorological data and exclusion ' area boundar" nformati. i, an atmospheric dispersion factor (X/Q) of 1,00 x 10-3 is assumed f or the { c/d exclusion area boundary (500 meters ~. ased on Chapter 15, Appendix A. B. Methodology To calculate the dose consequences for'a Waste Gas System failure methodology consistent with Branch Technical ESTB 11-5 is used, E K(i) Q (i) -

X/Q
7.25 D

= Where: Dose (mrem) D = the total-body dose factor given id K (i) = Table B-1 of Regulatory Guide 1.109-for 3 the.i"' isotope (mrem-m /pCi/yr). the noble gas nuclide release -rate for Q(i) = the i"' isotope (Ci/yr) atmospheric dispersion -4; ctor at - the X/O = exclusion area boundary ^ M' - A u, V- \\ eta 1.00 x 10 /m I 3 X/O = s 7,25 = conversion factor for 2 hour release 2 1 (pCi-yr /Ci-event-sec) C. Results and Conclusions The resulting Exclusion Area Boundary noble gas dose to the whole { Cid body is 29.8 mrem. This_ meets the guidelines specified in the Standard Review Plan Section 11,3. Page 2 of 2

I e i - Insert A-11.3.8-Concentration of-Normal Effluents The Gaseous Waste Management System (GWMS), processes gaseous _ waste _ through a charcoal ' delay system which holds-up noble ' gcses1 and -- allows'them to decay prior to release. The concentiation at ~ the exclusion area boundary during normal operation, -including anticipated operating occurrences, _ was-analyzed to verify it' is less than 10 CFR 20, Appendix B, Table II, Column-1. 11.3.8.1 Analysis of Effects and Consequences A. Bases The bases for the estimated concentration ' of ef fluent -are as follows: 1. This system continuously discharges at a unifora rate. 2. The concentration of the ef f' ent is based on the design basis source term. 3. The_ total gaseous effluent calculated using NUREG-_0017 methodology. shown in Table 11.3-4 is multiplied by seven: -to yield a conservative approximation of the design basis;. source term. This methodology is - consistent-with the suggested methodology _in Branch Technical Positi'on ESTB 11-5 for a Waste Gas. System-Leak of Fai' lure consequence analysis. 4. In the absence.of site specific meteorological-: data and-site Exclusion Area Boundary _( E m tion, an -[ CN 's ' atmospheric dispersion factor of -1.00: x 10 i s/m-was_ on c apterL15,_ assumed -- f o r the EAB (500 meters) baseo $II 3'-~ II) dNpi. Appendix A. B. Methodology i (- The methodology used to calculate the concentration of the ef fluent L at the Exclusion Area' Boundary is as follows: C (i) CF

7R (i)

X/Qm = L Where: C (i) = a Conced' zition of the-i" isotope at the - EAB-(pCi/ml) W ' f. J Page 1 of 3

T ri c.e rt A (cont ' d) CF e Conversion Factor 2 3.17 x 10'" (s-pci-m /yr -O A-ml) - = R(i) a Release Rate of i" isotope (Ci/yr) A- - spha dispersion factor at EAB ( s /m') X/Qu, = 1.00 x 10-3 (s/m ) k 3 = C. Results and Conclusions ~ 'h kW. The concentration of the ef fluent at the Exclusion Area Boundary is shown in Table 11.3-S. The concentration at the Exclusion Area Boundary is well within 10 CFR 20 guidelines. Although there are -periodic purges of containment during normal operat. ion, these purges will be controlled - by precedures developed by the Owner Operator to ensure compliance with 10 CFR 20 limits. 6

l 1 CESSAR E!!Wricariou TABLE 11.3-1 SOURCES, VOLUMES AND FLOW RATES OF STRIPPFD GASES FROM THE PRIMARY COOLANT Flow Rate (1) Annual Volume (2) Waste Cas Source (SCFM) (SCP/yr) PROCESS GAS HEADER (HYDROGENATED) CVCS Gas Stripper .32 145,000 Volume Control Tank .004 1,624 Equipment Drain Tank Reactor Drain Tank (3) .02 7, V 59, PROCESS VENT HEADER (AERATED) Blowdown Recycle IX (2) 32 112 Purification IX (2) 32 112 Deborating IX 16 56 ( Lithium Removal IX 16 56 Pre-Holdup IX 16 56 Boric Acid Condensate IX 16 56 Liquid Waste Process IX (6) 96 336 I Boric Acid Concentrator 1 2,626 Reactor Makeup Water Tank 22 127,480 Holdup Tank 22 127,480 Boric Acid Tank Laundry & Hot Shower Tank (2) 7 17,567 Floor Drain Waste Tank (2) Equipment Waste Tank (2) Waste Monitor Tank (4) 7 53,325 h Spent-Restn)(Tank 2 M')\\_ 22 - 1,-337 % Drain Tank (,2 / POWdex Sterage Tank 22 1,35i as-frtrTfper Vent Process Gas Adsorp'n Bed Drain f ~~~-#- Misc. Vents and Drains 4 Qg,g NOTES: (1) Flow rates are estimated maximums, not continuous. (2) Volumes include anticipated operational h occurrences, l s s e

f. y )

Amendment 'I kfp 4 December 21, 1990

G l Tablo 11.3-5: Average Annual Concontration - of Gasoous / Effluents at the Exclusion Are Boundary (a) C (i) MPC (i) Nuclido DuCi/ml) 0uCi/ml). FMPC (i) j 1-131 3.99E-15 1.00E-10 3.99E-05 I-133 1.20E-14 .00E-10 2.99E-05 Kr-85M 8.87E-13 .00E-07 8.87E Kr-85 1.71E-10 .00E-07 5.69E-04 Kr-87 8.87E-13 00E-08.4.44E-05 Kr-88 1.77E-12 f.00E-08 8.87E-05 Xe-131M 3.55E-11 14.00E-07 8.87E-05 Xe-133M 2.22E-13 3.00E-07 7.39E-07 hgg) Xe-133 1.57E-11 3.00E-07 5.25E-05 tj i f. /"' V Xe-135M 8.87E-13 3.00E-08 2.96E-05 Xe-135 5.32E-12 1.00E-07. 5.32E ) Xe-138 8.87E-13 3.00E-08 2.96E-05 Cr-51 7.32E-18 8.00E-08 9.15E-11 Mn-54 4.44E-18 1.00E-09 4.44E-09 3 Co-57 5.32E-19 6.00E-09 8.87E-11 l Co-58 6.65E-17 2.00E-09 3.33E-08 + co-60 2.13E-17 3.00E-10 7.10E-08 2.00E-09/9.54E-10 Fe-59 '1.91E-18 3.00E-10 5.2SE-08 Sr-89 1.57E-17 Sr-90 6.21E-18 3.00E-11 2.07E-01 Zr-95 2.44E-18 1.00E-09 2.44E-09 Nb-95 6.65E-18 3.00E-09 l2.22E-09 Ru-103 1.24E-18 '3.00E-09 4.14E-10 k Clad Ru-106 2.22E-19 2.00E-10 1.11E-09 I l-L Sb-125 1.35E-19 9.00E-10 1.50E-10 i l Cs-134 7.32E-18 4.00E-10 1.83E-08 Cs-136 2.22E-18 6.00E 3.70E-10 Cs-137 1.29E-17 5.00E 2.57E-08 i Ba-140 1.40E-18. 1.00E-09 1.40E Ce-141 9.54E-19 5.00E-09 1.91E-10 H-3 2.66E-10 2.00E-07 1.33E-03 C-14 1.62E-l' .1.00E-07 1.62E 7 Ar-41 7.54E-1. 4.00E-08 1-.89E-04 Stal: 2.57E-03 MPC 4 ',y VE %4 A.~. ~$ d (a) Based on the design basis source term. .Page 3 of 3 g h

i W CESSARin Luon gW _ y (V v ] (i y ( ( 1.v -{ O *r p - \\ 11.4.2 SYSTEM DESCRIPTION 11.4.2.1 General Description functions of the SWMS include providing means _ by which Primary inputs from the LWMS and primary letdown systems are processed to as well ensure economical packaging within regulatory guidelines, as handling dry, low activity wastes for shipment to a licensed burial facility. The pcudex t nh and-spent resin tank trains provide settling capacity for radioactive cchr t p ru d::. and bead resins yl transferred from various demineralizers. Capability is provided for solidification of dewatered resins or sluicing to containers approved for shipping and disposal of dewatered ion exchange resins.

Also, connections are provided for-use of, vendor supplied services such as rapid dewatering or waste drying systems when it is determined that the use of these methods represents a savings over the permanently installed alternatives.

A shielded onsite storage area is provided to allow for interim lJ storage of higher activity packaged wastes. The facility is sized such that it is capable of storing the maximum number of full shipping containers generated in any six month period ( containing the greatest expected waste generation. The process include a dedicated overhead crane with direct and storage areas access to adjacent truck bays with suf ficient overhead clearance facilitate direct trailer loading of waste packages. Crane I to operation may be performed remotely with the aid of crane-mounted video cameras or locally to provide additional flexibility. Building space is also provided to sort miscellaneous contaminated dry solids from uncontaminated solids for appropriate and cost effective packaging and disposal. Miscellaneous solid waste consisting of contaminated and other lJ or potentially contaminated rags, paper, clothing, glass, small items is received by the Solid Radwaste System when it arrives at the low-level handling and packaging area. Although waste forms are segregated and bagged at generation points I throughout the plant, this area provides space where the waste is further segregated (e.g., compactible versus non-compactible, radioactive versus non-radioactive) on sorting tables. When a sufficient quantity of contaminated waste has been accumulated, the compactor is operated. Radioactivity of filled containers-is f / Amendment J 11.4-5 , April 3 0, -19 9 2 A. W M % /4fZ

CESSAR! anne-4 i I monitored so that proper handling,. storage, and disposal are assured. Filled containers may be stored in the low-level package storage area until shipped. 11.4.2.2 Components Description-Design parameters for the equipment in the SWMS~are provided in Table 11.4-1. Component arrangement is shown on-the system flow diagrams provided in Figure 11.4-1 (Sheet 1 and 2). 11.4.2.2.1 Spent Resin Storage Tank A<w -Two-stainless steely GMC gallen= spent resin storage tanks with conical bottoms hold resins from radioactive or _potentially radioactive plant demineralizers. Non-clogging scree'ns prevent the flow of resins out of the tank through the~ spent resin tank dowatering pump suction lines and the service air injec'tio'n and vent lines. Multiple spent resin. tank dowatering; pump suction I screens are provided on'each spent resin storage._ tank to reduce the possibility of clogging-when operating-the spent resin dewatering pump. . Instrumentation which monitors resin.and. water levels in the tank and resin water content is read from a remote I panel located in the.radwaste control room. Normally, the-tank is vented-to the room exhaust duct whichlis handled by the Radwaste Building filtered exhaust system. During resin transfers, the vent -line is closed-to _ allow-. tank pressuri::ation. A . relief valve _on each tank prevents overpressurization due to service air-pressure.: regulating L valve failure. Resin transfers may be terminated from: the' control ~ room or the dewatered waste processing area; using an emergency cutoff to actuate valve closure in the resin' transfer line _ and service air supply to the-spent-resin storage l tank. D4 Powdex Storage-Tank The powdex st'brage tank is a 30,000 gallon. tank which L receives radioactive powdex % c (the condensate ion exchangers. TheLtank provides capacity for hoIttu and settling of powdex ' before -it is lJ is a stainless steely right processed and shipped. The n(1'x-ing of M the powdered re. sin cylinder with a conical bottom. prior to sampling is provided by a recirc Kuon,line and a fluid powered-mixer. Multiple connections are pr ded for' tank I g dewatering, -and the Instrumentation _ monitoring pow evel ~ in s H .k- - \\ the tank is read from a remote panel located in the ra te \\controlroom. \\ x A / Amendment J 11.4-6 April 3,0, 1992

CESSAR !!n% mon i .2.3 Powdex Dewatering Pump The pump apable_of recirculating storage tank contents for resin mixing o ansferring decant to the LWMS. Material of construction is at less

steel, and the pump controls - are C

located in the radwaste trol room. 11.4.2.2.4 Powdex Transfer This-pump is capable of transferring pow esin from the powdex storage tank to the dewatered waste processin ea. The pump is a stainless

steel, positive displacement pump.

ontrols are located in the radvaste control room, and an emergene toff is locat;d in the dewatered waste processing area for ust ing resin transfer to the shipping containers. 11.4.2.2.f Dry Solids Compactor The Dry Solids Compactor is used to reduce the volume = of such material as cloth,

paper, and plastic that is contaminated.

Sorting and staging space is available in the low level' waste handling and packaging area to separate non-contaminated'

c materials for ordinary landfill disposal.

I ?, ( 11.4.2.2.# Radvaste Building Crane The Radwaste Building Crane provides service to the-areas occupied by the: A. LWMS Process Vessels B. LWMS Process Pumps C. Shielded Storage Area D. Container Filling Platform E. Shipping Truck Bay F. Vendor Solidification Bay G._ Miscellaneous Contractor Space H. Low-level Handling and Packaging Area I. Low-level-Waste-Storage Area The crane is equipped with remote controls - and-surveillance cameras to minimize operational exposure. b Amendment <I' 11.4-7 December 21, 1990

CESSAR !!ah-W nr~P pn 11.b.3 System Operation 11 2.3.1 Spent Resin Storage and Handling N i The p dex tank process train is used to collect, dewater, and transfe spent radioactive powdex from the condensate dominera zers. Powdex resin is sluiced from condensate deminerall ers to the powdex storage tank where it is allowed to , settle. De ant is removed and transferred to the LWMS for / sampling pri r to release or recycled to the condensate system. I The resins a batched to the dewatered waste processing area where the rem ining water is removed and the container is j prepared for shi ent. Process line connections allowing the use I of vendor-supplie r d equipment are provided. When low activity in beds are expended, they are 'usually batched directly to disposal containers for vendor-ssrvice processing and direct pment to a licensed burial facility. / However, a low activity nt resin storage tank is provided to allow for settling and ho up of these resins prior to processing if necessary. Decant from resin storage tanks and disposal container dewatering operati is directed back to the LWMS. a )' By injecting service air or v through the resin outlet lina at the bottom of each tank, th crpfins may be agitated prior to transfer to the processing ar Sampling of the tank is performed to ascertain the radi uclide content of the spent resins. At the time of transfer, s ice air is allowed to flow + through the service air header o provide the necessary i overpressure required to propel the re 'ns out of the tank to the / dewatered waste process area. / High activity resins are sluiced to the hi activity spent resin storage tank and transferred to the proc sing area using the methods described above for transfer of ow activity spent resins. In some cases high activity resins ' y be blended with t low activity resins to reduce shipping

anc, disposal costs.

) Blending may be accomplished by utilizing a oss connection / which allows transfer of low activity spent resi s to the high activity spent resin storage tank. When solidification of spent resins is desired, ins entation on the spent resin storage tank is used to assure that the appropriate water-to-resin ratio is present. Adjustment to this ratio may be made using available water supplies or th-spent / resin tank dewaterkng pump as necessary. Following mixing, valve alignments are mde to direct the resins through the esin inetering pump to the binding area. Filled containers may ba) s cred in the shielded storage area until shipped. N

vv~~m%

Amendment I 11.4-8 December 21, 1990

~. d 4 Insert C 11.4.2.3 System operation 11.4.2.3.1 Spent Resin Storage and Handling r Spent resin is sluiced from various--plant ' demineralizers--_ or_ ion exchangers to spent resin storage tanks where it is allowed to settle prior to processing. Spent resin is segregated based on level of activity. High activity spent resin'from demineralizers used-to process primary coolant, such as the purification and pre-holdup lon exchangers in the Chemical Volume and Control System, are sluiced to the high activity spent resin storage tank._ Low activity spent resin from the fuel pool and boric acid concentrator ion exchangers and the LWMS demineralizers are sluiced to the low activity spent resin storage tank. Service air or water injected through the resin outlet line at the bottom of each tank is used to agitate the resins prior to transfer to the processing area. At the time of transfer, service air is allowed to flow through the service air header to provide the necessary overpressure required to propel the resins out of-the tank to the dewatered waste processing' area. If necessary, low activity spent resin are sluiced to the low-activity spent resin tank to allow for settling and holdup prior to. processing, Otherwise, they are batched directly to disposal containers for vendor-service processing and direct shipment-to a licensed burial facility. High activity spent resin is sluiced to the high activity-spent resin storage tank to _ allow settling and decay of short-lived isotopes. Resin are then transferred-to-the processing area. In- + some cases,_ high activity resins may be blended with_ low activity-resins. Blending may be accomplished - by utilizing a cross-connection which allows-transfer-of low-activity spent resins to the high activity spent resin torage tank. Decant from the resin-storage-tanks and-the disposal containers, removed.during the dewatering process, is. directed back to the LWMS for sampling and processing-prior to release _to the environment. Non-clogging screens on the - spent resin tank and filters-in. the process line are provided to-prevent the carryover of--spent resin beads or fines to the LWMS during the transfer of decanted water. When solidification of spent resins is desired, instrumentation on the spent resin-storage tank is used to assure that-the appropriate water-to-resin ratio is present. Adjustments to the' ratio may..be made using available. water supplies-or the. spent. resin tank dewatering pump as-necessary. Following mixing, valve alignments are made to the. binding area. Filled containers may be stored in the shielded storage area until-shipped. Page 1 of 1 g %n l& i

CESSARnnLw0,. t B. Flow and Pressure Indicators Pump discharge flow and suction netering as well as pump discharge pressure indication will be provided to properly control the bed transfer process. I C. Radiation Monitoring Area radiation monitors will be provided as discussed in ts - 12. Che=b e (1 5 $ cc. 11.4.7 S'1VRAGE CAPACITY System 80+ will provide an Interim Onsite Storage. Facility to-provide adequate shielded storage space for solid. waste -(i.e., The Interim Onsite Storage Eacility wet, dry, solidif}ed waste). is located. in close proximity to the Radwaste-Building to facilitate the transfer of shipping: containers from the Radwaste Building to the Interim Onsite Storage Facility. This facility in accordance with Standard Review Plan, Section designed is EPRI Electric Utility Document, Chapter 12, and Regulatory 11.4, Guide 1.143 requirements. These include:- This f acility provides sufficient shielded storage capacity to accommodate the maximum expected waste generated in a six A. ( month period. All-potential release pathways shall be controlled' and monitored in accordance-with -10 CFR 50, - Appendix A' (General B. i Design Criteria 60 and 64). This will be ensured by the following: Provision of curbing or elevated thresholds to retain such as dewatered resins-~or-sludges. spills of waste, Provision of floor drains to collect and route spills-back to LWMS for_ processing. Provision of

area, airborne, and process radiation monitors.

~! C. The f o u n d a t i o n -- a n d walls shall be designed in accordance to withstand an Operating-Basis with Regulatory Guide 1.143 Earthquake (OBE). Sufficient shielding is provided to limit the radiation level to less than 2.5 mrem /hr-in adjacent areas, permitting D. unrestricted access. 1 i Amendment J 11.4-11 April 30, 1992 I L

CESSAR nilinemeu i TAHLE 11.4-1 l ~ (Shoot 1 of 2) e SOLID WASTE MANAGEMENT SYSTEM 4 COMPONENT DESIGN 1 hEbiiTQRAGE TANK 1 Qt.antity Total Volumo (Gal) Stainless tue1% Material-Right cylinder,,Cor h Geometry lji w AG W W LPENT RESIN STORAGE TANK Quantity ,2" l - Total volume (Gal) 5000 Stainloan Stool-Material I i Right Cylinder,. Conical Bottom

Goomotry

. InMT SPENT RESIN TANK DEWATDtING PUMP Quantity / 2. 1 Cannod, llorinontal contrifugal-Type Stainions-Stooi Material t DEWATERING PUMP t 1 Quantity Singlo _ Stage Tur'oino Typo -Stainloon Stool-Material NiRDET-DEWATERILGyP -1 Quantity Cannod, llorizontalTUTitrifuga.L Typo Material POWDEX-TRANEFER PUMP ~ M-f Quantity Positivo D eemen h Type -Stainions Stool' -Material. c 2.oumw w~r ~ (~ ~ EcAiw TAuK 'V a .QhAvrgy_ _ TO4AL \\)ouwe (CrA4 z. ,k ^ 4,20er Amendmenti'I f BATIL AC h $ cWkg - - sb. Icu 161 3 comber 2217-19% 4 l. E%+ C 1[n4<el (o40.4 ); 3 i.

CESS AR !!A!Luos (. TAllLE 11. 4-1 (Cont'd) (Shoot 2 of 2) SOI.1D WASTE MANAGIMElfr SYSTIM COMPONENT DESIGN SPENT ItESIN MlfrEllI!id PUMP Quantity ,2 3 Type Positivo Displacement Material Stainless Stool SPEfff RESIN SI,UICE FILTEll Quantity X1 Type Disposablo Cartridge t Material Stainless Stool Rotention % (0 25 Micron) 90 Material -Stainless Stool i Amendment J %en-wo, 33 toon

~ CESSAR EN!i"icuion i TABLE 11.4-2 ESTIMATED MAXIMUM VOLUMES DISCllARGE FROM TIIE SWMS (1 UNIT' i. Volgues. f Wasto Type (ft fyr) l 21ZO (l)lt.) spent Dead Rosinn +2e (1) Powdew-Renine 1600 (21 Filters +30s f I Hiscollaneous solids 2400 NOTL'S : 1. 180 cubic foot: high activity resin and 240-l cubic feet low activity resin 6 2. Assumos' /3 condensato dimineralizer resin beds dischargo por fuel cyclu 4 t 1 Amendment:1-December 21, 1990 _._.,c_.-...

1 ) CESSAREn h ou A uJR - v87 l 12.2.1.6 Hadwnsto fluilding Radwanto building tanks and process component courco terms are summarized in Tables 12.2-17 through 12.2-19. The radwasto building sourco terms provided include wasto fluid and ion exchange resin specific activitico calculated for CVCS and condonsato cleanup components as well as calculated radwasto prococo equipment courco, terms. Equipment and floor drain tank fluid specific activitics are calculated using Table 12.2-5 degassed reactor coolant equilibrium radionuclido concentrations and Table 11.2.6-2 activity fraction assumptions (i.e., equipment and floor drain tanks receive fluids with average primary coolant activity fractions of 0.2 and 0.02, respectively). The laundry and hot shower tank specific activities are calculated using HUREG-0017 annual detergent wanto radionuclide rolcano projections and assuming 540 gallon per day of dotorgent wastos are treated and rolcased. The chenical wasto tank will receive fluids of varying radioactive contamination levels and in shielded assuming relatively high 1 cyclo (consistent with the equipment wasto drain tank) may be received. The wasto monitor tank source term is calculated using equipment wasta tank radionuclido specific [ activition and an assumption that liquid wasto processing equipment achieves an overall decontamination factor of 1000. 1 Specific activity source terms for wasto process filters and domineralizers are calculated using an activity build-up and decay model. Process flow rato assumptions consistent with Tablo 11.2.6-2 and process fluid activity levels provided jn Table 12.2-17 are used. For the purposes of the source term calculation, wasto process filters and resin beds are assumed to have a 3 month useful service life. Although radwaste process filtration media source terms and useful service life will realistically vary, component cources will be controlled (i.e., media replacement based on elevated dose rato

levels, if necessary) to assure occupational exposures associated with radwaste system operations remain ALARA.

Specific activities for the high activity spent resin storage tanks are the same as calculated for the CVCS purification domineralizer resins presented in Table 12.2-10. The low activity spent resin storage tank cource terms aro taken from Table 12.2-18 values for wanto proccas domineralizer resins. -Powde x s torage-te n k-s ou rce-te rma-a re--te ke n-f+oin-Te hle-14ra-15 s pee-i-f-io-e e t-i-v-ibles--fo r-powd em ?' 'l pN <(A 7 eg f f ~ i) i[ P Amendment I 2 }- 'Decembet-]2 {iMO[ 12.2 10

CESSAR Eninemou /) we - g9 Intake louvers for ventilation systems are located on the exterior of buildings draw outsido air into the plant. This air may be contaminated. The concentration of the radionuclidos in the air at the intake is a function of sito specific characteristics, such as the atmosphoric dispersion coefficient (X/Q), the wake offect from the surrounding structure. The releana of low loval of radioactivity from the unit vent is a continuous process. In general the airborno material will rise, duo to the momentum and the buoyancy of the offluent of the oxhaust, and will be carried away by wind currents.-

llovover, fumigation of the affluent may occur due to inversion of the plume compounded by wako offects of nearby structures.

This may cause the offluent to linger around the plant ventilation intakes whero it can be drawn into the plant recirculating contaminated air discharged from the plant. 12.2.2.1 Inplant concentrations The levels of airborno radioactivity within the plant during normal operation are based on estimatos of the above sources. It is assumed that in areas where there are no potential sources of radioactivo laakage or evaporation, the concentration of radioactivity is equal to the concentration in the air external to the ventilation intakes. This is reasonable because the design y of ventilation systems is such that air flows from areas of lower potential.airborno radioactivity to areas of higher airborno radioactivity. For those areas with sources of leakage or evaporation, the concentration is calculated byt c=co + Q/ (l.7t+os F) Whoro: C= room concontration (uci/ml) c =outside air concentration for the appropriato vbntilation-system (uCi/ml) \\ Q-source term (uCi/hr) QaL*PF*A N O L=1 akage or, vaporation rato(f t /hr) PF=hartitiohfactor / A = initial activity of fluid stream source (uCi/ml) O p Amendment J 12 2-13 April-307 1992 ()t$,/.si ' <* ' W

l CESSAR iniscucu /Lu A. - r 27 l 4 l Vafras- -voluma-o f-a i r4 n-r oo m ( m L) (fd 3 F= room exhaust flow rate (ft / min) 1.7E+06= conversion factor (ft -hr/ min) 4-o h\\) 3 Credit for decay has boon noglected for conservatism. The airborno concentrations in rooms or cubielos accessible by personnel throughout the plant will be maintained within maximum permissible concentrations proscribed in 10 CFR Part 20. 12.2.3 SOURCES USED IN NUREG-0737 POST-ACCIDENT SHIEIRING REVXEH Item II.b.2 of NUREG-0737 clarifies the requirement for ensuring that areas which require post-accident personnel access or contain safoty-related equipment are adequately shielded in.the vicinity of systems which may contain highly radioactive materials as a result of the Design Dania Accident. A radiation and shiolding design review of the System 80+ Standard Design in accordance with Item II.b.2 of NUREG-0737 is performed during the detailed design phase of the plant. The 7 review of systems that, as a result of an accident, contain highly radioactive materials was performed using the same methodology described in Section 12.3.2. Initial core releases are used which are equivalent to those recommended in Regulatory Guides 1.4 and 1.7 and Standard Review Plan 15.6.5. The source terms are presented in Table 12.2-20. Plant areas requiring post-accident occupation (" vital areas"), and the duration of occupation are identified. The calculated individual personnel radiation dosos and average dose rates in vital areas requiring continuous occupation are less than 5 Ram (GDC 19) and 15 mrem /hr, respectively. s Amendment J 12.2-14 April-30 F1992 Ofl4 $ ^, i fi V

CESSAR M,uince ALog y gp TABLE 12.2-15 (Sheet 1 of 2) 1URHINE BUILDING SOURCES l RADIONUED DE 5PICIFIC XCTIVITIES SG (1) ' Blowdown Blowdown Pswdex Water Condensate Steam Filter IX IX. Isotopo fgClfgel ,_{pCl/ gal (pC1/ge) -]pC1/ml) fpC1/ml) Ig'lfall l 3 Volume (ft ): 1-30

800 1.2E-04 4.E E-0 Sr-89 3.9E-09 2.0E-Il 2.0E-ll 5.4E-05, 2.0E-0 Sr-90 3.4E-10 1.7E-12 1.7E-12 5.lE-06 1.9: -C Sr-91 2.0E-08 1.0E-10 1.0E-10 5.1E-06 2.0?-q7 Y-91 1.4E-10 7.2E-13 7.2E-13 2.2E-05 8.2 :- D7 Y-93 8.6E-08 4.3E-10 4.3E-10 4.5E-04 1.7L- )5 Zr-95 1.lE-08 5.5E-11 5.5E-Il 1.7E-04 6.4l' 6

Nb-95 7.6E-09 3.8E-Il 3.8E-II. 1.3E-05 4.8f 07 Tc-99m 8.0E-08 4.0E-10 4.0E-10 3.0E-04 1.2E 05 Ho-99 1.7E-07 8.7E-10 8.7E-10 5.3E 2.lE -04 1-Ru-103 2.lE-07 1.lE-09 1.1E-09 2.9E-01 1.1 -02 Ru-106 2.5E-06 1.3E-08 1.3E-08 3.8E-03 2.8 04 1-131 7.4E-07 7.4E-09 7.4E-09 1 lE 8.lK 06 I-132 1.8E-06 1.8E-08 1.8E-08 1.2E-03 8.8 :- 05 1-133 2.1E-06 2.lE-08 2.1E-08 5.8E-04; 4.4:- 05 l-135 3.3E-06 3.3E-08 3.3E-08 5.2E-06 1,5.E-07 Te-129 1.7E-07 8.5E-10 8.5E-10. 1.2E-04 4.: E-06 Te-129m 5.4E-09 2.7E-Il 2.7E-Il 2.5E-07 9.4E-39 Te-131 2.3E-08 1.2E-10 1.2E-10 .3.0E 1..E- )G - Te-131m 3.8E-08 1.9E-10 1.9E --- 9.5E-05 - 3. 5E-16 Te-132 4.6E-08 2.3E-10 2.3E-10 3.6E-02 8.,5E-n4 Cs-134 2.9E-07 1.4E-09 1.4E --- 2.6E-04 6J2E Cs-136 3.5E-08 -1.7E-10 1.7E --- 5.6E-02 1 3E-( 3 Cs-137 3.9E-07 1.9E-09 1.9E > 2.9E 1,IE-C 4-Ba-140 3.6E-07 1.8E-09 1.8E-09 6.9E-04 2.6E-05 La-140 6.5E-07 3.2E-09 3.2E-09 -O f 3}2E 8.6E-05 Cc-141 4.2E-09 2.lE-Il 2.lE-11 2 3E-Oi 6.lE-05 Co-143 7.0E-08 3.5E-10 3.5E-10 1.2E d.4E-0l Cc-144 1.lE-07 5.5E-10 5.5E-10 J-i a Amendment,I December'2 G. 1990 <:P, 56 ,a n z.

CESSAR !!Mincum AWA "fM 1 ( 9 TA8LE 12.2-15 (Cont'd) t (Sheet 2 of 2) TURBINE BUILDING SOURCES RADIDNUCLTDE SPECIFIC AETIVITIES SG (1) Blowdown Blowdown Powde Water Condensate Steam Filter IX IX Isotope hCifgs] _(pC1/ge)_ jpC1/ge)_ jpC1/el) juci/el)_JC1/m) 1.2E-09 Kr-85 2.3E-08 Kr-85m 2.5E-08 Kr-87 4.5E-08 Kr-88 7.2E-09 Xe-131m 4.7 E-08 Xe-133 2.6E-09 Xe-133m 9.3E-08 Xe-135 2.5E-08 Xe-135m 6.6E-08 Xe-137 1 2.3E Xe-138 Mn 4.5E-08 2.2E-10 2.2E-10 1.5E-011 9.9E-05 1 8E 4 Co-58 1.3E-07 6.6E-10 6.6E-10 1.7E-01 1.1E-04 2 2E Co-60 1.5E-08 7.5E-Il 7.5E-11 6.7E-02' 4.5E-05 .6E-5 Fe-59 8.2E-09 4.lE-Il-4.lE-11 6.9E-03 4.7E-06 .7E-6 Cr--51 8.9E-08 4.5E-10 '4.5E-10 4.6E-02 3.lE-05' .9E- _(1) Also source assumed for SG Blowdown _ and SG Drain Tank fluid systems.

i
W s.

- Amandmental L-e LDecojnilie 2l',-1,990- {"

CESSAR HSinCAMN Aw A'vh7 - t TABLE 12.2-19 ) (Sheet 1 of 2) [ RADWASTE BUILDING SOURCES SOIID WASTE PROCESS EQUIPMENT HA Spent LA Spent m Powde Renin Resin h Stora e i Tank Tank (1.) I Tank Isotopo jpC1/ mil [ (pci/ml) 'p ci/m}L) - IMO 400Cf-3 Volumo(f t ) 670 690' \\ Dr-83 1.6E-02 N.2.9E-05f ~~ Dr-84 1.GE-01 'lT6E-04' Dr-85 1.7E-03 3.2E-06 Rb-88 9.7E-02 3.3E-04 Rb-89 9.9E-02 3.3E-04' Sr-89 2.3E+01 3.1E 4,8E 06 Sr-90 6.0E+00 3.4E-03

2. 0E OG Sr-91 1.2E-01 2.2E-04

1. 9E 07 Sr-92 1.6E-02 3.0E-05 I

Y-90 1.1E-02 2.1E -- Y-91 5.3E+00 6.8E-03

2. 1 -07 Y-91m 1.5E-04 2.9E-07 1

Y-92 4.0E-03 7.GE-06 Y-93 2.3E-02 ,4.3E-05 8.26-07 Zr-95 7.3E+00 8.9E-03 1.7E-05 Hb-95 4.1E+00 6.5E-03'-

6. K-06.

Tc-99m 1.0E-02 2.0E-05~ 4.

-Mo-99 3.7E+02 6.9E-01 1.

~05' Rh-103m 3.OE-04 5.6E-07 7-- Ru-103 3.4E+00 5.1E-03 2. E-04 Ru-106 - 3. 4 E+ 0 0 - 2.3E-03 _1.11 -02 I-131 3.9E+03 7.3E+00 L 2 8E 04-I-132 1.4E+01 2.6E-02 8 1 06 I I-133 6.6E+02 1.2E+00- '8 8 -05 I-134-4.0E+00 7.6E-03: I-135 1.2E+02 2.3E-01 4.4E-05. To-129-6.4E+02 1.2E-04 . 9 E To-129m 5.' 7 E+ 01 ' 9.2E-02 d.3E- 06: l.9Eh09 To-131 ~2.7E-02 5.1E-05 Te-131m 5.4E+00 1.OE-02 .1E-36 'To-132 1.6E+02 3.1E-01' .6E-36 Ji 1.SE-01-- 2.9E-04 To-134 .Cs-134 7.9E+03 8.9E+00 8.5E-4 Cs-136 2.1E+02-7.2E-01 6.2E-6 Cs-137 -8.9E+03 9.3E+00 1.3E-3 Co-138 7.6E-01 2.6E -- Ba-137m 2.9E-07 5.5E ' --- Amendment'J a_ a.-. - -..- -~ ~.

CESSAR En!Lui:n AL.uA-yt9 l TABLE 12.2-19, (Cont'd) (Sheet 2 of 2) RADWASTE BUILDING SOURCES- -l SOLID WASTE PROCESS EQUIPMENT HA Spent LA Spent I de I-Resin Resin) S: ora e-Tank (.L yank l Tank Icotopo _(p C1/ml) - (pci/ml) (pQi/ },.- ] Ba-139 5.8E-03 1.1E-05 Ba-140 9.0E+00 l'.7E-02 1.1 04 La-140 1.7E-01 3.2E-04

2. 6E 05.

Co-141 3.5E+00 5.7E-03 3.2 06 Co-143 1.1E-01 2.2E-04 2.3' 06 Co-144 1.3E+01 9.2E-03 4. 04 Pr-144 3.2E-05 6.0E-08 Mn-54 1.9E+01 2.7E-03 1. E-4 Co-58 '2.4E+01 5.7E-03 2 2E-4 F Co-60 8.2E+00 9.7E-04 8 6E-0 Fe-59 1.0E+00 3.0E-04 .7E-0 Cr-51 6.7E+00 2.3E-03 .9E-0 e 1 I k i- / I-AmendmentAh-w_- iDeconlik21,-.1990!

CESSAR in!%mou /) w 4 - y n 12.3 RADIATION PROTECTION DESIGN FENIURES 12.3.1 FACILITY DESIGN FEATURES .Inse cY -b A This sec on describes some of the System 80+ design features to achieve goals. A. ruel P formanc.c The Syst 80+ design features assure low primary system sources v h improved fuel clad leakage performance of less than 0.1% uel clad failures, as well as'an extended fuel cycle. B. Corrosion Prod et Control System 80+. den n includes design features than reduce corrosion product roduction in the primary system. 1. Primary' System aterials The System 80 design specifies primary system materials with lo corrosion rates and very low cobalt impurities. Steam generator tu os are fabricated to relieve stresses to reduce ress corrosion, cracking. This will reduce the probab ity of tube plugging activities and further reduce main nance exposures. Control rod drive mater is are specified with low cobalt alloys to reduce RC.a exposures. 2. Primary Systen Chemistry Increased pH in the range t 6.9 to 7.4 reduces equilibrium corrosion rates and buildup of activated corrosion products on primary sys em surfaces. C. Reactor Coolant Pump Seals System 80+ RCPs incorporate a cartridge ype of RCP seal which is a proven, reliable and easily eplaceable seal design. The replacement is also facilitated py the addition of platforms around the RCPs. This design retluces the time required to perform maintenance on the Rd seals and maintenance exposure. Amendment J 12.3-1 April 30, 1992

CESSAR Eininemon Az s/?-YP9 D. St am Generator Maintenance Syst m 80+ design includes several features which enhance acceshibility during maintenance and inspection. These featurks, described in Section 5.4.2, reduce the overall exposur to personnel during these activities. L These features neludes automatic /robotic equipment for inspect $1on and 1. Use o mainton nce activities 2. Adequate ull and laydown areau 3. Platforms 4. Handholes 5. Increased o e of manvays to 21" 6. Use of re' wable insulation to facilitate Veld inspection 7. Use of Inconel 690 for the tubes to reduce corrosion J product producti n. Also, included in the yatem 80+ design are features which are important to achievih ALARA goals. These include: 1. considerations to equipment reliability, maintainability, and a casibility 2. Component design, i.e., tank design, piping design and 7 instrument design to mini ize particulate deposition 3. System flushing and decont mination capability 4. Radwaste handling operat' ons (also discussed in Sections 11.2 - 11.4). 5. Isolation of contaminated components and proper shielding 6. Controlled access to high radi ion areas via locked doors. 7. Piping containing radioactive liq (ds, resino, or gases are routed through shielded pipe chises. In order to maintain exposure ALARA and to aid .n the. layout and shieldint design, the station is divided into adiation zones. I These zones indicate maximum dose rates ba ed on design activities only. The zone limits are summarized in able 12.3-1.

12. 3.1. ;t' te Radiation Zone Designation The radiation zones for normal operating conditions are designated in Table 12.3-2, as well as the gasociated Radiation J

Zone Maps illustrated in Figures 12.3-1 through 12.3-8. l Amendment J 12.3 April 30, 1992 l

y gJf/h0 /qs 4w /2 -Up Insert A N m 12.3.1 FACILITY DESIGN FEATURES The System 80+ design incorporates ALARA principles per Regulatory Guide 8.8 and 8.10 to minimize the onsite exposure to plant personnel and operators during normal operation and maint mance activities. Section 12.1.2.1 details ALARA principles incorporated into the plant layout, component location, and material selection. The following section details specific design features to ensure i operational and maintenance exposure is ALARA. 12.3.1.1 Gonoral Arrangemont Dosign Featuros A. Location of Radioactive Systems and Equipment Nonradioactive systems are separated from radioactive systems. This helps control the spread of contamination and minimize the necessity for routing piping containing radioactive fluids or slurries through personnel corridors. This,also facilitates radiation area access control. Radioactive equipment are separated into compartments whenever possible. Equipment is compartmentalized based on frequency of access required, operational characteristics, and radiation level. For pxample, ion exchangers containers resin beads are typically located in a separate compartment from active components, such as pumps and valves. Valves are typically located in valve galleries. Ion exchangers are located in pits with their associated spent resin service tanks located directly below the ion exchanger to minimize the pipe lengths and the general area radiation. The compartment walls provide shielding which enables personnel to perform operation and maintenance activities in a lower radiation area. B. Pipe Routing j Pipe lengths of radioactive systems are minimized by locating interfacing systems in close proximity. Piping for these systems are then routed through shielded pipe chases. The i number of active components located in pipe chases are minimized to reduce the frequency of access required into the pipe chase for maintenance activities. C. Spacing The System 80+" Standard Design is designed to provide adequate spacing around equipment for easy access of equipment for maintenance and inspection, This includes provisions for, adequate laydown area or equipment pull area, as well as transport paths for removal or replacement of equipment. Rigging and lif ting equipment are also provided to facilitate Page 1 of 9 Jh yf.a cA a ya m ,UW

A1.in-Yq the

removal, transport, or replacement of equipment or portable shielding during maintenance activities.

D. Hot Tool C1ibs and Hot Machine Shops Hot tool cribs are located in low radiation areas adjacent to maintenance areas to minimize waiting times in high radiation areas, to help prevent the spread of contamination, and to decrease the amount of decontamination work required to be performed. This reduces the radioactive wastes generated and personnel exposure. The provision of a hot machine shop adjacent to the equipment hatch enables personnel to remove equipment from containment and perform maintenance in a lower radiation area. Access to the hot machine shop is also provided from the truck bays and maintenance areas for ease of equipment movement. E. Staging Areas Large staging areas inside and outside the equipment histc' 'and h personnel airlocks allow pre-staging prior to the start of an

outage, as well as provide space for efficient radiation controls for moving equipment in and out of containment.

F. Personnel Decontamination and Change Areas Two personnel decontamination areas are provided in the System 80+" design. One is located within the radiation access control area (RCA) and the other is located adjacent to RCA access point. Protective clothing, respirators, shower and toilet facilities, lockers, and containers for contaminated clotuinn are provided in these' areas. Change areas are located near airlocks to minimize personnel. traffic flow, distance travelled, and the potential for the spread of contamination. G. Radiation Control Area (RCA) The System 80+" design provides for a single point access -into the RCA on elevation 91+9; however emergency egress is provided on all elevations. The. access area to - the RCA provides a flexible and adaptable layout, a large area (40' ~x 100') sufficient to accommodate outage work crews and enhance the availability of immediate -interaction with radiation- . protection personnel stationed at this point. H. Accessways and Entrances-to High Radiation Areas 1. Labyrinths or shield doors are provided at the entrances to high radiation areas to minimize the exposure due to scatter and streaming of radiation through entrances. Page 2 of 9 o q

WNNh 2. Shield plugs are provided as necessary to provide shiciding during normal operation for adjacent corridora. These shield plugs are removable to permit components, such as heat exchangers, and their internals to be pulled during maintenance activities. 3. High radiation areas are provided with locked doors to prevent inadvertent access by plant personnel. 12.3.1.2 Equipment and System Dosign Features for Control of Onsite Exposure System 80+" specifies the use of more reliable and simplistic equipment. This reduces the frequency of maintenance and the radiation exposure to plant personnel. The following section discusses equipment design characteristics utilized in radioactive systems. 9 A. Pumps 1. Pumps and associated piping are flanged to facilitate pump removal to a lower radiation area for_ maintenance or repair. Pump internals are also removable. 2. All pump casings are provided with drain connections to facilitate decontamit.ation. The drain connection are free of internal crevens to minimize accumulation of radioactive corrosion products (crud). 3. Pump seals are easily serviceable without removal of the entire pump or motor. The reactor coolant pump seals are a cartridge type to facilitate removal for maintenance or repair. B. Ion Exchangers (Demineralizers) 1. Ion exchangers are designed for complete drainage. 2. Spent resin removal is designed to done remotely by hydraulic flushing from the vessel to the Solid Waste Management System (SWMS). 3. Piping, strainers and resin screens are flushable so that all spent resin is removed in the flush mode. 4. Fresh resin addition is accomplished from a low radiation area above the shielded compartment housing the_ lon exchanger. 5. Internal crevices are minimize to prevent accumulation of radioactive crud. Page 3 of 9 l23')

bh ' 'f j 6. Ion exchanger manways are easily accessible. Internal components are easily removed through manways requiring minimal disassembly. C. Liquid Filters 1. Filter housings are provided with vents connections and are designed for complete drainage. 2 Filter housings are designed with a minimum of internal crevices to minimize the accumulation of radioactive crud. 3. Filter housings and cartridges are designed to permit remote removal of filter elements. Cartridge filter seals are an integral part of the filter cartridge so that seal removal is accomplished during cartridge removal. 4. Cartridge filter housing closure heads are dead,gned to swing free for the unobstructed removal of the cartridge. D. Tanks l. Tanks are designed for complete drainaget free of internal crevices, and pockets. The drain line is connected to the bottom. 2. Tanks are provided with at least one of the following means of decontaminating the tank internals: a. Ample space is provided to permit decontamination of the tank manway. b. Internal spray nozzles are provided on potentially highly contaminated tanks for internal decontamination. c. Back flush capability is provided for tank inlet screens. 3. Tanks are designed with a convex or sloped bottom to facilitate drainage and minimize the accumulation :of crud. 4. Tanks are provided with vents to facilitate'the removal-of potentially radioactive _ gases _during maintenance. 5. Non pressurized tanks are provided with overflows, routed to a floor drain _ sump or other suitable collection point to avoid spillage of radioact.ive fluids onto the floor or - ground. The' floor drain system is connected to the Page 4 of 9 jp,3.;L[ t-'y-' + b w,, ,w w

A wA-vfp Liquid Waste Management System for further processing prior to release to the environment. E. Valves 1. The following discussion summarizes valves specifications ' hat minimize valve leakage, as well as extend valve design life, a. Except for modulating valve applications, packless valves are used on all valves two inches and under in diameter, b. Modulating valves and valves greater than two inches in diameter use live loading of the packing by conical spring washers or equivalent means to maintain a compressive force on the packing where

possible, c.

Double stem packing with a leak-off between, the packing is used for valves four inches and larger, as well as normally open valves two to four inches in diameter. Stem leakage is piped to an appropriate drain sump or tank. d. Valves utilizing stem packing are provided with backseat capability. e. Radiation resistant seals, gaskets, and clastomers are utilized, when practicable, to extend the design life and reduce maintenance requirements. 2. Fully ported valves are used to minimize internal accumulation of crud. 3. Valves requiring removal during maintenance and inspection activities are flanged. 4. Internal valve surf aces are designed f ree of crevices to minimize the accumulation of crud. 5. Valve wetted parts are made of austenitic stainless steel or corrosion resistant material. 6. Valves are designed so that they may be repacked without removing the yoke or topworks. F. Piping and Penetrations 1. There is no field run piping. Page 5 of 9 / t L. )- 5

ALc'O. - 129 ) I 2. Resin and concentrate piping is designed as follows: a. The length of pipe runs are minimized, b. Piping is routed through shielded pipe chases whenever possible to minimize routing through personnel access corridors. c. Large diameter piping (> 5 pipe diameters) is utilized to minimize the potential for clogging during slurry or resin transfer without violating minimum flow requirements. d. The number of pipe fittings (e.g., cibows, tees, t etc.) are minimized to reduce the potential. for _ radioactive crud accumulation. e. Low points, deadlegs, and vertical pipo runs are minimized. Pipe runs are sloped and gravitational flow' is' used f. where practicable. 9 Crevices on piping internal surfaces are minimized. h. Flushing capability is provided to facilitate decontamination of piping. 1. Penetrations are located so that the source and the penetration are not in a direct line of sight. This minimizes the potential for personnel exposure due to streaming. G. liest Exchangers 1. Ileat exchangers are designed with vents and for complete drainage. 2. Internal wetted surfaces are designed crevices free to-minimize the potential for accumulation of radioactive crud on internal surfaces. 3. Corrosion resistant materials are utilized to minimize the need for replacement and reduce the f requency. of maintenance required. 12.3.1.3 Source Term Control Source term control _is an ' important~ aspect of' the System 80+" design. The following. design features reduce the overall dose due-to. operation, maintenance, and inspection activities. Page 6 of-9 g Y '&

id A. Fuel Performance The System 804" design features assure low primary nystem sources with improved fuel clad leakage performance of less than 0.1% fuel clad failures, as well as an extended fuel cycle. B. Corrosion Product Control System 804" design includes design features that reduce corrouion product production in the primary system. 1. Primary System Materials The System 80+" design specifies primary system materials with low corrosion rates and very low cobalt impurities. Steam generator tubes are f abricated to relieve stresses to reduce stress corrosion cracking. This will reduce the probability of tube plugging activities and further= reduce maintenance exposures. Control rod drive materials are specified with low cobalt alloys to reduce RCS exposures. 2. Primary System Chemistry Increased pil in the range of 6.9 to ~7. 4 reduces equilibrium corrosion rates and - buildup of activated corrosion products on primary system surfaces.. 12.3.1.4 Airborno Contamination Control In the System 804 design, plant ventilation systems are designed so that flow is from areas of lower to areas of higher potentd il activity. This design minimizes the potential for the spread of contamination. In addition, the following confinement devices are utilized to minimize the spread of contamination: A. Drip Containment Drip containment devices are used to collect equipment leakage and prevent suspension of radioactive particulate into the air t or volatile . radioisotopes, such as noble gases and-radiciodines. D. Glovo Bags i Glove bags are used to perform maintenance activities, such as valve refurbishments, in an enclosed area. Page 7 of 9 fl ,Y

$Nf I l-C. Tents Tents provide a large enclosed area to perform work such as grinding or maintenance on large equipment. These tents are provided with ventilation capabilities and essentially provide for a local hot machine shop. D. Ilot Machine and Instrument Shops These areas provide a dedicated area where maintenance can be performed on radioactive and contaminated equipment. 12.3.1.5 Equipment Improvements A. The System 80+" RCPs incorporate a cartridge type of RCP ser.1 which is a proven, reliable and easily replaceable seel design. The replacement is also facilitated by the addition of platforms around the RCPs. This design allows the seal to e be removed and repaired outside the clane wall or other low dose area.- Therefore, the time required to,po,rform maintenance on the RCP seals and maintenance exposure is reduced. B. Steam Generator Maintenance System 80+" design includes several features which enhance accessibility during maintenance and inspection. These

features, described in Section 5.4.2, reduce the overall-exposure to personnel during those activities. These features include:

1. Use of automatic /robetic equipment for inspection. and maintenance activities 2. Adequate pull and laydown areas 3. Platforms 4. !!andholes 5. Increased size of manways to 21" 6. Use of removable insulation to f acilitate weld inspection 7. Use of Inconnel 690 for tubes to reduce: corrosion product production. Also, included in the System 80+" design are features 'which are important to achieving ALARA goals. These include: 1. Considerations for-equipment reliability, maintainability, and accessibility -2. Component design, i.e., tank design,-piping design and instrument design to minimize particulate deposition 3. System flushing and decontamination capability 4. Radwaste handling operations (also discussed in Sections. 11.2 - 11.4) 5. Isolation of contaminated components and proper shielding Page 8 of 9

p. )- S

Uk-T@f 6. Controlled access to high radiation area via locked doorn 7. Piping containing radioactive liquid, resins, of gases are routed through shielded pipe chases. In order to maintain exposure ALAPA and to aid in the layout and shielding design, the station is divided into radiation zones. These zones indicate maximum dose rates based on design activities only. The zone limits are summarized in Table 12.3-1. \\ ] ({. l \\x, -._Q}, l Page 9 of 9 ( 2s. 3 'f

CESSAR nuhnou A *Y9 7 l l' 12.3.1.h General Design considerations to Keep Pont-Accident Exposures AIARA Sampling capabilities with exposures kept ALARA will incorporato a post-accident sampling system that meets the requirements of I NUREG-0737 and Regulatory Guide 1.97, Revision 2. The area of the hydrogen monitors /recombiners will also require post-accident accons. Projected dose rates without the recombiners in operation is expected to be 0.5 to 2.5 mrom/hr. Since the recombinors do not have to be operational until 72 hours after the DBA, dose rates attributable to.the operation of J-the hydrogen recombiners will have dropped due to decay.

Thus, the installed dose rata will be less than 5 rem /hr.

While the dose rate would be greater than 5 rem /hr for an intact primary-degraded core event, the recombiners would not need to be installed since this event does not generate hydrogen inside of the containment. If hydrogen generation was postulated, this would necessitato a break or opening in the primary system. The consequences of this scenario would lead - to the doses noted above. Therefore, considering direct and airborne sources, access can be provided to those vital areas noconnary for the control of the plant and personnel exposures will meet GDC 19 and NUREG-0737 . ( guidelines. 12.3.1./S Post-Accident Radiation Zones Radiation Zono maps were developed in accordance with NUREG-0737 to review access throughout the plant following a DBA. The layout assists in kooping occupational doses ALARA even following a DBA. Required access to vital areas and systems will not exceed 5 rom,_ Source terms are discussed in Section 12.2.2. Continuous access will be provided during post-accident conditions with. dose rates less or equal to 15 mrom/hr to the following vital areas: Advanced Control Complex which includes: J Main Control Room Technical Support Contor Remote Shutdown Panel Computer system area and Rooms housing Instrument and Control-systems equipment-B. Diesel Generator-Rooms Q ,7%. )) j (' Amendment J. 12.3-3 ( April-30, 1992- ~ 4 s. ~.. . ~, 4-- -,y

CESSAREnnum Aug - yp9 N237 BURP is a Duke Power Company code that calculatos the accumulated activity on domineralizar resins or filtors and tito resultant activity of the process stream. This is accomplished by solving a pair of coupled, first order differential equations. Required input is isotropic removal officiencios and operation time. Gamma source strengths are obtained from the calculated specific activities by considering gamma yield and lossos due to conversion electrons. The nearly 300 individual gamma emissions of those isotopes are divided into six discreto onorgy groups. J l Group boundarios remain fixed, but the average group onergy is calculated for each spectrum of isotopes. This allows reasonably preciso selections of energy dependent shield material proporties for attenuation proporties. 12.3.2.2 Shloiding Donign shielding-shall be designed to achieve the radiation The - plant zones designated in Tables 12.3-2 and 12.3-3 for normal operation and post-accident conditions respectively. 1%k b -v 12.3.3 VENTIIATION The ventilation systems are discussed in detail in Soction 9.4. I 12.3.4 AREA RADIATION AND AIRDORNE RADIOACTIVITY ( MONITORING INSTRUMENTATION I The area radiation monitoring systems are discussed in detail in Section 11.5. t t i I yf. Amendment / 12.3-7 , April 30, 1992 [)py.fv 9;/ f 9 l- , -.. _. _ _,. _... _. _. _. _. - _..... _.. -.. _.. _ - _ _, _. -. ~ _

f}ld h & } Insert D Transient sources of greater than 100 R/hr are considered in the System 804" shielding design to ensure adequate shielding is provided. One such source is a spent fuel assembly. During transfer of a spent fuel assembly through the fuel transfer tube, adjacent corridors may experience elevated radiation levels. Streaming from thi n source up through the joint between the Reactor Building and the Noclear Annex has been a concern for the current generation of nuclear plants. The System 804" design utilizes a connected building design to reduce the potential for streaming.- In addition, a lead collar is provided around the fuel transfer tube, as well as several feet of additional concrete shielding to maintain adjacent corridors radiation levels ALAPA. This permits personnel to perform maintenance and inspection activities in a lower -radiation areas and reduces the potential for adverse radiation zones from impacting refueling outage schedules. An inspection area is provided beneath the fuel transfer. tube. A labyrinth entrance and a lockable access point are provided to minimize pornonnel exposure and prevent in ss, to, a high radiation area during fuel movement. G,asivellentat iqure 12.3-1 provide a three dimensional view of the fuel transfer tGlis~,~thTs iolding provided, and the adjacent areas. D Seo-/y J .\\ 'bj# 3 h' t pMU ,f no i t' j-4 e Page 1 of 1

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v v_ v x,.- Initiation of containment isolation upon detection of the loss of RHR;I .y _i_ - n z _J (hlf o Plant communi atioh systems are described in CESSAR-DC Section 9.5.2. The system normally used for plant shutdown operation and maintenance is the Intraplant Sound-Powered Telephone System. Phone jacks connect specific areas of the plant and the control room, and the system is powered from+ diesel-backed power sources. The communications panel in the control room is described in CESSAR-DC Section 18.7.4.13. o Redundant vent lines are provided between the pressurizer and the in-containment refueling water storage tank to prevent significant pressurization of the RCS if occurs with the steam generator nozzle dams installed.~ boiling o The SCS suction isolation valves do not have an auto-closure interlock. As described in CESSAR-DC Section 7.6.1.1.1, the valves are interlocked to prevent them from being opened if. the RCS pressure has not decreased to an acceptablo.value. The interlocks are redundant so that no single failure can prevent the operator from aligning the valves in at least 1 inlet line after RCS pressure requirements have been one SCS satisfied. o The plant design is such that both a high pressure safety injection pump and another means could be available during cold shutdown to add water to the RCS to mitigate loss of RHR capability or RCS inventory if needed. In addition to the design features previously described, midloop operation heatup analyses are performed to provide a basis for operating procedure guidelines. These include the relationships between time after_ shutdown and decay heat, RCS heatup rate and boil-off rate. Guidelines are provided for reduced inventory operating and administrative procedures, including verifying availability of equipment and. W ' 2 oidino 4 cgncurrent op.cstion:L_ttiat,, ygty)Rt]1cJCS, L.L :: ~ Z - ^ :: 70 "i*cduceT1~~1 d; InstrDAntaETorEM'UYIng'SCS ~.m : T ~ oper dion WRii' inventory is described in CESSAR-DC Section 5.4.7.2.6. Since the foregoing design features and guidelines for operations with reduced RCS inventory meet the intent of the recommendations in GL 88-17, this issue is resolved for the System 80+ Standard Design. REFERENCES 1. NUREG-0933, "A Status Report on Unresolved Safety Issues", U.S. Nuclear RegulatoJy Commission, December 1989 Amendment I A-4Si December 21, 1990 .}}

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