Text

Doses in Combined Unit 1 & 2 CR Due to Waste Gas Sys Rupture at Unit 1 with 500 CFM Normal CR Ventilation
	ML20207F647
Person / Time
Site:	Beaver Valley
Issue date:	04/13/1987
From:	; STONE & WEBSTER, INC.
To:	;
Shared Package
ML20207F640	List: ML20207F634; ML20207F647;
References
	UR(B)-452.0, NUDOCS 9903110291
	Download: ML20207F647 (25)
	v • d • e

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ATTACHMENT A A . .

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Beaver Valley Power Station, Unit No. 1 i J

Unreviewed Safety Question License Amendment Request Additional Information l l 3

l Source term calculation package used in determining the control l

! room doses due to a waste gas system line rupture.

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CALCULATION SHEET C ALCUL ATION IDENTIFICATION NUMBER J. O. 0 9 W.O. NO. DIVISION O GROUP C ALCUL ATION N0. OPTIONAL TASK CODE PAGE 15 1 2 2.4 t /.4 % ti o .'$ ) 4% 'S 4 U 9 (6) - Vi2.- O -

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ToItphces (412):$3ecoc nucisas emyon P.o. lier 4 '

8.Ypplagpot).PA 1W814JO4 April 7, 1987 ND1NEH 1144 l I

1 Hr. D. A. Piccione Project Engineer (7.45-14)

Stons and Vabster Engineering Corp.

P. O. Box 232)

Scaton, HA 02107 .

Beaver Valley Power Station - Units 1 and 2 Joint Control Boom Radiation Deze Analysis DCP 611 Cf0 942 _

Dear Mr. Piccionel i Attachment 1 is the data which you have requested to perform the joi..t control room radiation dose annlysia, Attachment 7 is data on the chn1: coal delay tanks writch you have requested. It is requested that this analysis be completed by April 21, 1987. If you have any further questions plesse contact

-Steve Nass (412) 393-5671 or Larry Vinker (412) 393 5707. ,

Very truly.yours, i

/

a vv' k.. llm$

H. H. Siegel, Manager Nuclear Engineering Utpartment Y

4- -

4 5 2.-O 11.191 /I9 10 .19 - o R(6) i WW/jle Attachments ,

cc N. R. Tonat S. Ferguson (245-8) ;

- 5. A. Naaa

.- S. F. I4Vle G. ~ 3. Sovit.K Central File (2) t DCP 611 File a

09

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ATTACUMENT 1 4

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12 Wl / ;w i t o ."$9 -0 d([] - 9 6 2-C)

CONTROL B00H HABITABILITY DUB TO BV1 DBA'S 1

I I. Parameters applicable to all accident analyses:

A. Ratactor - Coolant System

1. Thermal'pover - (core) 2766 i

2. Technical Specification feaction calculate based on ;

of fuel with defects Technical Specification !

('IS'y 3.4.3

3. Tech. Spec. prii.ary coolent calculate l Concentrations -

based on #2 above .

4. Primary to secondary leak rate 1 gym (standard) 1 I

5. Secondary coolant tech, spec. calculato -

concentrations

6. Prir.ary Coolant concentrations uma BV2 Table 15.0-9 l due to pre-accident iodino sniks- l 4

7. Concurrent iodino spike release rates to primary coolant 500 use BV2 Table 15.0-10 tices tech spec. release rates j B. Concurrent iodina spike duration 4 hr (standard)

9. Steam generator fluid content /SG (note 1)

! liquid vt. (ib) 97.900 i 10%

ateam vt. (lb) 6,460 . 8%

6

10. Total steam flow (1b/hr)(all 3 SG) 11.55 x 10 5

3.,,90, x 10 10%

L 11. Total RGB vater (lb) (note 1) i

. Notent-

1. The~ initial steam gouerator and RCS rnass values given in this table best-estimats represent the 100% power (2652 P.WT core pover)

values, for use in defining the relative masses coolant of steam and/or system, vater in the steam generators and ree.ctor i 4

initial casy in the Uncertainties should be supplied to t's appropriate diteetion by the dose analyst. ;

C-

.. . z ._

I Z.t91 /191: c ,39 - UE. (d 4 5 2. - 0 Io harametere applicable to all accident analycret (cont.)

3 Control Boom

1. Volume (ft3 ) (free volur,e) BV1, 114,000; EV7, 59,000 3

2. . Normal intake rate (cfm) Byl, 300;BV2, 200

3. Emergency ventilation iutake BV1, 800-1000 rata (cfrn)

4. ar,ergency vent, filter efficiency 195% overall j I

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llaste Gas 5ystem Rupture Fraction of fuel with defects (design) .01

' Reactor coolant concentrations (design) calculate-Letdown ilev (gpm) (design) l'i0 charcos) delay bade holdup times (days)

'Kr It calculate Fraction of noble gases calculate released from charconi :

delay beds Duration of releaev i hr (standard) for the inlet line rupture (hra) .

GWS tank.s -

No. of tanks 3 3

Volume (f t ) 132 each i Pressure j Operating 65 psig i Deafgn 100 pslg !

Temperature Operating 100*F Design 200'P Pend rate (sef:1) 2 Method of operationi continuous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to shutdown, purifloation flow rate is increased.

A11gncients individually isolated Charcoal delay tanks ho, of tanks 4 charcoal (1b) (each) 1,000 internal diameter l' A" hofght of charcoal 6' 1"

\ 1? % l f! Q i . O , D, ' d , d 'j . ** $ 1 ' O CENDER - RETAIN YELLOW COPY. GEPt.lER - RETURN WHITE COPY.

FORWARD WHITE AND PGNK COPit3. RETAIN PINK COPY FOft FILE.

k h N e> !( D INTERO FICE JORRESPONDENCE TO: l LocATsoN SUBJECT / REFERENCE / J.O. NO. /ggpg be h fdI'@U40/1 l $slg,lpg FROM: l tocATioN (([$ - A g [p r [./

f fj / 1 [ g /g g g b 'll * / $ $/9ffh l 23/$~f)j MESSAGE:-

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l l ATTACHMENT B l Beaver Valley Power Station, Unit No. 1 j Unreviewed Safety Question License Amendment Request !

, Additional Information )

i I t

J Revised UFSAR Table 14.2-8. 1 I

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q BVPS-1-UPDATED FSAR Rsv. 15 (1/97)

' TABLE 14.2-8 PARAMETERS USED IN CONTROL ROOM HABITABILITY ANALYSIS i OF THE WASTE GAS SYSTEM FAILURE ACCIDENT

I 1

Desion Came Power, NWt' '

2766 Fraction of fuel.with defects

,y _0.0025 I Offsite AC power Lost Ta4+4=1 pr i == ~ -; :t z r. .. , d. 1-15y , puf y. 1. 0 -

Letdown flow rate, gym 120 i Analysis cases 1 Rupture of Wasta Gas Storage Tank (WGST) '

Rupture of Gaseous Waste System line upstream of charcoal delay beds Volume of *,.4ST, ft 132 WGST feed rate, scfm 2

Gaseous Waste System operating pressure, psig 65 Gr.seous Waste system operating temperature, *F 100 Charcoal bed holdup time, days Krypton Xenon 2.1 38.7 Control Room volume, ft 1.73E+5 Control Room normal intake, cfm 500 Control Room isolation None**

Control Room purging None f Control Room I/Q values, sec/m3 Auxiliary Building 0-8 hours (line rupture case) he J.}.st-4,94t=S*

Gaseous Waste Vault 0-8 hours (WGST rupture case)' 2.03E-2 Analysis references ibti'='"'-'55 12Mi[j4110.39-04 456j

This analysis was. originally performed in 1987 in support of plant modifications converting the Unit 1 Control Room to. a common Unit 1 - Unit 2 facility. The analysis inputs, assumptions, and methodologies are based on regulatory requirements that existed at the time the analysis was performed, and may differ from those used in the offsite dose calculations.

- An ndicated t JUT or the 1 pture c CRERAPS a ion wi occur. H , isolation is' required to t ancie erl+=ri .

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M%e.date cele Intion conswa tively Miument tint ele t% tivl mm vnelia tton non hkvs tariIl not initik te Con trul tvem trole w .

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g. ,

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ML20207F647

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