ML20090K668

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Forwards Supporting Documentation for Data Transmitted Via Emergency Response Data Sys,Per NRC Request,Consisting of Series of Graphs from EPIPs & Technical Data Book
ML20090K668
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/13/1992
From: Gates W
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-92-087R, LIC-92-87R, NUDOCS 9203190189
Download: ML20090K668 (22)
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Text

{{#Wiki_filter:. m. ~ ..~ ~.... - -. -,... 2 nr w~ ~. x... - ~ m m -- =~~m' ~~~~~ i k i I e, Omaha Public Power District ..A Douth 16th S'.rtet M3!! tr xm. Nebraska G8102-2247 March 13, 1992 Lit-92 087R V.S. Nuclear Reculatory Commission AlTN: Document' Control Desk Hall Station Pl-137 Washington, DC 20555 Referents: 1. Docket No. 50-285 2. t etter from 0 PPD (W. G. Gates) to NRC 22,1991 (LIC-91-315R)(Document Control Desk), dated November Gentlemen:

SUBJECT:

Supporting Documentation for Data Transmitted via the Emergency Response Data System in response to a request from Mr. J. R. Jolicoeur of your staff, attached is a series of graphs from the Fort Calhoun Station Emergency Plan implementing "rocedures and Technical Data Book. These graphs art for use in evaluating and interpreting data to be transmitted via the Emergency Response Data System (FRDS). The graphs include:

1..2 to EPIP-TSC for evaluating RCS inventory (cubic feet) from pressurizer level (percent).

2. Technical Data Book figures TOB-Ill.l.a through T08.111.2 - for converting indicated pressurizer level (percent) to actual pressurizer level (percent).

3..3 to EPIP-TSC Ior evaluating RCS inventory (cubic feet) from Reactor Vessel level Monitoring System (RVLMS) indication (percent).

4. Technical Data Book figure 10B-111.28 - for evaluating liquid level in the reactor vessel (percent) from the RVLMS indication. 5. Technical Data Book figures !!!.3.h through 111.3.0 - for cowerting steam generator level (percent) between narrow and wide range and evaluating indicated versus acNal steam generator wide range level (percent). 6. Technical Data Book figure 108-ill-3.p - Shows the steam generator component elevations (including level indication taps). 7. Appendix 6 to r9]P-TSC for evaluat.ing containment building water level (feet) versus volume of water in containment (cubic feet) for the wide range containment water level instrumentation. 9;!O3190199 9 0313 POR ADOCK 05000JG5 I {, f,': ( F ppR aw j e (n. v ~I cn, ww own d 8*~ M w/fHre;

. ~ - - - -. _ - - _ - - 4 0 ) 8 4 LIC-92 087R Page 2 i i 8. Appendix 7 to EPIP 1SC-8 for evaluating containment sump water volume (gallons and cubic f eet) ter level parameter.versus indicated level (i the narrow range containment wa t Clarification was also requested for the sensativity factors provided in { Reference 2 for the radiation monitor readings which are transmitted via the ERDS. These factors account for a conversion from counts per minute (CPM) provided by the monitor to an isotope radioactivity level in microcuries per milliliter (pC1/ml)itors RM056A, RM054A and RM0548, the monitored isotope it. CS-For monitors RM063H, RM057 and RM064, the monitored isotope l is XE.133. For mon 137. Any g estions pertaining to this data can be answered by our ERDS contact, Mr. T. A. Heng at (402) 636 3416. If you should have any questions, please contact me. Sincerely, AV h. W. G. Gates Division Manaaor Nuclear Operaf. ions WGG/sel I Attachment c: Leboeuf, Lamb, i.elby & MacRae R. D. Martin NRC Regional Administrator, Region IV s D. L. Wiggington, NRC Sbnior Project Manager J. R. Jo11 coeur, NRC-AE00 S. D. Bloom, NRC Project Engineer I R. P. Mullikin NRC Senior Resident inspector i H. Borchert Director-DivisionofRadiologicalHealth. t Nebraskadepartmentofllealth - T. P. LaRosa, Halliburton NUS l l l l 1 i ? p i 1 l

... q... .. ~ - - ' FORT CAI/IOUlf STATIOll EPIP TSC-8 Eh!ERGEllCY PLAN IMPLEME!1TI!1G PROCEDURES PAG" 16 OP 44 ATTACl!ME!1T 6. 2 RL:. INVENTORY USING PRESSURIZER LEVEL Page 1 of 1 3 8000 Primay Wlume iFt ) 7500< Pressurizer Level (%) 7000-6785 100 166fX) g 6500-L9 7 6M0 Top of so Tube $ 1 62 54 ~ 6000-ll* 39,7

57LO, 25,7 5500 5500 H7 5292 0

5000 Top of Upper Head SN b 4500- ~ From Top of Upper Head 4000-to 'Ibp of Active Core See Attachment 3 3000-I 2500< 2000< Tbp of Active Core 1823 Bottom of Active Cone 1309 1000-500- ) B ttom cf Core Cold Plenum 0 o FC/EPIP/02A R6

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TDB-fl!.1,b PRESSURIZER LEVEL CORRECTION (Density Effects Correction) L-101 100_ l -,- r r-r,, 95 : I l I I il,l---+- --e-I i l V -- r -- i h b l 1 l 4 /I i 3 h l l l l l i ~ i i i i i/ ii 90 -: . - Ambient Temperature = 120 deg. f -~1' 2100 osta ~ ~ j / -l 85 j ! NOTE: TemperaturerAtatncdfrom i V g ERF points 1-88 /,888,889, /' l lM J 80-: and 890. 8/j_,800 psia /f ) 3 75 L l 70 l / / l }i 7 m / / /< a 65 ~ N i / / /dOO esis / / / v 6 0 _-

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.d INDICATED PRESSURIZER LEVEL SEP08 icy 7 ( % Tap Span ) R2 09-08 87 L .. a

TDB-III.l.c PRESSURIZER LEVEL CORRECTION (Density Ef fects Correction) L-101 100 1 Ii I 1 95 2 -i 1 i i l i l 2l00osia /i 90 - - Ambient Temperature a 200 deg F -. !.. X.J l / I ! HOTE: Temperaturaentsinesfrom _ j__. f l 85 i l ERf points T-887,888,889, I l j/ l _a _, 1 80 - ond 890. __ 1 7 ] l j j l l l / 1000 osia j t g 75=: -+ L-v' J, / ld o i i ay ' e 70 J a L~ i / i 65 " - - - /y'l a b" 60.! !A / i/ / i a ,,300 psto y i w 55 L / ,e' /,/ /,/ i / I 50 : / +d -t A5 -l h Y fl / E i /'/ / j n. / g/ 3 5.' a 4 /c-( l3 30 i-4 m i' // I 25-:

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TCB-ll!.1.e PRESSURl2ER LEVEL CORRECTION (Densit.y Ef fects Correction) L-101 100 l 2 I I 95 ; c i i I i I l l l l 4 i 90-l-' AmbleN Tempercii.re 300 deg F 'M i l _,2$0psg i L5 ! NOTE: Imp 2;t 8 ctoinW fron. ..L_ j ERf points T-887,888,889, i 00 +- oM o90-l j i/j N i i i iei 4 I I I/b 75 E l I l I l iI ' b00 0siel S 70 2 L l I t! i / J j l l l/ /!./ g 65 : l i. 4 x i l l 1 / / l'. 60 i d i i i jf I I 7-' i i 3 55 4 d I / / 300 osia i .a W 50 : / / a: l / / i i m I / / 45 } s s' / / i 4: I / / / ly EE i / // l a. 35i- / ,,2. i f / /'/ L 30 '~ ---= \\ U lV / l 25 " I i i l '(Y l l 20 ~ l 15 2 gf i I l / l. i + l 10 : t v---- 3 M,,,/ t I i 5 ,e f

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FORT CALHOUN STATIOli EPIP-TSC-8 EMERGENCY PLAN IMPLEMENTING PROCEDURES PAGE 17 0F 44 ATTACHMENT 6.3 RCS INVEllTORY USING RVLMS 3 Primary Volume (Ft ) gg RVLMS (fo) 3$00- _.3221 Top of Upper Head 100 1 3000 2%7 L183 l 4 2365 L2 63 2300-2fX4 d *- Top of Hot Leg L3 43 1500-t r. 1G(4 908_ Centerlin.t of Nozrje t,. 29 -500 L 357 Bottom of Hot Leg U 21 I 253 L614 l 166 L7 8 - l IgP Lg o 44 0 From Top of Active _ Core =.. FC/EPIP/02A C6 e

TD3 111.08 HEIGH! (ltod$ L(H%R INDICAf(D P 051l10t4 LlH%iR AS(Nf FAP) 1,1 Yll t[tB,,. ' ". 'A 100 00h 10P b HUa 1 180 22 92558 63 005 141PO*f S Bil0W 10? Of HCAD 2 i42 34 73 102 63 C0% 100 a tvorp rupt LTRlcivRt 3 10453 's3 f 8 5 43005 4 66 62 34225 29 001100 Cf hof Lf 0 5 50 62 2t,004 21005 tilM4 L Li H01L(0 6 34 62 17181 14 005 60fitt1(W H0ill0 7 '/2.3 4 11 475 6005 e 10 09 51(

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.....m.--___. 4 TORTL CAutotJN STATION-EPIP-TSC-B -EMERGENCY PLAN IMPLEMENTING PROCEDURES PAGE 40 OF 44 ATTAClU(ENT 6.10 1 (Continued) Pago 12 of 1c APPENDIX 6 CONTAINMENT BUILDING WATER LEVEL vs. VOLUME 8 -~_ ~ rf-7 i (~ r i / 6 5-g L w g / .a 4 ta LJ J 3 ] i. 2 C-t / .l / i L OMl 'l l W ''1 L i''' i -7 i i 0 10000 20000 30000 40000 50000 3 VOLUME, FT -FC/EPIP/02A R6 L }

TORT CALHOUN STATION EPIP-TSC-8 EMERGENCY PLAN IMPLEMENTING PROCEDURES PAGE 4L OF 44 ATTACIIMENT 6.10 (Continued) Page l') of 16 APPENDIX 7 CONTAIRMENT SUMP CURVE LEVEL va, VOLUME GALS. FT3 110 L14.71 l I l t ' JOT. I 102 i 100 -13.36 i + l __ j 90 -1'i. 03--- i / ~ t ~+ 7-n w "r 80 -j10.70l -+ L g [ +- i I 70 - 9,36 ~ ~ ~ ^, 4-g I t r 5 /l j 60 r 8.02-o e \\ f ~ h \\ 50 - 6.03 ) y ,3 I t 3 [ O 40 4 S.3$ j i c. 2 _m 30 - 4.01 l l l \\ / 2

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