ML19263C406
| ML19263C406 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/13/1979 |
| From: | Shively C ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19263C404 | List: |
| References | |
| NUDOCS 7902220070 | |
| Download: ML19263C406 (5) | |
Text
.
AVER \GL D AILY UNIT POhER LEVEL 9 50-313 DOCKIT N o.
i NIi AN011 02-13-79 I)tII CO\1PlEILD fiY C. N. Shively T E LFPHON'E 501-968-2519
\10N111 Jingary_.
J DAY AVER AGE DAILY POWER LEVEL DAY AVER 4GE DAILY POWER LEVEL
( \tWe-Net i ( MWe-NeO l Q l7 0 0
2 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 0 22 7 0 23 O M 0 24 0 9 0 25 0 10 0 0 26 11 0 27 0 12 0 2h a l3 0 -
29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCIlONS On this format. int the au: ice Ja;h inut ,umer lesel ni MWe Net f or each day ni the repoiling in,' nth. ('oinpute to the nearest whole nepwati 07/77) 7902220078
OPERATING DATA REPORT DOCKE I NO _50-313 DATE _02 7 9 COMPLETED fly C . N. Shively TELEP110NE 5 0 ! - 0 6 8 - 2 519 OPERATING STATUS Arkansas Nuclear One - lin i t 1 N '"
- 1. Unit Name:
- 2. Reporting Period: January 1-31. 1979
- 3. Licensed Thennal Power iMbt r 2568
- 4. Nameplate Rating (Gross MWe) 902.74 ,
- 5. Design Electrical Rating (Net MWe): 6 f2.D_
- 6. Masimum Dependable Capacity (C=w MWe): 883
- 7. Masimum Dependable Capacity (Net MWe): 836
- 8. If Changes Occur i Tapacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasont None
- 9. Power Lesel To Which Restricted,if Any (Net MWe): None
- 10. Reasons For Restrictions. If Any: NA This Month Yr..to.Date Cumulatise i1. Ilours in Reporting Period 744.0 744.0 36115.0
- 12. Number Of flours Reactor Was Critical 0.0 0.0 25710.I
- 13. Reactor Rewne Shutdown llours 522.2 522.2 2512.'T
- 14. flours Generator On.Line 0 0 0.0 25213.7
- 15. Unit Resene Shutdown llours 0.0 0.0 205.2
- 16. Gross Thermal Energy Generated (MWil) 0.0 0.0 60806709.0 17 Gross El ctrical Energy Generated (MhH) 0.O__, 0.0 20240681.0
- 18. Net Electrical Energy Generated (MWH) _
0.0 0.0 19310546.0
- 19. Unit Senice Factor 0.0 0.0 69.8-
- 20. Unit Asailability Factor 0.0 0.0 70.4
- 21. Unit Capacity Factor (Using MDC Net) O.0 0.0 64.0
- 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 62.9
- 23. Unit Forced Outage Rate 100.Oi 100.0% 13.2
- 24. Shutdowns Scheduled Over Nest 6 Months (Type, Date, and Duration of Each):
9cheduled Refueline _
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA
- 26. Units in Test Status (Prior to Commercial Operation) Forecast Achieved INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCI AL OPER ATION N/77)
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DATE: .la n na ry ,1979 REFUELING INFORMATION
- 1. Name of facility. Arkansas Nuclear ane-Unit 1
- 2. Scheduled date for next refueling shutdown. n3_23_70
- 3. Scheduled date for restart following refueling. 05-23-79
- 4. Will refueling c resumption of operation th;reafter require a technical specification change or other license amendment?
If answer is yes, what, in general, will these be?
If answer in no, has the reload fuel design and core configuratic1 been reviewed by your Plant Safety Review Committee to deteneine whether any unreviewed safety questions are associated with the core reload (nef. 10 CFR Section 50.59)?
_Yes. see letter to Reid dated 11-9-78.
- 5. Scheduled date(s) for submitting proposed licenaing action and supporting information. 11_9_ q r i c + ,, .i i i
- 6. Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
h'i l l reload 64 fresh fuel assemblies and operate for approximately 16 months
- 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 112
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in nu=ber of fuel assemblics.
present 590 increase size by 0
- 9. The projected date of the laat refueling that can be discharged to the apent fuel pool acou =ing the present licensed capacity.
DATE: March , 1988
NRC MONTiiLY OPERATING REPORT Operating Sununary - January, 1979 Unit 1 The unit remained shutdown throughout the month due to the Low Pressure Turbine blading failure. The damaged rotor was replaced.
Adjustments were made to the Once Through Steam Generator downcomer orifice plates in order to improve operating stability at partial power levels.
A portion of the Refueling Outage #3 Inservice Inspection Program was completed during the outage. One volumetric exam, nine surface exams and thirty-two visual examinations were conducted.
Approval was obtained from the NRC to discontinue the use of sodium thiosulfate in the Emergency Core Cooling System. The sodium thiosul-fate tank was drained and valves connectud to the Emergency Core Cooling System were locked closed.
On 1-12-79, during the liydrogen Purge Standby Unit Surveillance Test, the required flow could not be obtained. The air flow was restricted due to a collapsed inlet filter. A design change is being engineered to prevent water from entering the filter housing and damaging the filter (Reference LER 50-313/79-001).
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SHMPP WELL PERMEAMETER TEST A V g - 2 9 - F - / - pF-J TESM D L 0C ATION TEsr nu VR 4. J M.E W /S. Brwud M 100 sd"LSDO ,
OBSERVATION HOLE
STRATA DEPTH ( f t. ) . . SOIL CLASSIFICATION FROM TO O 2.O WCWM CMYEV SgMEMl .
77sr Fitt (T2Aucem i2mkriu_)
- l. DEPTH (f t.) TO WATER TABLE:
2, DEPTH (f t.) TO GROUND SURFACE f
- 3. DEPTH (f t.) TO BOTTOM OF WELL: 2.73
- 4. DEPTH (f t.) TO TOP OF SAND: o,co
- 5. DEPTH (f t.) 0F SAND (3) -(4) . 2.23
- 6. DEPTH (f t.) TO WATER SURFACE IN WELL: O ' OD
- 7. DEPTH (it.) 0F WATER IN WELL h=(3) -(n. 2.co
- 8. DENSITY (pcf) 0F STANDARD SAND 45.4o 9 WEIGHT (lb) 0F SAND + CONTAINER BEFORE FILLING WELL: 3 2 . I d' IO.WEIGliT (lb) 0F SAND + CONTAINER AFTER FILLING WELL: 3 . o 5-1I WEIGHT (lb) 0F SAND USED( 9)-(10): 29.Io i 2.VOLLHE (cu. f t.) 0F WELL (11),(8) : o ao 5
- 13. RADIUS ( f t. ) 0F WELL r= / (12) _ _ _ . _ _ _ . _ . . _. .A. . _lS E (5) w TOOL iD CP'-C -436G
n SH!!PP WELL PERMEAMETER TEST V g - 2 4 - V / p 7 .7_
E
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M tso D 2.Sco OBSERVATION HOLE STRATA DEPTH (f t.) SOIL CLASSIFICATION FROM TO O'_ +* -B'sgad _c_t.Aysy s^cestoac
. T2MDom Eccxpat. . .
(, DEPTH ( f t.) TO WATER TABLE: g/4 2, DEPTH (ft.) TO GROUND SUEFACE a/j
- 3. DEPTH (f t.) TO BOTTOM OF WELL: 2. 9.T
- 4. DEPTH (f t.) TO TOP OF SAND: 4.00
- 5. DEFIH (f t.) OF SAND (3) -(4) 2 83
- 6. DEPTH (f t.) TO WATER SURFACE IN WELL:
- 7. DEPTH (it.) 0F WATER IN WELL h=(3) -(M . 24o
- 8. DENSITY (pcf) 0F STANDARD SAND 95.g
- 9. WEIGHT (lb) 0F SAND + CONTAINER BEFORE FILLING WELL: 3g,3 IO. WEIGHT (1b) 0F SAND + CONTAINER AFTER FILLING WELL: F.o Il WEIGHT (ib) 0F SAND USED( 9)-(10): 27.3
- 12. VOLUME (cu. f t.) 0F WELL (11),(8) : o.266
- 13. RADIUS (ft. ) 0F WELL r= / (12) 0 . I 7?_ _ __ _ .
(5) w TOOL ID C R- C- 4 M6
~. .
~
SHNFP
'4 ELL PERMEAMETER TEST y R - 2 % / - ['[' Z TIME 'JATER VOLUME ACCOM, DRUM NUMEER DRUM NUMBER TOTAL ACCUM, TEMPERATURE CLOCK (MIN.) READING DIFFEREfCi READIt:0 JIFFERENCF DIFFERENC:: FLOW l .' /D l. fso /3.o 2 :lo (so /. 4o 0. 2.0 0,10 0.2D / 3.0 1.:40 90 / . 15 c. W 0. 2 f 0.4f /2.f 3: to fM o, W o.29 0.20 0 . foC 12 0 3*40 /So 0 . 75~ 0.20 0.Z0 0 . VD" / /.1 4'; lo / G'O 0 . 55~ 0.20 0. Z 0 f .oS //. ~5 4: 40 Ato D 3S~ C*10 0.70 7.2C /t.*
O
s'
- 4 CAROLINA POWER & LIGHT SHEARON HARRIS' NUCLEAR POWER PLANT .
COEFFICI-ENT OF PER!E. ABILITY b
Sample No. VR-3+- 4 -l - PL - 1 Date 14- 26 '7?
Location M too W tsoo Tested By S M . fb.w [ul.o.Aeoco Description h ere h t_(R%com A kkfil)
WATER CONTENT , DENSITY , ,
~
Wt. Container' Md Wt. Mold + Soil n/a Wt. Cont. + Wet Soil 2co.o Wt. Mold qt2 Wt. Cont. + Dry Soil 18 7. 6~ Wet Density f 4 7. 0 Moisture Content 6. G"7 Dry Density I37.6 Standpipe Cross Sectional Area, a = d/a sq cm Sample Cross Sectional Area, A = 73 0. ( sq cm Sample Length, L = 21.?6 cm ]
Constant Head Test No. h, cm t, sec Q, cc -T, C k, cm/see
. l 4 S.72 If 43.0 1200 2o.0 7 2,X/C' K=b Aht .
(
Ve ia'ile Head Test No. h,, cm t.
h.,, em t ,, k, cm/sec b L"h2 K = At ( g/ ,
a 1
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. 9 CAROLINA POWER & LIGHT SHEARON HARRIS' NUCLEAR POWER PLANT .
COEFFICIENT OF PERMEABILITY t
Sample No . VR .Z4 / - F4. Date /2 -f'- 7 5I Location Al doo D 2 s~o Tested By S.M.8%00 f bd. 4. RuocM Deseription rese s,u . sea.c [
EU'TEC &ck f*&wocm & %L-yll WA.TER CONTENT , DENSITY , ,
Wt. Container'
~
A/$ Wt. Mold + Soil J/e Wt. Cont. + Wet Soil 2 40 0 <x Wt. Mold 4/4 Wt. Cont. + Dry Soil M 'y Wet Density / 4/a . O Moisture Content f. 9 7o Dry Density /3 '7. 6 Standpipe Cross Sectional Area, a = 4/,* sq cm Sample Cross Sectional Area, A = 7.30.02 sq cm Sample Length, L = .:22, 8 6 cm ]
Constant Head Test No. h, em t, sec Q, cc T. C <. em/see
- n. 2. - A //3..f too .2:S~o f 1o.0 3.o3 51o ~
" '0 %35 K = Aht /Z 0 0 VT50 20.0 2. 9/ X/e '
C y3. 5 /200 7750 zo.o .
- 2. vius
l Variable Head __ Test No. h, , cm t, h ' ""
2 t k' "/**"
K = AtLn h2 L '
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COMMENTS Y
CAROLIllA POWER.& LIGHT CO.
HARRIS.4ITE.
l US STANDARD SIEVE SIZES
, , , A* f" . [S/4" 1/8" 4 ? IO f,' 20 b. 40 +go 100 200 l
N ! ,
i i : : :
So l s i
s . .
l l I 80 ' '
i k
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10 0 10 ID OJ Q01 QD01 GRAIN SIZE IN WILLIMETERS DOUL ORAVEL SAND FINES DERS COARSE FIN E COARSE MEDIUM FIN E SILT SITES CLAY SIZ ES SAMPLE F10. LOCATION NAT WC LL PL PI DESCRIPTION OR CL AS SIFIC ATI ON m-2+ i ai , GRAIN SIZE DISTRIBUTION sf v a-2+ - + - i
{ - -
ELASTED ROCK , TRANDCM DATE: 12 76 INSPECTOR G St. Ba W '
Gnoe/efion rf LJ 3 PViTM9J W f-kre a f/y "'+*~ l ' kc~pund i*l
- CllECKED a t,,ee/
f ei f r , //
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1
CAROLINA POWER & LIGHT
. SIEVE ANALYSIS (Large Scale Gradation)
SAMPLE NUMBER T R. .2 4 - g - / DATE /4 .?'7 - 7 9 LOCATION // /do D 2Svo TEST METHOD 45r# O (2,1.
DESCRIPTION TEsr fiu- SnmmG f Bmrw Rxk . /% &h s '
(Smpw dmnon stemnw ;o ?ha . 72: .r Vit-2%-%~l~ PL 2 __
Sieve Accumulativc p Percent Percent Percent No./ Weight Retained Passing Fassing Passing Siie' Retained Subtotal Subtotal Total 3 0,00 0*oD /so.co o
I T, /2 22, .2 / . 40 4, l 757. 44 gl
% .22.2.9 m 39 y s/ a?
/g 30 47 S3. 7 / % .2 9 4- 37.54 Cf.14 3 + . .t &
T 4.3. o 9 75.4G .2 4. 6*&
/b 57./o -
l l
i
/ c_. ,, no .4o .y 37. Ci 71.35' ! /7.7i ac S co . 90 c, Sc.23 +1 77 11.21 5c 272 25 9 4x 21 3/.79 7.20
/cc .3.1 s". /9 g _ _ g; , 2.1 /g.71 4. ST
.2 c c Ja3 1 .
, _ _ yo , y a g 9 20 2.16
__. 7 P++2 +o C.0 0 g -
Calibrated Equipment Used: Inspector SruwNMuk Fe,J _,
Tool ID Nu=ber cpt - 499364 l
QA Review gM h
' f
CAROLINA POWER & LIGHT SHEARON HARRIS' NUCLEAR POWER PLANT .
COEFFICIENT OF PERMFABILITY Sample No. Vg -Zl,t - tp f - ps - 3 9,g, j,7l2gl7f Location W /0o W .2 5' o a Tested By h./11 8rewA / W. # 8/ cu Description O/4 r /c./ A'd a u Xd C/C'[///
WATER CONTENT , DENSITY , ,
Wt. Container ' bbd Wt. Mold + Soil #!A W "- ;. + Wet Soil 2 00. 6 V Wt. Mold /'///
r int. + Dry Soil /78 O 9 Wet Density /b3+ / *//Y' Moisture Content 5. 3 2 Dry Density /37.9 Y Standpipe Cross Sectional Area, a = A sq cm Sample Cross Sectional Area, A = 730, 6 sq cm Sample Length, L = 22SI cm ~;
Constant Head Test No. h, em t, sec Q, cc T. C k. cm/see A +3. 4 Goo 2/62 20
~
- 2. 4 x.-!c '
K=l Aht B ( 700 2?30 7 2 3 xio '
~
) /7 %0
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( 3oo 950 f 2. 4 3 Y /0 ~'
E } C0o ll2 5 ) /. 3 't X tc '
~
f l 1200 /$ 75 ( /. /2 x /C "
G W (r 0 C q2 5 4 '9.%/to*Y Variable Head ._ Test No. h,, cm t, h,,, cm t ,, ,, cm/see K=b^'Ln"
> / A
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A -
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2 I
CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT FIELD INSPECTION REPORT Date /L/Uf'79
/ /
Spec. No. 8//-l OOf LocatioL A/ /oo M)25m Inspector 8 Ad. M o e Elevation 75L Shift Day
-- Weather Cum Idwov , b/-
COMMENT py,g .t. e2 T~est Fa.L. MR 4 - I LCAS SrA RTED 7eMV AfrM :TEL6cnWG-ska Ar%EA AD3nc5MT To THE EMERGENCY GERt/tcE J/to rurAKE CMAUMEL .
M AREA toA 5 SCAAGEL> TD 4 LEVEL S M o o T H GlLR fA C E AMD THEA)
Rot LEO Bs/ A VtBRATDRV I?oLL&e (SGLf-MCP5LLfo ) . G ENsut25 A FIRM BASE , TEN PbtM75 (ExPEcrEOTD BE ukrH/W 7MPR/NC/ PAL AREA of YH2 rest ~ flu.) tuetel= setscrED AMD THeiR ELEv'ATioNS 'R&# ^tCED - AP7ZC4 TEA /(e) RouEe Passes 792 fewrs MERE REENor n CALn - ArE PossueLc serTLEMEnT ~7NE .SETTLEMEA/r 4)s95 NEGL/St E .
. A rER serne w= rwe %-~Es sore m resr , me e,urr-rue 4f LJFr tDA s EAto -btiMPED cm- YMG EM LToftD6At gy-LJh3 TNfr)
Sptnao tarro A 2 A - ice n Ltfr av s D-O tc~ Zee. TRAv&L. wbd vWf i t P r* BV BorH THE EttwDs AUD Z';e1ee 40 % kEpr re TNv Sw2sr-1%1o WiM st m . A FTEft epMDLPrf/WG TW2 FILL- As)O SerH RAM);K THg"
- or crYeArt/c BAct' D24t%GO *fM6 ENTlCE AREA TD SMoo7H THE ~%AFACE.
tys RCL.LEf? A ~RASCAt. (sco A HT3w P>eccEEDED TD FutTHEk smeern ryg ARcA prpKiN& s+Al /Nt riet. PA.ss ps RawDED /g SEcr7es.)
4.1. 4 of TP-0I THE TWEAJr 't' - FM (x4) SET 7wmEar Fbturs 4'ERE
-nJE^' P!N TED CA THE SuRFA-c f TO S E G A) TN2 AcrtzAL sDseC C E OLL E E Hou)EVGE DuZ TD TMf E L)MirA r/ OMS RoLUNG CA=R.477o 45 cowi.O AJO T* BG SrM2 rep (600 A )
INSPECTOR Q A REVIEW
I l
CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT FIELD INSPECTION REPORT Date /a ,/// 7B Spec. No. CN-+ 7P-o/
Location Al foo L<) ttreo Inspector S. M. BecaA Elevation 25D- Shift .Dav
.. Wea ther d'4oy , ME [ %'-
COMMENT pnc,6 2 of 2.
7 7,18 MA-722/*t. Ase 77t/S F/RC7~ L /57' h)h5 7A-KEA) FROM fL2 VAT 7 0A) 22.0 NEAft SrrtT7oAl 8 + C0 ef THE &ea dG TesOEA NA<f- lLP Ytb ism 2 M coa /S/ STT 8f A 73ResuN SAMOV 5/L75TDAJ2 AA/O
/s dreROPC) LAP TD 2/ /NCHes i<)/ TH Afo3r* FrendMErt/75 P'e st! To isNGrd 5 /WCMES /Af c' AfrErt R2co/ED/A/G 77 2 /A//77M Lifr~ TN/CKNE-SS AA/D &NGioclus't?*
N$Xr D4VS AC77 t/77ES uhM /dfS 14427fD Dchf 73 Dag MESS INSPECTOR , d[h Q A REVIEW //A/M
/
/-//-27
. d
CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT' FIELD INSPECTION REPORT Date C// N 7P o /
l'Lf/ 2l7 V Spec. No.
Location N /oo A.) 262D Inspector & M. BeeusA Elevation -2 f3 Shift .D a v
-- Weather Id/wov f Soc COMMER f%cyg 1e2
~
Apree rw i<>iriu. Licr ruicxxess AA/D TBAf M RECMr 7HE vreenroev Rev d A SEGkAl rys /Atirine P M ES. zr's 3WD t;MS 2AsEO ea 3 mias /
'ouse 2 /r AvEensED /95 sEcwns rc cc M rME S6"FEfr of VESY ARPA , THE y/ S ge 77e ds l< M A f REMotorb ?-c /3E tarW/^) -THE //co ro /Sho nevt TesAt &E So fen 77/E r/Rsr* PnssEs . 7WE Nr8RArcRt/ Rou.E2 2 des /A) com R,tA,VCE ukrH 7P-Qf
- W ro mw e rxAe assmarry er em a,o a ne same,uear- nors.
\ '
ryc Rei LGe (A.46 ins-e:<.cEO To CzsircnxE srsers es* ry,/E ic bixirs of EAcH Ros AND YNEA) 6vf<> +P 2)' /cR MME FEs=rh
/
Aerce EAc4 CP W2 TE-N Passes TH6 Sbsers (4EAf SNc7~ ' rb CenshLTE GErrt.EMErV7 tdirW rWE f)RSEsf D/FfpA)E-svt~.E' Secs) A,crEA 7?E IN/77M- pas 5 BREAST' Dea /Al ff 77h
- S u 2 fAH1 E' Ortu?. LEO Suc)/
77Mr Afr2A T M' 774fCD PACC . rWG voids B f 9 A) YD Fiu- s3 M StV PhssES Y?/2 S&M t.dA 3 GEAMeAt 1 si L.ts// f c k sv) uyrd MidcR SwEranor/S (11 ' t.AMEA'-- BouLDGAS FRarGUDIA/Cs 2TE . .
THE= de M P W T7M) [F TW& YfMrH S&f7tE1MErvr cau=cx mc^ist.Eo 78E SE6/NN/MCs- CF YNC SCeedD l-ifr. AS SmrED JW VES TELDm,i S Rff:ber 7PE M m sn. t<>As Evo - Ou.sv1PEb BV M bs cA) r ,JE E~Asr StOE AAID PhSeteD Ld=$rtuARD BY 'rHE D- EJ Dc2ER toro A ?A. txta u mr.
T/h" MATER >Ar ,
as tats. ALL PUVEO IAl TN9 Y E 5 7" P / U . _ (JAS EWCAvh W ccvro INSPECTOR Q A REVIEW a
n CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT FIELD INSPECTION REPORT Date /2/>2l-76*
Spec. No. d/Pf p 7~-o/
/
Location A//do M 2540 Inspector 9 A1. M1m-Elevation 259 Shift hy
-~
Weather (Awev l Cces.
C0FDENT Pac,e 2 oF 2 ft2eM 77/9 CAC4 JA/6 70LOEnt NAffkA lr'tO ldhY S A S7" C S IM S M o'~
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Location A/ /oo d2nd Inspector M.AN Reed '
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I , TABLE OF C0f1TEf1TS Ef'VIR0ilMENTAL MONITOP,ING LOW LEVEL LIQUID EFFLUEf4TS GASE0US EFFLUENTS SURVEILLANCE TESTS LOW LEVEL LIQUID WASTE TREATMEllT PLAflT PERFORMAtlCE TABLE 1 LIQUID EFFLUENTS--1978 TABLE 2 GASEOUS EFFLUENTS--1978 TABLE 3 SURVEILLAtlCE TESTS TABLE 4 FILTER REPLACEMENT PROCESSIflG
SUMMARY
NUCLEAR FUEL
SUMMARY
TABLE 5 NUCLEAR FUEL STATUS - DECEMBER 31, 1978 RADI0 ACTIVE WASTE FACILITY PEP,F0PfWlCE AND MODIFICATIONS ATTACHMENT - 8D-2 PAN TESTS s.
\
Et;VIRONMENTAL MONITORII;G_ f -
\
As a result of changes in Technical Specifications, sbjnpling milk for 131I was dis-continued on September 21, 1973. Thirty-nine (39) samples were obtained during the fourth quarter from the perimeter monitoring stations and were analyzed for alpha and beta activity. The aloha activity ranged from 1.38 (10 16) to 1.40 (10 15~ pCi/ml for an average of 3.91 (10 16) pCi/ml. The beta activity ranged from 7.35(10l5)to4.54(10 14) pCi/ml with an average of 2.02 (10 14) pCi/ml. LOW LEVEL LIQUID EFFLUENTS The amounts of radioactivity in liquid discharged from the plant during this period and their relationship to the maximum permissible concentration (11PC) in the Cattaraugus Creek are shown in Table 1. GASE0US EFFLUENTS The amount of particulate radioactivity discharged via the plant stack and the relationship to the release limit in the Technical Specifications is shown in Table
- 2. Change 20 to the Technical Specifications discontinued the requirements of Krypton-85 and Iodine-131 monitoring while plant operations are suspended.
SURVEILLANCE TESTS During this period, tests were performed in accordance with Section 6 of the Technical Specifications. The completion dates are shown in Tables 3 and 4. LOW LEVEL LIQUID WASTE TREATMENT PLANT PERFORMANCE During this period, the LLWT was in operation a total of 16 days and treated 1,370,000 gallons of water. Sixty-six (66) drums of concentrated sludge were removed, each having a radiation level of <10 mr/hr. Decontamination of waste water continues to be good. All water discharged Tias been below 2.0 x 10 5 pCi Csl37/nl. Average removal facters for this period are shown below. AVERAGE REMOVAL FACTOR Isotope Previous A rter_ This Quarter Cs-137 93.7 94.7 Sr-90 Insufficient Data Insufficient Data Ru-Rh-106 Insufficient Data Insufficient Data Gross Beta 96.8 94.9 l'o significant developments or modifications to the facility have occurred during the past quarter and operation has been routine.
, Table 1
_L I._QU_I_D EFFLUEf1TS--1978 ' ,
\
f 90 129 % tiPC" f4aasured lionth Gross a Gross 8 Tritium Sr 7 In Cattaraunus Creek Jan 0.00092 0.087 433 0.0023 0.00005 1.74 Feb 0.00007 0.040 166 0.0009 0.00002 1.61 Mar 0.00014 0.024 110 0.0016 0.00007 0.45 Apr 0.000001 0.00007 0.0006 0.00001 f1R c 1.20 May 0.00037 0.016 57.7 0.0045 0.00013 1.05 Jun 0.000001 0.00002 0.0001 0.00001 fir c 3.76 Jul 0.000001 0.00007 0.0003 c 0.00001 f1R 0.48 Aug 0.000002 0.00003 c 0.0005 0.00001 f1R 0.33 Sep 0.000001 0.00005 0.0004 0.00001 f;R c 0.51 Oct 0.000001 0.00003 0.0009 0.00001 fir c 0.68 0.00016 0.026 b b b
?!ov 7.4 flA !!A g Oec. 0.000001 b c b 0.00004 0.0005 !!A NR 7;g e
1978 0.00167 0.193 774.1 0.0094 0.00027 e 1,19 d MPC (8) = 3.0 (10 7) pCi/ml when Sr90 analyses are not available MPC (8) = 1.0 (10'S) pCi/ml when Sr90 analyses are included separately
~
MPC (a) = 5.0 (10 6) pCi/ml b riot yet available c riot required; there were no Lagoon 3 effluent releases for the month d MPC through October 1978 e Release through October 1978
e Table 2 / i PARTICULATEGASEOUSEFFLUET)TS Month Curies % Monthly Limit January .0001 0.04 February .0001 0.04 March .0001 0.03 April .00004 0.02 May .00005 0.02 June .00009 0.03 July .00006 0.02 August .00006 0.03 September .00024 0.08 October .00035 0.15 t'ovember .00018 0.08 December .00013 0.04 1978 .00149 0.047
. i
, , Table 3 SURVEILLAtlCE TESTS I
Spec. # Subject Completed This Quarter Comments
\
6.1 Raschig Ring Tanks C Tanks are to be scheduled prior to next processing use 6.2 Sump Alarms and Eductors XC-2 10-8, ' '-29, 11-19, 12-19 Satis factory XC-3 10-8, 1 '9, 11-19, 12-19 Satisfactory PPC 10-8, IL-29, 11-19, 12-19 Satis factory 6.3 Uaste Storage Tank Pan Ins trumentation 8D-1, 8D-2 10-17, 11-7, 11-28*, 12-21 Satisfactory 8D-3, 8D-4 10-17, 11-7, 11-28, 12-21 Satisfactory 6.4 Emergency Utility Equipr..ent 30T-1 10-19 Satisfactory 31K-1 10-19 Satis factory 32G-4B 10-19 Satisfactory 31G-2, 2A 10-12, 12-12 Satisfactory 31K-2, 2A 10-12, 12-12 Sa tisfactory 32G-2A, 2B 10-12, 12-12 Satisfactory Diesel Fuel 10-2, 10-9, 10-16, 10-23, 10-30 11-6, 11-13, 11-20, 11-28, 12-4, 12-11, 12-18, 12-26 Satisfactory Propane Fuel 10-2, 10-9, 10-16, 10-24, 10-31, 11-6, 11-13, 11-20, 11,27, 12-4, 12-11, 12-18, 12-25 Sa tis factory 15K-10A 10-19 Satisfactory 15F-21 10-19 Catisfactory 6.5 Filters 10-3, 10-9, 10-18, 10-26, 11-8, 11-14, 11-22, 11-27, 12-14, 12-22, 12-26 Satisfactory 6.6 Dilution Air f;ot required this period 6.7 Boric Acid l'ot required this period 6.8 Locking Out tiot required this period 6.9 Water Activity Alarms flot reovired this period 6.10 Poisoned Dissolver Baskets flot recuired this period 6.11 Solvent Analysis flot recuired this period
- See accompanying attachment for 8D-2 test.
Table 4 \ e FILTER REPLACE'iEilT flovember 10, 1978 - The Uaste Tank Farm off-gas filter 8T-1A was changed.
s f PROCESSING SU EARY During thi- riod there was no processing of fuel.
I I _NU_ CLEAR FUEL
SUMMARY
\
r The following information is based upon nuclear material accountability records and indicates the disposition of nuclear material in fuel at the reprocessing plant. A. IflVENTORY The total on-site inventory on December 31, 1978 was 166,759 kilograms of uranium and 1,045,629 grams of plutonium. An inventory description by source and material type is presented in Table 5. B. RECEIPTS AND SHIPMENTS During the quarter, there were no shipments or receipts of spent fuel assemblies at the West Valley site. C. MEASURED WASTE AND ADJUSTl1ENTS There was less than one kilogram of uranium and less than one gram of plutonium during the reporting period as measured waste. An adjustment of less than one kilogram of uranium and less than one gram of plutonium to NFS Lot 27A was required.
Table 5 I NUCLEAR FUEL STATUS AS OF DECEMBER :31,19_78,
)-
Kilocrams Grams Total U U-235 U-233 Total Pu I. INVENTORY (10/1/ /BT NFS 3,271 8.01 -- 306 Dresden-1 20,4!9 144.03 0.30 117,608 RG&E 46,136 722.48 -- 287,410 Consumers 11,130 238.68 -- 64,367 WEPC0 43,017 462.61 -- 340,730 Jersey Central 42,756 463.43 -- 235,208 TOTAL 166,759 2,039.24 0.30 1,045,629 II. 9ECEIPTS (10/1/78-12/31/78) No receipts during this period. III. . REMOVALS T10/1/78-12/31/78) A. Measured Waste Lot 27A <1 <.01 0 <1 B. Adjustments Lot 27A (<1) (<.01) 0 (<1) TOTAL 0 0 0 0 IV. INVENTORY T12/31/Tli) NFS 3,271 8.01 -- 306 Dresden-1 20,429 144.03 0.30 117,603 RG&E 46,156 722.48 -- 287,410 Consumers 11,130 238.68 -- 64,367 WEPCO 43,017 462.61 -- 340,730 Jersey Central 42,756 463.43 -- 235,208 TOTAL 166,759 2,039.24 0.30 1,045,629
I . i
\
r RADI0 ACTIVE WASTE A. Solid Waste The radioactive plant waste buried during this quarter consisted of 789.78 cu. f t. containing 23.111 curies. The material was buried as high level waste. B. liigh Level Liquid Waste As of December 29, 1978, the high level storage tank 8D-2 contained 583,100 gallons of neutralized waste with an activity of 4,278 pCi Cs-137/ml and 111 pCi Cs-134/ml.
FACILITY PERFORMANCE AND MODIFICATI0tlS This section describes:
- 1. Major modifications that were either initiated or completed at the processing plant during the reporting period.
There were no modifications initiated or completed during this reporting period except as noted in the accompanying attachment.
- 2. A description of malfunctions of any equipment listed in Appendices 5.2, 9.51, 9.53 and 9.56 of the Final Safety Analysis Report which are important to safety.
NFS initiated a testing program of the 8D-2 waste tank pan instrumentation as stated in NFS' letter of October 12, 1978 to Mr. Richard Starostecki, USilRC. During the tests it was found that the pan level instrument 8LI-5 did not function as required. A report of these tests is attached.
t 9 ATTACHitENT TO FIFTY-FIRST , QUARTERLY REPORT - October 1,1978 - l December 31, 1978 \ 8D-2 PAN TESTS Introduction On November 15, 1978, a test was initiated to verify the level instrument response in 8D-2 pan by adding water to the pan, as stated in NFS' letter of October 12, 1978 to R. W. Starostecki, USNRr., It was intended that this test would provide verification of instrument response to an actual water addition to the pan. Such a test is not part of the routine surveillance of the high level waste tank containment systems. Routine instrument checks for Technical S,oecification compliance involve applying an air signal to the pneumatic transmitters and calibration and testing of the system. Summary It ha'd been originally estimated that the 8D-2 pan level instrument (8LI-5) would indicate a reading at a volume addition of as low as 500 gallons. After 3000 gallons had been added, a temporary instrument probe was installed in the pan as a backup to 8LI-5 which was reading zero. Subsequently, it was ascertained from drawings of the tank complex that engineered ports in the perlite retaining skirt would allow water to enter the area of perlite blocks under the tank 8D-2 so that estimates of volume required to produce a level of two or three inches in the pan were revised upward to about 15,000 gallons. Water was then added in 200 to 500-gallon increments over fifteen days, and readings were obtained on the temporary instrument, but those levels dropped to zero in a short time due to the wick effect of the warm perlite block absorbing water from the pan annulus. 8LI-5 showed no readings throughout the tests.
8D-2 Pan Tests I c
\
On November 30, af ter 26,500 gallons had been added to the pan, a reading was observed in the 8D-2 vault level. Subsequent water additions to the pan produced simultaneous level increases in both the pan and va ul t. When the vault water was educted into the pan (two occasions), the flow was reversed when the eductor was stopped. The pan water was then pumped to the lagoon and a simultaneous drop in the vault level was observed. The pen pump was examined and is in good condition. The sample of water from the pan showed only background radioactivity. An additional level probe was installed in the pan adjacent to the pan pump, and copper tubing was inserted into the vault level probe and extended to the bottom of the vault. The water addition test was repeated and these instruments confirmed that water addition to the pan produced increases in the vault level. The vault eductor and level probe assembly was removed, examined and reinstalled. It was determined that the eductor suction pipe and the original level instrument line were both 12 inches shorter than shown on construction prints, but this examination also eliminated the possibility that a syphon existed between the vault and the pan. At this point it was apparent that a connection existed between the pan and vault, and USNRC Region I and Licensing were notified of this condition. Determinations from the tests are summarized below.
- 1. The original 8LI-5 instrument for 80-2 pan was inoperative with a malfunction between the transmitter and the pan (5 to 10 feet underground).
- 2. There is a connection between the pan and vault at an undetermined location, but somewhere between 0 and 3 inches from the pan bottom.
- 3. The vault couctor assembly (jet suction and instrument probe) is installed 12 inches higher than indicated on the drawings.
- 4. The 8D-2 pan pump was operated and shown tu function well.
8D-2 Pan Tests i j . t
- 5. The background radioactivity level of 8D-2 pan water demonstrates the containment integrity of tank 8D-2.
- 6. The 8D-1 pan and vault systems were tested with water and do not have a connection as was discovered in 80-2 pan and vault.
Upgraded instrumentation was instr lled in 8D-2 pan and vault. The level instrument for 8D-2 pan (3LR-5) consists of the stainless probe (adjacent to the pan pump) which is connected to a Taylor transmitter and level recorder. The level instrument probe for 8D-2 vault (8LR-15) is a copper tube extended to the bottom of the vault (inside old 8LI-15 tube) and is connected to a Taylor transmitter anJ level recorder. Both of these new instruments are wired to the alarm annunciating panel board in the Waste Tar k Farm shelter. In view of the detcrminations made during the 8D-2 pan tests, NFS has decided to pursue several courses of action to further evaluate the pan and related equipment and to assure the sensitivity and reliability of pan monitoring instrumentation. Such steps include: (a)anentry into the 8D-1 vault to examine the vault, pan and pan retaining skirt, (b) an investigation of the feasibility of remote viewing equipment types and applications for examining the 8D-2 pan and skirt, and (c) the extension of vault level probe and eductor suction line by 12 inches. Additionally, NFS' records have been reviewed to determine the extent and type of testing conducted as part of either acceptance or licensing reviews by NFS, New York State and the Atomic Energy Commission. These records indicate that no liquid tests similar to those recently completed were required or conducted as part of these reviews.
80-2 Pan Tests l (
).
Chronology of Tests and Results 8D-2 pan tests were initiated on flovember 15, 1978. Water was added to the pan through a Badger water meter into the sample tube to the pan. This sample tube is a 2-inch pipe which has two offsets and extends downward to 2 inches above the pan floor. Water additions were made initially in 200-gallon increments, then in 400-gallon increments until 3000 gallcns had been added to the pan. It was anticipated that a level reading would be indicated on 8LI-5 with this quantity of water, but 8LI-5 had a zero reading. A temporary probe was installed down the 2-inch sample tube as a backup instrument. Af ter the 3000-gallon water addition, this temporary probe, connected to a manometer, indicated a 4.1-inch level in the pan. One hour later (1500) the manometer indicated 2.0 inches. On flovember 16, the Badger water metar function was checked by filling a 55-gallo, drum with satisfactory results. After another 400-gallon addition, the temporary probe showed a water level of 2.8 inches in the pan. Another 400 gallons were added to the pan and the temporary manometer then indicated 3.05 inches. flo positive indication was shown on 8LI-5 throughout these tests. It was recognized that sample bottles may have been lost over previous years of attempted sampling through the 2-inch tube in 8D-2 pan, and while it appeared that the temporary probe inserted in this tube was at the bottom of the pan, there was a clear possibility of a sample bottle obstruction at the bottom of the tube. At this point the entire 2-inch sample tube was capped and used as an instrument line. A zero reading was obtained on the manometer. Water addition was started again at 1515. After addition of 700 gallons, a reading of 3.6 inches was shown on the reinstalled temporary probe. Fifteen hundred gallons of water were added on flovember 16 bringing the total to 4500 gallons.
. 8D-2 Pan Tests I . t (
)
On November 17, 1978 at 0835, the canometer on the sample tube probs read zero. Water was added to 8D-2 pan as follows: Total Temp Probe Time Gallons Manometer Od45 4500 0 0922 4900 3.46" 0934 5300 4.10" 1040 5300 2.20" 1045 5700 - 1100 5700 4.3" 1110 5700 3.35" 1124 6060 4.20" 1249 6060 1.85" Because of the indication of water drop over time in the pan and the potent:?1 that the temporary probe was obstructed with old sample bottles, a weight was lowered into the sample tube to clear any potential obstruction. The weight when retrieved appeared dry exceot for a bit of rust on the end. The temporary probe was then reinstalled and the manometer indicated 0.5 inches. The operator could hear water bubbling from the instrument purge. An attempt was made to use the water sparge line on the 8D-2 pan pump as an instrument dip tube, but a zero reading was obtained. Water additions were started again. At the end of November 17, 1978, 6860 gallons of water had been added and the temporary instrument showed 4.2 inches in the pan. 8D-P pan tests were continued on Monday, November 20, 1978. At this time it was recognized that a possible wick action might be occurring in the perlite blocks, and that an equilibrium level in the pan might not be reached until 20 to 30,000 gallons of water had been added.
8D-2 Pan Tests I ,
\
C On the morning of November 20, 1978, the temporary instrument in the sample tube showed a zero reading. Water addition to the pan was continued with results similar to those of November 17, 1978. Each 400-gallon increment would produce a level reading on the temporary instrument, but the level would drop quickly with time. By the end of the day, a total of 8860 gallons had been added and the instrument had dropped to zero. On November 21, 1978, water additions to the pan were continued. The temporary instrument showed readings as high as 5.2 inches. A total of 14,000 gallons had been added at this point. After 12 hours the manometer had dropped to zero. No water additions were made over the holiday weekend, and the manometer continued reading zero. On November 27, 1978, the temporary probe was pulled and leak-checked, then water additions were continued. From this point on, the temporary probe manometer never dropped to zero. Water additions produced level increases on the instrument, although the levels dropped between increments. At the end of November 27, 1978, a total of 17,500 gallons had been added and the manometer read 3.8 inches. Water additions were continued on November 28, 1978. The initial manometer reading was 3.2 inches; it had dropped 0.6 inches overnight. At the end of November 28, 1978, 23,500 gallons had been added to the pan and the level reading was 12.2 inches. This level dropped one inch in the next 14 hours with no water addition. On No, ember 29, 1978, water addition brought the total to 25,000 gallons with a level of 14.0 inches. This level remained stable for five hours with no further water additions. In the afternoon of November 29, 1978, 1500 gallons were added to the pan, producing a level of 16.9 inches. To this point no level indications had been observed on LI-15, the 8D-2 vault level instrument. This instrument is read each shift; it is an Ashcroft Duragauge, a direct-reading bellows-type gauge, with a 0 to 30-inch water range.
~ 8D-2 Pan Tes ts / , e On November 30, 1978 at 0100, the operator observed a reading of 6.8 inches on the vault instrument. This level remained stable throughout the night, and the LI-15 instrument was examined at 0835 by an instrument technician and verified to be functioning properly. Water was then added to the pan to test instrument response. Water Added Pan Vaul t Time (Gal.) Level Level 0957 0 16.7" 6.8" 1100 0 16.7" 6.8" 1108 100 16.9" 6.9" 1113 100 17.0" 7.1" 1126 100 17.1" 7.38" 1145 0 17.2" 7.45" 1300 0 17.4" 7.45" It was decided to jet (educt) the vault water into the pan in order to determine if the vault readings were anomalous. The following data were obtained: Time Pan Level (in.) Vault Level (in.) 1300 17.4 7.45 1303 Jet Started 17.4 7.00 1305 17.4 6.55 1306 1/.5 6.30 1307 17.7 6.00 1308 17.8 5.80 1309 17.8 5.60 1310 17.8 5.40 1315 17.8 4.70 1316 17.8 4.70 1317 17.8 4.58 1320 17.8 4.30
8D-2 Pan Tests I ~
~
r (Cont'd) Time Pan Level (in.) Vault Level (in.) 1325 17.8 3.90 1330 17.9 3.68 1335 18.0 3.5 1340 18.0 3.35 1345 18.0 3.22 1350 18.0 3.17 1355 18.0 3.10 1400 ~8.0
- 3.10 1405 Stopped Jet 18.0 3.10 After the jetting was stopped, the following data were obtained:
Time Pan Level (in.) Vault' Level (in.) 1410 17.8 4.5 1415 17.4 6.05 1420 17.3 6.90 1445 17.3 7.55 The pan was then sampled, a result of 2 x 10-6 pCi/ml gross 8 was obtained, and the pan was pumped for two hours to 8D-2 tank (about 1500 gallons) and then valved to Lagoon 1 as pumping continued. The vault level decreased as the pan was pumped, and this relationship is shown in Figure 1. A zero level in the vault was observed when the pan level had been pumped down to about 10 inches. On December 1,1978, it was determined t actual measurement of pan dimensions would aid in the analysis of data being obtained, and that it would be valuable to install a welded 1/4-inch stainless steel dip tube at a measured depth along the pan pumo assembly for future level readings. The bottom of the pump assembly was reasured as 38'-6" from the flange. The new probe is installed 2-3/8" frcm the bottom of the pan.
. 8D-2 Pan Tests I ' 1
\
f. fio water additions were made on December 2 and 3. On December 4, 1978, it was decided to add water to the 8D-2 vault via the LI-15 instrument line to determine if a corresponding increase would be observed in the pan. Since the level of water in the vault was below the instrument line, no level was observed in the vault. The pan level increased from 2.45 inches to 5.20 inches during this test in which 1250 gallons were added. The possibility was recognized that the vault jet assembly may not have been fabricated as designed, and if the discharge leg of the jet extended to a low level in the pan, we could be observing a syphon action. On December 5,1978, the jet was purged for two minutes with instrument air pressure to clear any potential water from the lines. Another 500 gallons of water were added to the vault and the pan increased from 5.10 to 6.23 inches. fio level was observed in the vault. To test LI-5, the 8D-2 pan level probe which had not resnonded, 700 gallons of water were added via this probe and the pan level increased from 6.23 to 6.87 inches. LI-5 was ret nnected and read zero. A water addition was then started to the 8D-2 pan via the sample tube. At a pan level of 9.7 inches, the vault level reading was 0.1 inches. After adding 2100 gallons to the pan, the pan level was 11.39 inches and the vault level was 2.6 inches. Water was then added to the vault (300 gallons), and the pan level rose to 12.00 inches and the vault level to 3.36 inches. The vault was then jetted to the pan. The pan level rose from 12.01 to 12.23 inches, and the vault level dropped from 3.36 to 1.78 inches. After the jet was shut off, the vault rose to 3.20 inches and the pan dropped to 12.10 inches. On December 6,1978, copper tubing was inserted down the LI-15 probe into the vault. When the bottom of the vault was detected, a manometer was connected to the tubing and read 16.4 inches. Th u r, , the LI-15 probe appeared to be about 13 inches above the vault gravel.
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8D-2 Pan Tes ts l ' (C On December 7,1978, the 8D-2 vault eductor and level probe assembly was removed from the vault and measured. Measurements confirmed the assembly is 12 inch ; shorter than shown on construction prints. 8D-2 pan was sampled and the result was 6.6 x 10-7 pCi/ml s. (Alargersample was used for this analysis which gave greater accuracy.) On December 8,1978, 8D-2 pan contents were pumped to Lagoon 1. The data on pan and vault levels (instruments at bottom of vessels) during this pumpout are provided in Figure 2.
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80-1 PAN AND VAULT TESTS A test of 80-1 vault and pan instruments was initiated on December 6, 1978. The vault and pan contained some water prior to the tests. Prior to jetting the vault to the pan, a copper tube was inserted into 8LI-14, the vault level instrument line, since it was anticipated that this vault instrument could be 12 inches above the elevation indicated on drawings, as was 8D-2 vault. The 8D-1 pan level was read from a probe inserted .ato the pan sample tube to the bottom of the pan. Thus, indicated levels are irom the bottom of the vessels: Time Pan (in.) Vault (in.) 1754 6.84 16.60 1755 Jet Started 1911 Jet Off 9.19 12.45 1945 9.32 12.50 There was no apparent reversal of flow from the pan to the vault after the jet was stopped. On December 7,1978, water was added to 8D-1 vault via the vault instrument tube. The pan level remained at 8.7 inches during the addition of 3000 gallons to the vault. (This 8.7 inches differs from the 9.32 inches from the previous day because of an instrument adjustment.) The vault level increased from 12.50 inches to 58.40 inchas during the water addition. There was no level change in the pan during the water addition to the vault. This level was held for several hours, then the vault was jetted to the pan. The vault level decreased from 58.60 inches to 12.05 inches during jetting. The can increased from 8.84 inches to 17.10 inches during the jetting. These levels,16 hours later, had remained stable.
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