ML19351E087
| ML19351E087 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/20/1968 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E086 | List: |
| References | |
| NUDOCS 8011250585 | |
| Download: ML19351E087 (8) | |
Text
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%;'d YA!!KEE 1;UCLEAR PUlER STATIC:;
' kr v-OPERATIO l REPGRT I;0. 92 For the nonth of Augaa t 1968
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Sub.-dtted by YAI;KEE ATCHIC ELECTRIC CCFPANY Ecsten Macsachuse tta l
Septer.ber 20, 1968 RESU3IOR DJaif LECD)Y s o t i e n o E?r
1 Thic repar* covert the cperation of the Yankee Atcmic Electric Cavany pl.n* at hcae, ? 'a t : nc h u s e +. t 3 fcr the rentn of Auguat, 1968.
1 I
P;
.t lead inriei betwu n 175 ' Ode und 179.0 VJe as circulating 1
l wat er iniot temporat ur e fluctuated betv.en 589 and 530F.
On August 16 plar.t load was reduced t o,130 ICde and the I;o. h lcop was luclated to ef fer* ropuirc to a drain 1ine on the main coolsnt chur6 nc 1
lino An a re: ult of t h<
leak, "apor container atcasphere tritiurt concentra-l tior in^reuce 1 frca
'.S x 10-5' L : / c - to 5.3 x 10-b ue/ce.
A cteam feed to the n t a i r.me n t f ar *.rit ;um dilutic: w a :, initiated and after a seven day period a re luc t i cn o f + h-airtorna tritium v 21 to 0.h x 10-9 Lc/cc was realized.
l.
Tne tanthly c:ntrol r:d exere:,o was perfcr=ed during the period.
Contrni r ul Ib. 9 dii not appear t.o w cut the first attenpt but behaved na rrti ly I'cllowing in ert w t
und D wer~ cave.1 out one step to 83 1/8 Ccntrol rod groups 13, na purt t ht rod
- ep wear progra:; ccnt ral rod ia. 17 remairs in the
% VH : n 11:: st ea pn i t wn.
3:.s un a p:w nt ofcpv* iuel :cn+m nir,' nine Core VI assemblies van nude
. lugus+ 31.
In:
fu e l t hi rna nt wa:. the twenty third in the series, t rin61ng t he number f eitN n'a chipped in + he t en element cack to 217 and the t at.al numt er af +1
-nta sh;pped to date to
'D.
Fr:'
to the chipment an IAEA inspector remcVed the seals frcm the s p~ n
- ruel p_*
lua1.r.g hatch; 'Le batch was reacaled alter the fuel cack van r :ma 1
+r~m *Pr pit.
'i?w t eala Wr" plu; ?d : t h._
n r t ar head mincile shield by the I/.iA 1 r m: ? :
isen*
el reciu c
- 1 c ra dur;.ng the perica were as follows:
A w u:t Ia
...s;.
M j:
L u ri
.iactiun to 55 Tie; I;o. < feedvater heater c
icolat ed to repu r vent line leak.
A u g r. t 11 14;-1;10):
1ind reduett;n to i f, !Cde ; routine test of turbine throttle talvec.
f Augur
- I-. 1100-1400):
Load redrtion tc 13; VJe; I;o. L loop isolated to cap a leaking drain 1;ne en the charging line. The inboard gland on th" No.. boiler feed pump was packed.
Augu
- 17 (1030-11h21:
Loa:1 reduction to ib ! Ode due to elect-ical storm in a re.
Augua* 20 tl?h9-1910):
Ecud redu: tion to ILO f0de due tc electrical storm in area.
'i ' plant c hu t <lc un : or reactor scrams occurred during the month of Auguat,.96 rlan-Mi
~t. mn:e l
l Tho follcwing la a list of pertinent maintenance items perfcrmed y the plant staff during the contn of August, 1968.
O o
1.
Three new plungers and packing sere installed on the No. 1 charging pump.
l The No. 1 toiler feed pump inboard gland packing was replaced.
3.
Two inlet and one outlet valve were replaced in each of the vaste gas compressors; a new set of diaphragms was installed in the No.1 compresecr.
h.
Installation of a pneumatically operated valve in the generator hydrogen vent line was completed.
5.
The yard area crane and crane cable were inspected and lubricated.
6.
Oil cooler cooling water regulators for the No. 1 and No. 3 charging pump fluid drives were installed.
Instrumentation and Control
)
The follex;'.g is a list of pertinent instrumentation and control maintenance performed by the plant staff during the month of August, 1968.
1.
A water tight container was fabricated for the spent Puel monitoring neutron detector.
2.
Work was performed to develop a new scheme for the control rod position indicating coil light, l'Workcontinuedonthe incore flux wire modification program.
eactor Plant Performance Normal core reactivity depletion of 0.755 LK/K per 1000 MWD /MTU and O. Lb7 ppm baron per ;"dD/MTU was experienced during the period.
The end of core full power life, unadjusted pH is estimated to be " arch 1, 1969; average burnup will be approximately 8876 Mh~D/MTU.
T'.e following parameters were determined by means of incore instrumentation:
Zircaloy assembly 598.0 MWt, 526.20F Tavg, Control red group A @ 76 7/8; B,C, D @ 88 1/8, 811 ppm baron.
F 1.9
=
1.8 aH
=
Minimum DNEF 3.50
=
i l
0 582.5 F l
Maximun outlet temperature
=
Secondsrv Plant Pe r formanc o The condenser performance was as follcvs:
T.T.D.
35.6 F Clean 1necs factor 55.7
=
l l
O O
Feedwater heater terminal differences were as follcus:
.e n
No. 1:
ll.4"F; No. 2:
10.8 F; no. 3:
5.0 F Chemistry The main coolant boron concentration decreased from 922 ppm to 78h ppm during the period to compenaate for normal core burnup. Main coolant pH averaged 5.20.
d.o, x 10-', Average coolant gross beta-gamma activity and crud level were pc/nl and 0.06 ppm, respectively.
The main coolant tritium specific activity averaged h.86 c/ml during the month.
Iodine - 131 specific activity was 2.5 x 10-5 pc/ml and the iodine 131/133 atomic ratio vac 0.81, indicating.
the absence cf any detectable fuel defects.
A representative crud sample for the month, collected on August 23, had the following radicchemical analysea:
dpm/mg crud Cr-51 Mn-5h Fe-59 5
1.69 x 10 9.72 x 10' 8.85 x 10 Co-56 Cc-60 Ag-110M 6
6 5
3 89 x 10 1.63 x 10 1.80 x 10 A main coolant gas sample collected on August 19 had the following radicchemical nalyses:
tc/cc gac Xe-133 Xe-135 Ar bl
~>
o
-l
- 1. 5 8 x 10 --
1.66 x 10-'
2.12 x 10 8Hva19 and l'afety j
Was*e disposal 11 quid releases totaling 31,398 gallons contained i
O.01 mc of grecs beta-gamma activity and 125.5 curies of tritium.
Gaseous rele.aea during this pericd were 93.9 me of gross beta-gamma activity.
Secondary plant water bacharged vaa 235, 705 gallons and contained a total of 0.005 me of gross beta-gamma act;vlty and 0.93 curies of tritium.
One shipment of spent fuel containing a total activity of 17.2 megacuries was made during the period.
Average acenculated exposure dose h8 mrem.
I Maximum accumulated exposure dose 121 trem.
i i
The ccmputed activl y release numbers reported for July, 1968 are in error.
A corrected page 3 is attached for insertion in Operation Report No. 91.
i
'll
YANKEE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
AUGUST 1968 ELECTRICAL MONTH YEAR TO DATE Gross Generation KWH 131,568,200 797,530,800 8,508,415,h00 Sta. Service (While Gen. Incl. Losses)
KWH 8,182,620 51,6h0,283 564,307,216 Net Output KWH 123,385,580 Th5,890,51T 7,9hh,108,18h Station Service 6.22 6.h8 6.63 Sta. Service (While Not Cen. Incl. Losses) KWH 0
1,171,231 25,976,758 Ave. Gen. For Month KW 176.839 Ave. Gen. Running KW 176.839 g
PLWT PERFORMANCE Net Plant Efficiency 27.79 27.96 28.35 Net Plant Heat Rate btu /KWH 12,280 12,206 12,038 Plant Operating Factor 99.hh 75.9h 73.76 Reactor Plant Availability 100.00 84.25 83.46 i
i NUCLEAR MONTH CORE VII TOTAL Hours Critical HRS 74h.00 2961.31 58,068.T3 Times Scrammed 0
0 55 Burnup Core Average MWD /MTU Region Average fGD/MTU 895.21 3471.62 A (INNER) 891 569 3525.8h3 21,380.11 B (MIDDLE) 10h2.h8h 4083.437 1h,070.86 i
C (OUTER) 728.387 2767.h57 2767.h6 i
D (ZIRCALOY) 911.543 3561.708 3561.71 i
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0 l2 i
SYA D
l D
AD 8
I 6
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9 E
1 G
l5 A
r T 1
o S L
H f U i
V G
A UA Y
i LIAD i
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M O
0 0
0 0
0 5
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2 1
1 M g$ g M1< t4a 1
f.
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-s.
s.s YANKEE
- ROWE C ORE 3DE 3
A B
C D
E yF G
H J
K XXXX 2
3 NXX XX/
X X
3 XX XX 4
sL X MR x 4 84 X
MM X
~
XX XX 7
X X
o
/XX XXN f
4 XXXX 3
REGION A
a j
-ze Es o
=
Fontomg.e
O O
(
s Reactor Plant Performance Normal core reactivity depletion of approximately 0.152 ppm boron per MWD /MTU was experienced during the period.
l The followiL2 parameters were determined by means of incore instrumentation.
598.8 MW, 525 F.
T Ocntrol rod group A @ 90, B, 1,
- AVG, 0
C, e @ 87, 971 ppm bcrcn 1.8 F
=
q 1.6 F
=
AH Minimum DNER 3 50
=
581.6 Maximum outlet temperature
=
l Secondary Plant Performance I
The condenser performance was as follows:
3h.6 T.T.D.
=
55.8 Cleanliness facter
=
Feedwater heater terminal differences at 178.5 MWe and 2.65
" HG backpressure were:
?io. 1:
11.3 F; Uo. 2:
10.9 F; No. 3:
5.2 F Health and 'Jafety Weste disposal liquid releases totaling 27,960 gallons contained 0.026 me of gross beta-gamma activity and 65.6 curies of tritium. Gaseous releases during this pericd were 27.5 me of gross beta-ga:ma activity.
Secondary plant water discharged was 280,595 gallons and centained a total of 0.006 te of gross beta-gamma activity and 0.87 curies of tritium.
An additional 0.05 curies of tritium vapor was purged from the vapor container to the primary vent stack during the period.
Average accumulated exposure dose:
67 mrem Maximum accumulated exposure dose:
215 mrem
.l NOTE:
Thio page supercedes page 3 of the July Operation Report No. 91.
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