ML19351E236
| ML19351E236 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/22/1972 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011260315 | |
| Download: ML19351E236 (8) | |
Text
__
l
,.=y
_gg Regtlatory File Cy,
%/
l O
m.==sr
.i YANKEE NUCLEAR POWER STATION 4
OPERATION REPORT NO. 136
)
For the Month of
- @[
5 pf([l'j'l/p f' i, April 1972
'4 lfhp?f2)
(( ~ ' [h i
i
'/j,"T[\\g g
,/ '
U-s% %"
1 I
IM
/
I rs1 s.%.
19?2.
l
~
3!
gh Af;.7,:}y c>l 4
i Submitted by YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts May 22, 1972 o
R ib
I t
i i
l This report covers the operation of the Yankee Atomic' Electric Company at Rove, Massachusetts for the month of April,1972.
l The plant continued its Core IX-X refueling and maintenance j
j cutage throughout the report period. All core components were in place I
and the reactor head was reinstalled on April 29, following return of the shield tank cavity borated water to the safety injection tank. At the end of the period decontaminatica of the shield tank cavity was in l
progress preparatory to installation of the reactor head closure studs, f
Repairs to the turbine generator stator coils, performed con-1 l
currently with the refueling and maintenance outage, were completed on i
t April 15.
Reassembly, alignment and coupling of the rotor to the turbine shaft occupied the balance of the period.
t l
Plant Abnormal Occurrences t
l There were'no plant abnormal occurrences during the report period.
I Plant Shutdowns l
l Shutdown No. 120-9-72:
February 12, 1972 continuing through the report l
period. A plant shutdown foi turbine generator repairs; and for ccacurrent refueling and main-tenance.
O Core IX-X Major Work Items 1
Work was continued on the master list of major work items to be completed during the current shutdown period. The following major work items were completed.
1.
A nes air baffle was installed on the reactor head, f
2.
An operational test of the primary protective relays was successfully performed.
3.
The North and South turning vanes in the low pressure steam lines were replaced.
4 L.
A capacity test of each of the two, vapor container recirculation system pumps was performed.
5 A capacity test was perfoemed on each of the three station batteries.
Design Changes l
l 1.
Core X l
Core X was loaded in the same regional pattern used in the previous cores. Thirty six new 4.0% enriched Zirealoy clad fuel assemblies were G
located in the peripheral region. Thirty six stainless steel clad fuel assemblies, originally-h.9h% enriched and which were cycled in Core IX, were located in the intermediate region.
Four stainless steel clad fuel assemblies, also originally h.9h% enriched and which were cycled in Ceres VIII and IX, were located in the center region.
i nn,.__
i
~
2.
Reactor Protective System Modifications rs
[
')
A.
A reactor trip system which is derived from a reactor coolant pump
\\_/
over or under current condition was installed. A coincidence of two of four reactor coolant pumps with either an over-current or under-current condition vill initiate a reactor trip.
B.
A new steam generator low level reactor trip system was installed.
A coincidence of two of four stcsm generators with a low level condition vill-initiate a reactor trip.
C.
The emergency core cooling system was modified to include the following:
(1) Three pumping trains each comprised of one low pressure safety injection pump and one high pressure safety injection pump.
(2) An ac tumulator filled with approximately 800 cubic feet of pressurized borated water.
(3) A high pressure gas storage system containing nitrogen gas to pressurize the accumulator.
(h) The piping, valves and instrumentation associated with the above listed components.
Preoperational testing of the modified emergency core cooling system
,- s
(
)
was completed April 17.
%d Plant Maintenance The following is a liet of pertinent plant maintenance items performed, additional to the major work items, during the month of April, 1972.
1.
The safety injection tank outlet valve CS-V-60h was refurbished.
2.
The safety valves for the No. 2 and No. 3 feed water heaters were re-paired, tested, and reinstalled.
3.
The diaphragms in the No. 2 waste gas compressor were replaced.
h.
Both heater drains tank pumps were repacked.
5 The No. 3 condensate pump was repacked.
Instrumentation and Control The following is a list of pertinent instrumentation and control maintenance items performed by the plant staff during the month of April, 1972.
1.
Calibration was performed of the following instrumentation:
(A) a.
Main coolant temperature channels.
' ~ ~ '
b.
Feedwater control system pneumatic relays.
I I
j
'l 1
l c.
Vapor container relative humidity and dev point measuring
- systems, d.
Level controls for the feedwater heaters; heater drains tank; l
condenser hot well; and moisture separators, i
l l
2.
A new, vapor container penetration was installed at blister location 6E.
l Chemistry The main coolat t baron concentrations and pH averaged 2595 ppm l
and h.68, respectively c. ring the report period.
l The main coolant beta-gamma specific activity and crud level averaged 4.25 x 10-2 ue/ml and 0.06 ppm, respectively.
The main coolant tritium concentration averaged 1.87 x 10-2 uc/ml during the period.
1 The iodine-131 specific activity decressed to 1.17 x 10-7 v./ml during the period.
A crud sample for the month collected on April 25, had the follow-ing radiochemical analyses : dpm/cg crud cr-51 M"-Sh Fe-59 co-58 6
6 5
6 1.78 x 10 1.55 x 10 h.h2 x 10 3.80 x 10 i
Sb-124 Co-60 Ag-110M Z#~95 6 5
6 5
2.h3 x 10 3 71 x 10 1.76 x 10 1.21 x 10 IIealth and Safety i
}
Four shipments of low level radioactive vaste were made during the period consisting of 223 drums, and 43.2 ft3 of miscellaneous vaste with
)
a total activity of 41h.7 me.
Waste disposal liquid releases totalled 77,102 gallons containing
.016 me of gross beta-gamma activity and 15.78 curies of tritium. Secondary plant water discharged totalled 20,360 gallons containing 0.005 me of cross beta-gamma activity and 0.18 curies of tritium.
L In adt 'lon to the above releases 1.012 curies of tritium as a vapor were purgen from the vapor container through the primary vent stack, i
i Radiation exposure doses for Yankee personnel; NEPS"o personnel; l
and Outside Contractor personnel as measured by film badge for the month of April,1972 vere.
l l
Yankee Plant Personnel:
Average accumulated exposure dose: 166 mrem Maximum accumulated exposure dose: 940 mrem i
r l
l
. _ -- - -_ _..-, -. ~.. --...,. _,~.-. -- - - _ _.- c -,,.- -,n -.- --,,_,- -..--
l l
i
-h-l 1
i N.E.P.S.Co. Personnel:
Average accumulated exposure done: 206 mrem Maximum accumulated exposure dose: 690 mrem Outside Contractor Personnel:
l l
Average accumulated exposure dose: 349 mrem l
Maximum accumulated exposure dose: 22h0 mrem j-Ouerations Attached is a summary of plant operating statistics and a plot j
j of daily average load for the month of April, 1972.
I The following Emergracy Instructions were revised and reissued during the month of April:
)
505B8 Partial Loss of Main Coolant Flow 505B11 Large or Partial Loss of Main Coolant i
!!G t
f I
?
8 o
4 i
a ilO i
i
(
. ~
h
. h)
...y.
i I
. YANKEE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
lY
'~ '
APRIL 1972 ELECTRICAL MONTH
. YEAR'
.TO DATE-
[
. Gross Generation KWH
'0'
'1h7,688,100 13,163,56h,000 _
Sta. Service"-(While~ Gen.' Incl. Losses)
INH 0
'10,086,184
.851,155,798 *'
- Net Output KWH 0
137,601,9161
'12,312,408,202-Station Service 0
6.83
_6.47-Sta. Service (While Not Gen. Incl. Losses) KWH 503,776~
.2,339,261 35,443,653.
Ave. Gen. For Month.(719)
KW 0
Ave. Gen. Running (0)
KW 0
-PLANT PERFORMANCE--
Net Plant Efficiency 0
'27 92
.28.h5 Net Plant Heat Rate btu /KWH 0
12,232 11,974_'
. Reactor Plant-Availability O
h0.28
~ 75.52 "-
Plant Capacity Factor 0
28.29 84.00' 18-NUCLEAR-MONTH CORE IX,
TOTAL
]
i Hours Critical HRS 0.
10,520.59._
85,484.99
-l Times Scra: cued 0
5 66.
Burnup Core Average MTD/MTU 0
11,9h6.29 9
Region Average IND/MTU A (INNER) 0 11,757.8h 28.961.51-'
B (MIDDLE) 0
'13,940.87 22,682.72 C (OUTER) 0 9,974.66 9,974.66:
'D (ZIRCALOY)-
C
!lIJI1.
I
,l,I?!ljil il}
!Ii!!t; Ih l
.I-h-
03 5
2 Y
NA P
0 M
2 O
N C
D W
A O
C O
D I
L TU E
2 H
G 7
S' A
0 S
R R
1 G
Y E
O N
A V
F L
I D
C A
I L
I R
E M
Y P
U 5
O L
A F
1 E
T I
A A
R D
X F
X x
I hA E
Y P
OC 01 5
~
9
~
~
~ -
0 0
5 0
5 2
1
.g o@m O'S SobN bQa ns i o t
I; ll l
['
-1 JUEL ASSEMBLY LAY-00T
~
C CORE X 3
A B
C D
E F
G H
J K
y XXXX 2 NXX XX/ 3 XX XX 3
XX XX 4
oL X
M XA s
^ X E3 X
~
XX XX 7
XX XX o
/X X XX'N o
XXXX J"=-
=
E24 w
^
a S A I ESS X ZlRCALOY.
c ams
.