ML19351E237
| ML19351E237 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/28/1972 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011260319 | |
| Download: ML19351E237 (10) | |
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YANKEE NUCLEAR POWER STATION i
OPERATION REPORT NO. 135 l
i For."the Month of j
March 1972 S
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Submitted by i
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YANKEE ATOMIC ELECTRIC COMPANY
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i Westboro Massachusetts i
April 28, 1972 I
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This report covers the: operation of the Yankee Atomic Electric
. Companyf at. Rowe, Massachusetts.for the month of March,1972.
The plant' continued its Core-IX-X' refueling and maintenance
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outage'throughout the report period..The reactor head was removed on d
March 1 and the-shield tank' cavity was' filled to refueling level on 3
March h.
The refuelir g procedure was effected March 7, e.ad the transfer Lof fuel was completed March 10.
Thirty six spent fuel' assemblies were removed from the core and 36 new zircaloy clad fuel assemblies were inserted into the cora. The <1 rive shaf ts and' attached dash pots for control rods No.'s-1, 2, 11,'16, 18 and 21 were replaced with' refurbished drive assemblies.
Plant Abnormal Occurrences There were no plant abnormal occurrences during the report period.
4 Plant Shutdowns-
' Shutdown No. 120-9-72:
February 12, 1972. continuing through the report period. A plant shutdown for turbine generator ~
- repairs; and for' concurrent refueling and mainte-nance.
Core IX-X Major Work Items-
. 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.
The two pressurizer - safety valves were removed, lapped', tested, and reinstalled.
2.
The top bearing on the No. 1 main coolant pump was replaced.
- 3..The shaft.vas. repaired and the top bearing was replaced on the No. 3
- condensate pump, b.
A chemical cleaning was performed of the following segments of the service water system:
a.
Both No. 1 and'No. 2 component cooling heat exchangers.
b.
A11~four, vapor container cooling fan heat exchangers with associated supply and return piping.
c.
The supply'and return piping in the primary auxiliary building-
. cubicle area.
d.
The steam generator sample cooler together with its supply and return piping.
-5 Two of the three heat exchangers for the vapor container No.1 cooling fan were replaced.~
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The safety injection tank outlet valve CS-V-604, was refurbished, w/
7 The 20 gpm orifice in the main coolant bleed line was replaced.
Primary Plant Inspections The following is a list of major inspections performed during the report period.
1.
An inservice inspection of the reactor coolant systems was performed
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by an uutside contractor during the outage. Systems included in the inspection and the type (s) of inspection performed are presented in the table below.
Component or Inspection System Inspected Area Inspected Type Inspection Coverage Reactor Vessel and Closure head Versel Flange Weld Volumetric 75%
Flange Ligaments Between Threaded I
Stud Holes Volumetric 75%
2 lHeadCladding Visual and Surface Three - 36 in patches j
Closure Studs, a
! Nuts and Washers Volumetric 100%
(
)
Piping Pressure 20" !!ain Coolant Boundary Circumferential Welds Visual; Volumetric Six Locations 24" Main Coolant Circunferential Welds Visual; Volumetric Nine Locations 6" Shutdown Cooling i
Circumferential Welds I Visual; Volumetric Two Locations 5" Loop Bypass Circumferential Welds Visual; Volumetric 12 Locations 2" Charging Line Circumferential Welds Visual; Surface 16 Locations 2" Bleed Line Circumferential Welds Visual; Surface 23 Locations 20" Steam Jenerator Nozzle Safe Ends Visual; Surface Two Locations 24" Steam Generator Nozzle Safe Ends Visual; Surface Two Locations The inservice inspection was performed as designated in Section Xi of the ASME Boiler and Pressure Vessel Code, entitled " Inservice Inspection of Nuclear Reactor Coolant Systems" p
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Visual inspections were performed by p ant personnel of the below l
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listed components and/or systems.
' w./Y Component or System Inspected Area Inspected
. Inspection Coverage Pressure Retaining Incore Instrumentation Reactor Bolting Head Penetration Seals 100%
Main Coolant Loop: Th Valves 100%
Tc Valves 100%
Check Valves 100%
Bypass Valves 100%
Fill Valves 100%
Main Coolant Pumps 100%
-Steam Generator: Primary Side Manways Inlet 100%
Secondary Side Manways No. 2 and h 100%
Main Coolent Loop Safety Injection Valves 100%
Shutdown Cooling 6" MOV's 100%
Pressurizer: Safety Valves 100%
Manway 100%
Spray Penetration 100%
Main Coolant Bleed Line Valves:
CH-61h 100%
CH-MOV-525 100%
CH-MOV-526 100%
CH-MOV-527 100%
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CH-MOV-528 100%
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Main Coolant Bleed Line Orifices:
20 gpm 100%
75 spm 100%
Variable 0-70 gpm 100%
Main Coolant & Charging Line Valves:
CH-611 100%
CH-611A 100%
CH-MOV-52h 100%
Hangers Inside Main Coolant Th, Tc, & Bypass Piping 100%
Vapor Container Main Coolant Pumps 100%
Shutdown Cooling Piping - Loop No. 4:
Between Th & SC-MOV-552 100%
Tc & SC-MOV-551 100%
Main Coolant Bleed Line Piping:
Between CH-61h & CH-MOV-527 100%
Main Coolant Charging Line Piping:
Between CH-611 & CH-MOV-52h 100%
3.
A total of five fuel assemblies were inspected. No mechanical abnormalities were noted. Core X will be the second cycle for three, and the third cycle for one of the assemblies.
One assembly was removed from the core as spent fuel after three core cycles.
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Five control rods were inspected, and exhibited only minor wear in the (s) vicinity of the guide blocks.
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5 Two shim rods were inspected. No significant wear was detected.
6.
The North source vane was inspected and found to be in good condition.
7.
The reactor vessel thermal shield seam clamps and secondary core supports were inspected using closed circuit television equipment.
No abnormal conditions were found.
Secondary Plant Inspections 1.
The No. 3 boiler feed pump check valve was opened for inspection.
No abnormalities were detected.
2.
The steam side of the main condenser was inspected. No abnormal conditions were detected.
3.
The following circulating water components were inspected:
a.
The No. 2 circulating water pump impeller bell hcusing.
b.
The circulating water inlet pipe.
c.
The circulating water outfall foundation.
The inspection in.cluded visual observation and photographing of the above listed components. No abnormal conditions were detected.
/'~'h 4.
The turbine lube oil reservoir, oil screens and strainers were inspected
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and cleaned. No sbnormalities were detected.
5 The No. 2 heater drains pump was removed for inspection. Minor repairs were required.
6.
The No. 1 and No. 2 steam extraction line check valvec were inspected and found to be in good condition.
7 The No.1 feedvater line check valve in the vapor container was inspected.
No abnormal conditions were detected.
Plett Maintenance The following is a list of pertinent plant maintenance items performed additional to the major work items, during the month of March, 1972.
1.
Installation of a new air baffle assembly on the reactor head was completed.
2.
The main coolant pump hangers were readjusted as required.
3.
Seven new valves were installed in the service vater system to facilitate future chemical cleaning of the piping.
4.
Maintenance was performed on the North incore instrumentation thimble
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j during which the backup plug was removed; the joint between the primary
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seal assembly and the instrumentation rack was ground out and revelded; the spacer plug was replaced; and two paths were removed from service by
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-installation of seal welded plugs.
5 The se u and discs of vapor container recirculation valves PU-MOV-5h?
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-and 548 vere lapped.
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Instrumentation and Control The'following is a list of pertinent instrumentation and control maintenance items performed by the plant staff during the month of March, 1972, 1.
Calibration of the following was performed:
.a.
. Narrow range pressurizer level.
b.
Wide range pressurizer level, c.
Pressurizer pressure transmitter.
d.
Charging and volume speed control.
. Steam generator level and pressure channels No.'s 1,2,3 and h.
e.
f.
TRT-3C recording ohmeter.
2.
Ppecial Test No. 72-3, " Monitoring of Spent Fuel Pit with New h.0 v/o Zire Clad Fuel Assemblies", was completed.
3.
Assisted with TV inspection of reactor vessel components, k.
A second pressure switch and time delay relay for the reactor permissive circuit was installed and tested.
5.
The slidevires and cam followers on the steam generator level receivers were replaced.
V' 6.
The feedvater control and bypass valves were repacked.
7.
The V.C. isolation trip valve test was performed, satisfactorily.
8.
The pressurizer pressure safety injection initiation switch was replaced.
Chemistry The main coolant boron concentration and pH averaged 2h95 ppm and 5.22, respectively during the report period.
The main coolant beta-gamma specific activity and crud level averaged 1.20 x 10-3 ue/ml and 0.42 ppm, respectively.
The main coolant tritium concentration averaged 3.09 x 10-2 ue/ml during the period.
The iodine-131 specific activity averaged 7.04 x 10-6 ue/ml.
A crud sample for the month collected on March 3, had the following radiochemical analyses:
dpm/mg crud Cr-51 Mn-5h Fe-59 Co-58 5
fx 2.55'x 106 1.92 x 105 3.h8 x 105 9.81 x 10
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sb-12h Co-60 Ag-110M Zr-95 g 3
3.38 x 105 2.98 x 105 4.88 x 10 5 10 x 10
_ _ _ _ = - _ - - _ - _ _ _ _
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Health and Safety Wasto disposal liquid releases totalled 93,504 gallons containing 0.036 me of gross beta-gamma activity and 61.0h curies of tritium. There were no secondary releases during the period.
In addition to the above releases 1.1hl curies of tritium as a 1-vapor were purged from the vapor container through the primary vent stack.
Radiation exposure doses for Yankee personnel; NEPSCo personnel; and Outside Contractor personnel as measured by film badge for the month of March, 1972 vere:
Yankee Plant Personnel:
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Average accumulated exposure dose:
305 mrem.
Maximwn accumulated exposure dose:
1160 mrem.
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j N.E.P.S.Co Personnel:
Average accumulated exposure dose:
391 mrem.
Maximum accumulated exposure dose:
3480 mrem.
4 Outside Contractor Personnel:
Average accumulated exposure dose:
1138 mrem.
lG Maximum accumulated exposure dose:
26h0 mrem.
Operations
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Attached is a summary of plant operating statistics for the month of March, 1972.
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l YANN ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
March 1972 t
MdNTH YEAR TO DATE ELECTRICAL Gross Generation KWH 0
1k7,688,100.
13,163,564,000 Sta._ Service (While Gen. Incl. Losses)
KWH 0
10,086,184 851,155,T98 KWH 0
137,601,916 12,312,408,202.
Net Output.
- St'ation Service' 0
6.83 6.47 Sta'. Service'-(While Not Gen. Incl. Losses) KWH 531,478 1,835,485 34,939,877 Ave. Gen. For Month (Thh)
KW 0
Ave. Gen. Running
'(0)
KW 0
~ PLANT PERFURMANCE Net Plant Efficiency 0'
27 92' 28.45 Net Plant' Feat Rate btu /KWH 0
12,232 11,974 Plant Capa.
7 Factor 5
0 37.61 76.09 8h'.60 Reactor Pla Availability 0
53.5h MONTH CORE IX
' TOTAL'
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NUCLEAR 1
Hours Critical HRS 0
10,520.59 85,484.99 0
5 66 Times Scrammed
' Burnup Core Average MTD/MTU 0
11,9h6.29
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i MWD /MTU Re6 on Average A (INNER) 0 11,757.8h -
28,961.51-B (MIDDLE) 0 13,940.87 22,682.72 C (OUTER).
0 9,974.66 9,37h.66 D (ZIRCALOY) 0 I
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F YANKEE ATOMIC IC COMPANY
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i DAILY E LOAD FOR
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March 1972
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200-m en 8
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100 _
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I (Core IX-X Refueling in progress during March 1972) 0-
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10 15 20 25 30 I
DAYS i
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~ FUEL ASSEMBLY UW-00T O
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
X MM X
o cf 2_X EM X
s XX XX 7
XX XX o
/XX X'X'N XXXX J=~z
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A A 4.94 %
N STAINLESS C 4.001 ZlRCALOY
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