ML20137B443
| ML20137B443 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 01/01/1974 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20137B401 | List: |
| References | |
| FOIA-85-723 NUDOCS 8511260274 | |
| Download: ML20137B443 (27) | |
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT llADDAM, CONNECTICUT SEMIANNUAL OPERATING REPORT No. 73-2 FOR Tile PERIOD OF JULY 1, 1973 to JANUARY 1, 1974 i
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February 28, 1974 I
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8511260274 B51119 PDR FOIA RATHJEBS-723 PDR 2
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OPERATIONS
SUMMARY
Near the end of the last six month reporting interval the plant had been removed from service to investigate the reason for increased turbine vibration, localized at the #6 bearing. The #2 Low Pressure Turbine was disassembled and inspected. Two blades and one piece of shroud were found missing from the 6th rotating stage (generator end). One blade and a piece of shroud were missing from the 7th stationary row. All sixth row blades (rotating and stationary) were removed and the unit was reassembled and returned to service at a vendor imposed limit of 515 MWe. Plans were developed to replace the 6th row blades during the fall refueling shut-down. On July 8,1973 turbine vibration alarms were received at the main control board indicating a problem with the #2 Low Pressure Turbine. A load reduction was commenced when local readings confirmed the main control board annunciated alarms, and the unit was removed from service. Later disassembly and inspection of the #2 Low Pressure Turbine revealed extensive damage to the 7th rows, both stationary and rotating. One blade and one piece of shroud were missing from the 7th rotating row. Six blades and three shroud sections were missing from the 7th stationary row. Non-destructive testing revcaled numerous cracks in the first serration of many of the rotor steeples in the 6th and 7th rows. Top serrations from selected rotor steeples were removed for metallurgical examination. As a result of metallurgical examinations performed by the vendor, a decision was reached on August 2,1973 to replace the two low pressure turbine rotors before the unit was returned to service. The rotors were replaced with rotors available in the vendor's shop. These rotors required minor modifications and repairs before installation. A decision was also reached on August 2,1973 to advance the refueling date and complete the work during the current shutdown.
The first of the two replacement low pressure turbine rotors arrived at the site on a barge on October 15 and the second replacement turbine arrived on 11/5/73. By the end of November the "B" Low Pressure Turbine was in place with the upper half components installed. A blade frequency modification program was completed on the new "A" Low Pressure Turbine after a similar frequency modification was successfully tested on the old "A" Low Pressure Turbine. The "A" Low Pressure Turbine was then installed and the entire unit was ready for service by mid December. The generator was phased to the electrical grid at 1806 on December 14, 1973 ending a five month long outage. During the remainder of the report period the unit was operated at full licensed capability except for three shut-downs for turbine / generator balancing and main generator / exciter maintenance.
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etration from eddy current tests Flux Mapping System- Dirt in Detector would None Cleaned out path with cleaning None required Thimble M-8 thimble not insert tool.
fully Primary Water Storage Normal wear Torn seal None Installed new floating head None required Tank Floating Head seal. '
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- 4 Steam Generator Unknown One support None Installed new support. None required
, Ferd Ring Support broken
, Emsrgency Diesel Wire rubbing Inoperative None Repositioned mercury switch. None required G;ntrator Day Tank against mer- alarm Level Alarm coid switch
, case Manipulator Crane Broken cable No indication None Replaced cable. None required i Arca Radiation
. Monitor Fusl Transfer Car Too much Cable broke when None Replaced cable and adjusted None required Ceble slack first operating slack.
carriage
, Air Supply Line To Vibration Fitting parted None Replaced copper tubing with None required RH-FCV-602 closing valve Heavy wall flexible rubber
,] tubing.
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? EFFECT SPECIAL PRECA!!TIONS -
,- SYSTEM ,
ON CORRECTIVE ACTION TAKEN TO PROVIDE b ' OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT RESULT OPERATION REPETITION DURING REPAIR
] CAUSE -
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i Switchgear Room Sheared pin High Tempera- None Replaced sheared pin None required l 1 Ventilation Damper ture at vital ,
bus inverter l t
resulting in U 'l . voltage spikes *
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l ,#4 Feedwater Water hammer Bottom flange None Replaced bottom flange gasket. None required j 4 Regulating Valve due to proced- leak Reviewed procedure with those ural error involved, j 4 1
- NuclearInstrumenta- Failed light Over-power rod None Replaced light source. Optical, None required ;
tion System Channel source stop alarm meter relays to be replaced with ,
l 31 Meter Relay- new design. i I:
lCondsnser Air- Faulty Erroneous None Replaced detector None required. ;
Ejector Radiation detector readings , !
' Monitor !
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F' Nuclear Instrumenta- Faulty driver Low countrate None. R'placed e J-203 card None required l tion System card
, Channel 11 t
- 2 Steam Line AP Failed light Reactor trip None Replaced light source. Optical None required Rasetor Trip Unit source alarm meter relays to be replaced with i new design.
i RHR-MOV-804 Galled yoke Valve did not None Replaced bushing None required ,
! (RHR to Loop 2) bushing threads operate elect-l rically i
Safety Injection' Unknown Valve seat cut None Welded new seat None required
- l Valva HCV-1881 I (Pump Recirc. Valve) let Stage Evaporator Normal wear Seal leakage None Replaced pump seal and repaired None required
- Bottoms Pump worn shaft.
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t-EFFECT SPECIAL PRECAUTIONS SYS11;M ON CORRECTIVE ACTION TAKEN TO PROVIDE . l MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY ,
ts CAUSE RESULT OPERATION REPETITION DURING REPAIR COMPONENT i Reactor Vessel Head Loose soldered Intermittent None Repaired cold soldered connector None required Laak Detection connection alarms - on alarm relay coil circuit. ,
Alarm Unit ,
Emergency Diesel Moisture in. The engine did None The air start system was modi- None required Crnerator 2B' Air air start not start until fled to prevent moisture Start Motor system both banks of accumulation.
air start
! motors were energized .
A & B Steam Erosion Leakage past None Machined seat rings and discs. None required Generator Feed valve seats Pump Isolation Valves
- 2 Rod Drive Normal wear Fan inoperative None Replaced with rebuilt unit. None required
, Cooling Fan i Emergency Diesel Unknown one of 20 None Replaced f a.ulty injector. The None required Generator 2B Fuel injectors did injector was returned to the Injector not cperate vendor for analysis.
The timers did See Replaced f aulty contacts. None required Service Water and Insufficient Containment Air relay contact not operate AO 73-9 Inspecting at increased Recirculation Fan pressure when teste( and frequency. Investigating relays Timing Relays the equipme'nt of improved design.
(Type SV) failed to start Loss of power See A design change is under consid- None required Motor Control Design Center-5 Power deficiency to motor con- A0-73-10 eration. Written procedures win i
trol center be used when performing maint-Supply Auto-
~ Transfer Mechanism enance on the affected breakers.
Failed head Steam leak None Replaced head gasket. None required Primary Water
' ' Storage Tank gasket i
Heater , .
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EFFECT SPECIAL PRECAUTIONS SYST121 ON CORRECTIVE ACTION TAKEN TO PROVIDE i OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY '
COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR
, Loops 2 & 3 Steam Borated water Rusted bolts None All bolts replaced. Gasket None required Generator Primary leakage . surfaces repaired. 4 Manway Bolts l #1 Reactor Coolant Slight wear on Higher than None Replaced #1 seal and runner. None required l Pump #1 seal face normal seal plates water return l
flow Feedwater Manual Steam cut Valves leak by None Remachined valve seats and plugs None required and Motor Operated internally '
f l Isolation Valves Primary Auxiliary Loose float Sump overflowed None Tightened loose float switch None required l ,
Building Sump Pump switch actu- to floor of PAB actuating arm. ,
~ Float Switch ating arm .
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8 Main Stack Radiation Normal wear Pump inoperative None Replaced two belts and the pump. None required a Monitor Sample Pump "A" High Pressure Unknown Boric acid None Replaced bonnet gasket. None required Safety Injection leakage _
Pu=p Suction Valve {
"A" Aerated Drains Normal wear Seal leakage None Replaced mechanical seal. None required Tank Pump Radiation Monitoring Frayed cable No response None Repaired detector cable. None required System Channel 35 Letdown Relief Unknown Leakage past None Relapped seats and rebuilt None required Valves 205 and 252 seats valves.
. Radiation Monitor- Loose wires Detector inoper- None Resoldered connectors at None required ing System Channel ative detector and replaced fuse.
. 36
- 1 Reactor Coolant Failed light No temperature None Replaced failed light scurce. None required Pu=p Lower Bearing source ind ica t ion Te=perature
i EFFECT SPECIAL PRECAUTIONS V SYsil21 ON CORRECTIVE ACTION TAKEN TO PROVIDE '
tu MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPCNENT CAUSE RESULT OPERATION REPETITION DURING REPAlR Refueling Water Torn valve Water leak See More frequent replacement of None required Storage Tank diaphragm A0 73-11 valve diaphragm. Installed a Hester Isolation travel stop device to prevent Valve over-conpression.
Boron Recovery Leaking head Water leak None Replace head gasket. None required Evaporator gasket Site Evacuation Faulty One half of None Replaced two output transistors. None required Alarm transistors alarm system -
inoperat iv e RCP Seal Water Hi Failed light Hi tenperature None Replaced light source. Optical None required Te:perature at source alarm meter relays will be replaced.
i Seal Alarm
" Nuclear Instru- Failed light Low alarm on None Replaced light source. Optical None required
' centation System source main control meter relays will be replaced.
Power Range board Channel 33 Control Air Branch Vibration Broken air None Resoldered broken joints. None required Line Break line '
- 1, #2 Low Stress Cracked and None Replaced both low pressure None required '
Pressure Turbines corrosion / thrown blades turbines.
f a tigue A & B Emergency Poor design Split expansion None Replaced with new design None required Diesel Generator joint expansion joint.
Exhaust Mufflers Prescurizer Relief Unknown Leakage past None Relapped seat and retested Cold shutdown
. valve 584 valve seat valve. ;
Stea= Cenerator Stress Twenty-four of See All fractured bolts replaced. Cold shutdown Seismic Support corra-t:- 256 bolts 73-8 and All other bolts ultrasonically
' Hold Down Bolts '
fractured 73-12 tested. Bolt ronitoring syste= -4 installed. New design under .
. consideration.
PLANT CHANGES. TESTS, EXPERIMENTS The following is a brief description and a summary of the safety evaluation for those changes which were carried out without prior Commission approval, pursuant to the requirements of 10 CFR Part 50, Section 50.59 (b):
Plant Design Change #93 entitled, " Temporary Bypass of Letdown Valve Closure and Pressurizer Heater Trip" was completed. This change provides a means of returning pressurizer heater control to the operator to override the heater trip that occurs upon loss of the light source in the optical meter relay. The safety evaluation concluded that the change is not an unreviewed safety item because the probability of an accident important to safety previously evaluated will not be increased and the possibility for an accident of a dif ferent type than any evaluated previ-ously will not be created.
Plant Design Change #118 entitled, " Emergency Diesel Generator Starting Air System Modification" was completed during the month. The change modifies the air starting system piping to provide separate compressor discharge and starting motor supply headers. Additionally, a trap is installed to automatically drain off the accumulated condensate from the air receivers. The change will reduce required maintenance and parts replacement on the starting air motors. The safety evaluation concluded that the probability of occurrence and the consequences of an accident or equipment malfunction are not increased by the change. The evaluation further states that the possibility for a dif ferent type of accident other than that previously evaluated does not exist and the margin of safety is not reduced. The evaluation concluded that the change i represents sound engineering judgement and increases plant reliability.
Plant Design Change #120 entitled, " Upgrading of Semi-Vital Bus Power Supply" was completed during the month. The change invoi res the installation of two 5 KVA regulated transformers, in place of the presently installed unregulated transformer; installation of an automatic bus transfer switch in place of the mechanical switch; installation of an alarm to signal bus transfer. The originally installed semi-vital bus power supply produces a plant trip when the power supply fails. The new installation provides two regulated power supplies. A failure of one power supply will automatically cause a switchover to the redundant supply without a plant trip. The alarm will notify the operator of the change. The safety evaluation concluded that the change will increase the reliability of the semi-vital bus power supply by having two available regulated power nupplies.
Also, this change will remove the possibility of a plant trip with the installation of an automatic bus transfer switch. The evaluation further concluded that the change is not an unreviewed safety item because the probability of an accident previously evlauated will not he increased or created. l 1
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Plant Design Change #121 entitled, " Upgrading of Emergency Diesel Generator Timer Circuitry" was completed during the month. The ,
j change involves rewiring the emergency diesel generator timers to provide a 110V power supply to each timer. Before the change was made, an open circuit in the power supply line could cause a loss of all timers in the circuit. The safety eva16ation concluded that the design change will increase the reliability of the diesel generator operation and that the change is not an unreviewed safety item; also, the probability of an accident previously evaluated will not be increased.
Plant Design Change #125 entitled, " Oil Separator Installation In Vapor Extractor Line" was completed during the report period. The change involved the installation of an oil separator system in the exhaust line from the turbine lube oil reservoir vapor extractor and the generator oil vapor extractor. The separator removes oil that previously was ex-pelled to the atmosphere. The safety evaluation concluded that the probability of occurrence and the consequences of an accident or equip-ment malfunction are not increased by this plant design change. Also, the possibility for a dif ferent type of accident other than that previ-ously evaluated does not exist and the margin of safety is not reduced.
The evaluation further concludes that the change represents sound engi-neering judgement and will increase plant reliability.
Plant Design Change #127 entitled, " Modification of PAB Instrument Air System" was completed during the month. This change involves the addition of isolation valves in the auxiliary building control air system to provide the ability to isolate a break with minimum ef fect on the plant.
The change also involves the addition of a separate header to RHR valves in the PAB. The safety evaluation concluded that the change will improve the reliability of the system and will not constitute an unreviewed safety item.
Plant Design Change #135 entitled, " Modification To Yard Crane Structure" was completed during the month. The change involves the addition of a side brace to the Northwest Yard Crane support column and removal of an existing cross brace. The change was necessary since the addition to the ion exchange cubicles extends through the present cross brace location.
The safety evaluation concluded that the probability of occurrence and the consequences of an accident or equipment malfunction are not increased by this change. Also, the possibility for a dif ferent type of accident other than that previously evaluated does not exist and the margin of safety is not reduced. The change represents sound engineering judgement.
Plant Design Change #138 entitled, " Diesel Generator Day Tank Overflow Protection" was completed. This change will prevent over-filling the day tanks and overflowing to the diesel generator building floor drains.
The safety evaluation concluded the following: (1) The probability of occurrence and the conaequences of an accident or equipment malfunction are not increased by this plant design change. (2) The possibility for a different type of accident other than that previously evaluated does not exist. (3) The margin of safety is not reduced. (4) The change represents sound engineering judgement.
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Plant Design Change #142 entitled, " Prevention of Inadvertent Defeat of Redundant Saf eguards Equipment" was completed during the month.
This change corrects a design deficiency that could have defeated the auto- '
matic starting of backup service water pumps and containment air recir-culation fans, if the breakers for the primary components were racked out.
The change will allow starting of the redundant alternate component irre-gardless of the breaker position for the primary component. The safety evaluation stated that the change involves a modification which results in the circuit acting in accordance with the original analysis. The safety evaluation concluded that the modification is safety related but does not constitute an unreviewed safety item.
Plant Design Change #154 entitled, " Reactor Coolant Pump Oil Lif t System" was completed during the month. The change involves the addition of an isolation valve to facilitate calibration of the pressure gauges on all four reactor coolant oil lift systems. The change will prevent spilling oil on the side of the motor when gauge removal is necessary. The change also involves repiping the oil lines to the pressure gauges and alarm switches on all four pumps. The repiping will facilitate checking the alarm setpoints. The safety evaluation concluded that addition of an isolation valve and the repiping of the oil line with 3/8" stainless steel tubing will not constitute unreviewed safety items.
The evaluation further concluded that the changes will improve the reliability of the components in the RCP oil lif t system.
Plant Design Change #155 entitled, " Removable Insulation For Inservice Inspection" was completed during the report period. The change involves removal of permanent insulation over areas to be inspected as part of the Inservice Inspection Program and replacement with removable pad type insulation. Removable insulation over inspection areas mini-mizes personnel radiation exposure. It also minimizes dust and debris from repetitive removal or permanent insulation. ine safety evaluation concluded that the change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FDSA. Also, the possibility of an accident or malfunction of a dif ferent type than any evaluated previously in the FDSA will not be created. The evaluation further concludes that the margin of safety as defined in the basis for any technical specification is not reduced and is not an unreviewed safety item.
Plant Design Change #161 entitled, " Steam Generator Bolt Monitoring System" was completed during the report period. The change involves installation of a micro-switch on each of 256 steam generator lower support bolts to detect an upward motion of the bolt head which is characteristic of a failed bolt. The change provides a system to contin-uously monitor the steam generator support bolts for failure. The safety evaluation concluded that the probability of occurrence and the consequences of an accident or equipment malfunction are not increased by this change.
Also, the possibility for a dif ferent type of accident other than that previously evaluated does not exist and the margin of safety is not reduced.
The evaluation further concludes that the change represents sound engineering judgement.
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Plant Design Change #162 entitled, " Steam Generator Hold Down Bolt Repair" was completed during the report period. The change involves installation of twenty-four new bolts to replace those that were fractured. -
The change will allow the steam generator support structure to function as originally intended. The safety evaluation concluded that the probability of occurrence and the consequences of an accident or equipment malfunction are not increased by this change. Also, the possibility for a different type of accident other than that previously evaluated does not exist and the margin of safety is not reduced. The evaluation further concludes that the change represents sound engineering judgement and based upon the detailed stress analysis of the ring girder, the cut sections of the ring ,
girder have no adverse effects upon the integrity of the steam generator support .
l PR7 MARY C001. ANT CHEMISTRY -
I JULY AUGUST SEPTEMBER OCTOBFR NOVEMBER D8CDGER
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- g Max. Min, g Max. Mir . AvR. Max. Min
- g g Min. g Max. Min. g Men. Min. ,
pu 9 25'c 6.16 7.50 5.15 5.60 6.00 5.15 5.40 5.75 5.00 5.26 5.60 5.00 5.49 5.75 5.15 5.73 6.20 5.15 conductivity 12.3 20.5 3.94 9.13 11.30 4.9) 10.6 15.5 8.9 11.4 14.6 9.35 9.79 13.5 8.7 11.0 18.6 4.70 .
(ashos/ca)
Chitrides <07 <07 <.07 < 07 <.07 <.07 <.07 <.07 <.07 .07 .07 c 07 .07 .07 c.07 .07 .07 c.07 (ppe)
, Di: solved 0 0 0 Not Measured 0.8 0.8 0.8 Not Heasured Not Measured 6.7 .10 5 Osy8en (ppb) ppm pp l ,I PPe PPS Borsn 752 1482 175 2057 2824 1473 3050 2952 2835 2938 2994 2842 2855 2962 2766 1903 3211 1204 (ppa)
Lichtua 1.65 ~ 2.15 1.25 Not Measured Not Measured Not Measured Not Measured 0.93 1.1 0.85 t (ppa)
Gross Activity 1.7(-1)* 7.2(-3) 8.4(-3) 5.3(-3) 3.1(-2) 1.0(-3) 4.4(-3) 2.4(-2) 4.8(-4) 2.6(-3) 1.4 (-2) 5.1(-4) 7.4(-3} 1.3(-2)'2.2(-3) 2.5(-1) 7.4 (-1) 1.6(-3) j (.,C1/al)
Iodine 3.7(-3) 6.7(-1) 7.5(-4) Not Measured Not Measured Not Measured
! I Not Measured 8.3(-3) 8.3(-3) 8.3 (-3) g (wC1/al)133I Trittua 7.43 7.71 6.90 Not Measured Not Measured 3.29 3.29 3.29 3.3 3.3 I 3.3 2.8 3.5 2.3 (6C1/al) 131g/133g ,75 .75 75 Not Measured Not Measured Not Measured Not Measured 2.75 2.75 2.75 Ratio t
t r 12 15 9 Not Measured Not Measured Not Measured Not Measured 27 27 27
- 1.7(-1) = 1.7 X 10-1 i
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REPORT OF RADIOACTIVE EFFLUENTS 6 Months Summary July to December 1973 Facility: Connecticut Yankee Atomic Power Company Docket: 50-213
- 1. LIQUID RELEASES Unita Torn 1
- 1. Gross radioactivity (8,y)*
a) Total release Curies 2.45 b) Avg. concentration released pCi/ml 1.67(-8) c) Max. concentration released uCi/ml 2.84(-7)
- 2. Tritium a) Total release Curies 2.85(3) b) Avg. concentration released pCi/ml 1.94(-5)
- 3. Dissolved noble gases a) Total release Curies 4.93(-2) b) Avg. concentration relenmed u ci/ml 3.35(-10)
- 4. Gross alpha radio-activity a) Total release Curies 6.19(-3) b) Avg. concentration released u Ci/ml 4.21(-11)
- 5. Volume of liquid waste to discharge canal Liters 5.33(6)
- 6. Volume of dilution water Liters 1.47(11)
- 7. Isotopes released Curies Kr-87 I-133 I-131 4.98(-3)
Xe-133 4.60(-2)
Xe-135 3.28(-3)
Cs-137 2.46(-1)
Cc-144 4.08(-1)
Co-60 4.84(-1)
Co-58 6.59(-1)
Cr-51 4.49(-1)
Mn-54 Ru-103 1.84(-1)
Sr-90 1.82(-4)
Sr-89 6.45(-5)
Unidentified (Gross 6-y) 8.06(-3)
- 8. Percent of tech. specs.
limit for total activity released ** 2.69(-1)
- Except tritium and dissolved gases
- Based upon actual available dilution water
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II. AIRBORNE RELEASES Units Total l
- 1. Total noble gases Curies 1,97(1)
- 2. Total halogens Curies 6.68(-4) ,
- 3. Total particulate gross radioactivity (S.Y) Curies 8.90(-3)
- 4. Total tritium Curies 4.56(1)
- 5. Total particulate gross alpha radio-activity Curies NDA*
- 6. Maximum noble gas release rate uCi/sec. 9.26
- 7. Percent of applicable 1 Lait for:**
a) Noble gases % 7.27(-3) b) Halogens % 7.07(-4) c) Particulates % 9.37(-3) d) Tritium 2.00(-2)
- 8. Isotope released:
Particulates Curies C-14 1. 66 (-2 )
Ba+La-140 Sr-90 Cs-138
, Rb-88 Unidentif ied 8.89(-3)
Halogens 1-131 6.68(-4) 1-133 1-115 Gases Kr-85 9,97 Xe-133 9.52 Kr-88 2.16(-2)
Kr-8/ 7.43(-3)
Kr-85m Xe-138 Xe-135m 1.64(-2)
Xe-135 1.91(-1)
Ar-41 1.04(-2)
Ar-3 7' 3.89(-2)
- }
- NDA = No deceStable activity
- Based upon actual available dilution air
SOLID WASTE SHIPMENTS Volume Curie Date Material Ft3 Content Disposition 8-21-73 Radioactive waste 1058 341 Offsite Burial compacted into 55 gallon drums 9-13-73 55 gallon drums 992 1.496 Offsite Burial compacted waste 9-19-73 180 ft3 spent 180.0 133.00 Offsite Burial resin 9-21-73 55 gallon drums 661.5 .177 Of fsite Burial compacted waste 10-09-73 Compacted waste in 787 .908 Offsite Burial 55 gallon drums 10-31-73 Resin 45 5.2 offsite Burial 11-07-73 Compacted dry waste 706.0 0.174 Offsite Burial in 55 gallon drums 12-12-73 Compacted dry 102.9 2.733 offsite Burial waste
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OCCUPATIONAL PERSONNEL RADIATION EXPOSURE July 1, 1973 - January 1, 1974 4
' EXPOSURE INCRENENTS NO. OF PERSONNEL 4
Less than 100 mrem 558 100 - 250 mrem 85 1
250 - 500 mrem 37 500 - 750 mrem 24 l 750 - 1000 mrem 35 ,
! 1 - 2 Rem 108 1
2 - 3 Rem 59 3 - 4 Rem 11 4 - 5 Rem 10 1
1 4 5 - 6 Rem 1
>6 Rem 0 5 NUMBER OF PERSONNEL RECEIVING OVER 500 MRFF AND CONDITIONS i
! 1. Routine Refueling Operations 31 l
i 2. Special Plant Surveillance / Inspection i
In-Service inspection-primary system welds 25 Inservice inspection-insulation 13 Eddy current testing-steam generator tubes 24 Hydrostatic tests-primary system 18
! 3. Special Plant Maintenance Steam generator hold-down bolt repair 57 Steam generator manway surface repair 62 Refueling canal gate installation 18 i
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