ML20137B416
| ML20137B416 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/01/1973 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20137B401 | List: |
| References | |
| FOIA-85-723 NUDOCS 8511260269 | |
| Download: ML20137B416 (21) | |
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT SEMIANNUAL OPERATING REPORT NO 73-1 FOR THE PERIOD OF JANUARY 1, 1973 to JULY 1, 1973 i
l August 28, 1973 hM 12p Q 9 851119 ,
RATHJE85-723 PDR L
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OPERATIONS
SUMMARY
The plant was operated base-loaded throughout the report period. Load reductions to 4h00 MWe for routine turbine stop and control valve testing averaged one per week during the report period. The. plant was shutdown three times during the six month period, all three being secondary system problems. (Feedvater control valve, moisture separator reheater and turbine).
Gross electrical generation for the month of March was the highest for a single month in the six year history of the plant. Gross electrical generation to date exceeded 22.5 billion KWil during the report period.
CliANGES IN FACILITY DESIGN j The only major changes in facility design in progress during the report
! period are the changes to the radioactive waste systems. The upgraded i gaseous waste system will provide a means of removing dissolved gases from plant liquids, compressing and storing them. The aerated liquid waste system will provide filtration, ion exchange, holdup, evaporation and drumming of contaminated, aerated liquids. The existing primary auxiliary building ventilatic,n and containment purge systems will be modified to include prefilters and charcoal filters. These changes are being made to upgrade present radwaste '
j facilities to meet new guides and standards. -
FUEL j Routine radiochemical analysis of reactor coolant confirms the continuing
! integrity of the fuel cladding. The concentration of radioactive fission products is indicative of very ninor defects in a few fuel tubes.
I STEAM GENERATOR TUBES A primary to secondary steam generator tube leak developed in the.#1 l steam generator on h-26-73. The leak remained relatively constant at %10 gallons per day. During the June outage the leaking tube was identified and 4
explosively plugged. Eddy current testing of the tubes in at least two i steam generators is planned for the forthcoming refueling and maintenance l outage.
2 i .
RESULTS OF SURVEILLANCE TESTS / INSPECTIONS I
All checks, calibrations, tests and inspections required during the report period were completed. In the performance of three surveillance tests problems were identified, reported and corrected. They are !
sunsnarized below:
1-11-73 Pressurizer Level Six Week Setpoint Check One of three pressurizer high level trip channels was found inoperative. To prevent recurrence the existing thermovolt i optical meter relays will be replaced systematically with a relay of improved design. This event was reported to
, DOL-AEC as Abnormal Occurrence.73-1.
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3-2-73 Pressurizer Pressure Six Week Setpoint Check One of three pressurizer pressure / core cooling trip unit setpoints was found unacceptable during the six week surveillance check. To prevent recurrence the existing thermovolt optical meter relays will be replaced systematically with a relay of improved design. This event was reported to DOL-AEC as Abnormal Occurrence 73-2.
4-4-73 Emergency Diesel Generator Monthly Rest During a routine monthly operational test of Emergency Diesel Generator 2B, the diesel load was observed to be oscillating approximately 200 KW. A load gain potentiometer locking mechanism had loosened allowing the governor to exceed normal oscillation. This event was reported to DOL-AEC as Abnormal Occurrence #73-3 TECHNICAL SPECIFICATICN CHANGES Change #21 Section 5.7 entitled " Plant Reporting Requirements" was approved by AEC during the report period. The change standardizes our reporting requirements with other facilities.
Change #20 This change describes our respiratory protection program and provides allowances for the use of respiratory protective equipment.
VIY SUPERVISORY PERSONNEL CHANGES Mr. Paul Ahern, Shift Supervisor has been promoted to Operations Supervisor to fill a vacancy created by the transfer of Mr. Marshall Morris to the position of Technical Assistant to the Superintendent. All other key supervisory positions remain unchanged.
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a POWER GENERATION (Jan - July)
Gross Thermal Power Generated 6,958,419.00 MWH Gross Electrical Power Generated 2.293.750.00 MWH Net Electrical Power Generated 2,184,699.70 MWH Hours Reactor Critical 4031.1 Hours -
Hours Generator On-line 3920 7 Hours e
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. PLANT CHUTDOWHS Date Duration Method of Plant (Hours) Shutting Status Cause Of Outage / Corrective Action Down Reactor During l Outage 2-2-73 9.3 Manual Trip Hot Standby Manual plant trip as a result of uncontrolled increase in S.G. #2 level. The connector between the #2 feed water control valve stem and actuator loosened, permitting the valve to go fully open.
The valve stem and actuator vere reconnected and bolted. The plant remained in hot standby while 4 repairs were made and miscellaneous maintenance performed.
The connecting bolts on all four feedvater valves were replaced with longer bolts and locking nuts
, were applied.
o i' 2-2k-73 L6.7 N/A Hot Standby Planned shutdown to investigate the source of noise and lov outlet temperature from "D" moisture separator reheater. Inspection revealed an eroded steam inlet baffle. The baffle bolts were eroded, permitting the baffle to drop from its bolted position.
I The baffle was velded back in place. Eight leaking tubes were plugged. The plant remained in hot stand-by while moisture separator reheater repairs were made and miscellaneous maintenance was perfor=ed.
6-2-73 366.h Manual Planned shutdown to investigate the reason for in-to Controlled Cold crease turbine vibration at the #6 bearing.-
) 6-17-73 Shutdown Shutdown lhe #2 L.P. Turbine was disassembled and inspected.
Two baldes and one piece of shroud were found missing from the 6th rotating stage (generator end). One blade
, and a piece of shroud was missing from the 7th stationary rov. All sixth row blades (rotating and stationary) were removed and the unit reassenbled.
The primary plant was cooled and depressurized and one leaking tube in the #1 steam generator was explosively plugged. In addition to the turbine and steam generator repairs, many oth'er items on the shutdown work list were repaired.
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EFFECT SPECIAL PRECAUTIONS SYSTEM . ON CORRECTIVE ACTION TAKEN TO PROVIDE
, OR MALFUNCTION SAFE TAKEN 'IO PREVENT FOR REACTOR SAFETY. .
I COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Emsrgency Generator Faulty micro- Speed changer None Installed a new micro-switch in None required t2A Electric Governor switch inoperative the raise-lover circuit Spard Changer during diesel test Pre'ssurizer Level Faulty thermo- Hi-level trip None Replaced thermovolt meter relay. Tripping logic changed Chdnnel 1 - Hi Level volt meter unit on channel A meter relay of improved design from 2/3 to 1/2 Trip Unit relay 1 inoperative has been ordered.
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1BjRHR Pump Seal Line Normal wear Leakage None Replaced leaking svage-lock None required
', fitting J#2 Containment Recire. Erosion Tube leakage None Plugged one leaking tube and None required Fan Cooler adjusted flow through all coolers
- 1 Stcam Line High AP Failed light Reactor trip None Replaced light source. Meter None required Rtactor Trip Unit source signal relays of improved design have i been ordered and will be U: replaced systematically.
A - Auxiliary Steam Erosion Leakage past None Relapped seat and reset valve None required G nerator Feed Pump valve seat Casing Relief Valve
'A & B Energency Diesel Erosion Leakage past None Installed new erosion resistant None required Gancrator Engine valve stainless steel valves !
Cooling Control Valves l Rod Control Subgroup 4 Faulty time Rods misstepped None Installed new h-TR1 time delay None required delay relay relay Precsurizer Pressure Faulty light Pressurizer low None Replaced light sensitive photo- Tripping logic Channel 2 sensitive diode pressure / core diode. Meter relays of changed from cooling trip improved design will be in- 2/3 to 1/2 point lower than stalled required Prcarurizer Spray Dirty E/P con- Sluggiso valve None Cleaned E/P converter and valve None required Valve ST3 verter and operation positioner f positioner '
I EFFECT SPECIAL PRECAUTIONS I
SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAF5TY
, f, COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR w -
!, t I'oLoop 3 Ret.. t ar Coolant Failed light Lov flow indi- None Replaced light source. Meter None required Flow Indica.t un source cation relays of improved design have been ordered and vill be l installed systematically "B" Service Water Normal wear Upper bearing None Replaced upper bearing None required Pump noisy
- #2 Feedvater Control Vibration Valve stem Plant Installed longer bolts on clamp None' required iValva parted from Trip between stem and actuator. Also, valve actua- installed -double nuts and lock-tor when bolts washers
. " ~ , . loosened b ,
Pressurizer Pressure Failed power Lov pressure / None Replaced fuse None required
. Channel 2 supply fuse core cooling i t trip alarms y actuated i
,1B uxiliary Steam Too much Hot inboard None Removed one ring of packing None required Ghnsrator Feed Pump packing gland Plant AT Alarm Failed I/I Oscillating AT None Replaced I/I converter None required Circuit converter
+t Containment Purge Broken linkage Damper inopera- None Repaired linkage None required Fan' tive
'i Nuclear Instrumenta- Failed light Hi-level alarm None Replaced failed light source None required tion System Channel.ll4 source annunciated I
' Enargency Diesel Back- Dirty contacts Backup equipment None Cleaned contacts None required up Equipment Timers timers did not i
operate 2B Emergency Diesel Loose load gain Lead oscil- None The load gain potentio=eter None reqnired Genirator potentiometer lations locking mechanism was applied locking mechanism
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,e EFFECT SPECIAL PRECAUTIONS
- j', SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE
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OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY .
COMPONENT OPERATION REPETITION DURING REPAIR n CAUSE RESULT .
- h Containment Sediment accumu- Flov restrict- None Cleaned all tubes and plugged None required Rscirculation Fan lation and ion and leaking tubes Coolcr erosion leakage "A" Control Air Particulate Sticky valve None Cleaned and lubricated valve- None required Drysr 4-Way Valve matter inside internals valve 4
Wacto Gas Sphere Age Leaking None Installed new diaphragm None required a diaphragm "A* Service Water Shaft mis- Vibration None Realigned pump to motor None required c Pump alignment Prsesurizer Spray Faulty air Valve would None ' Replaced regulator None required
,_ Valva 574 regulator not open U Neutron Flux Monitor- Failed detector Erroneous None Replaced detector None required
,e ing System readings
' Letdown ADV-20h Boric acid Valve would not None Valve cleaned and repacked. None required leakage / close Valve vill be inspected and deposits operationally checked at
. increased frequencies . >
Steam Generator #1 Unknown Primary to None Plugged one tube Plant cold shutdown
! secondary tube leakage I
- i. Purification System Valve over- Torn diaphragm Unplanned The valve diaphragm was replaced. None required j Valva 269 torqued release . A mechanical stopping device
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of radio- vill be added to the valve.
active gas
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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, pursusat to the requirements of IOCFR Part 50, Section 50.59 (b) of the Commission's regulations:
Plant Design Change #88 entitled, " Hot Water Supply Line Extension" was completed. This change provides a supply of hot water at the chemical feed station where dry chemicals must be dissolved and added to the feedvater system.
The safety evaluation concluded that the change does not present any significant hazardous condition not described nor implied in the FDSA based upon the following:
- 1. The hot water system is not a safety related item and vill not affect the remainder of the system.
- 2. The hot water is being added to the un-modified feedvater system and the quantity used (% 10 gallons) is negligible when compared to the volume of f eedvater in the system. Therefore, the small amount of untreated hot water vill have no detectable effect on the treated feedwater.
Plant Design Change #89 entitled " Installation of Ammeters on Power Supplies to Containment Air Compressors" was completed. This change provides a means of remote monitoring of the operation of these units.' The safety evaluation concluded that the implementation of this change in no way affects the safety of the plant. It is judged to be good engineering practice and vill be an operator aid.
Plant Design Change #95 entitled " Service Air to Control Air System Cross-Connection Filter" was completed curing the report period.
The two air systems were incompatible in that the service air does not meet the oil free requirements of the control air system. The installation of this filter provides the oil free air required. The safety evaluation concluded that the probability of occurrence or the consequences of an accident or equipment malfunction are not increased by this change. The possibility of a different type of accident or malfunction is not created and the margin of safety is not reduced.
The change represents sound engineering judgement and vill increase plant reliability.
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Plant Design Change #97 entitled " Automatic Opening of FM-MOV-30 On Low Service Water Pressure" was completed during the report period. The safety evaluation concluded that the change would not result in the degradation of the engineering design, nor is it an unreviewed safety item. By making this valve operate automatically rather than relying on an operator, it will increase the margin of safety as well as reduce the possibility of damage to the turbine on loss of station service AC power.
Plant Design Change #116.1 entitled " Relocation of North Fire Header" was completed during the report period. This relocation of the north fire main is necessitated by construction of the new radwaste building. The safety evaluation concluded the following:
- 1. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FDSA is not increased.
- 2. A possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis is not created.
- 3. The margin of safety as defined in the basis for any technical specification is not reduced.
Plant Design Change #117 entitled " Turbine Building Sprinkler System Extension" was completed during the report period. The added sprinkler system will protect the area beneath the main generator, a previously unprotected area. The safety evaluation concluded that the safety related systems are not affected by this change. The change has no affect on the operation of nuclear safety equipment nor upon the consequences of an accident. The system cannot affect the probability of the incidence of a nuclear accident, inasmuch as the proposed system is completely isolated from nuclear systems. Also the installation and/or the operation of the sprinkler system cannot create the possibility of an accident or malfunction not previously evaluated.
Plant Design Change #122 entitled " Upgrading of Feedwater Control Solenoid Valve Circuit" was completed during the report period. Before the change was made, certain types of solenoid failures could result in tripping the supply circuit breaker which would cause the remaining solenoid to also loose power, resulting in a plant trip. The addition of an indicating fuse for each solenoid would allow the fuse to blow instead of the circuit breaker tripping. Power would not be interrupted to the other solenoid valve thus the plant would not trip. The failed solenoid
. and fuse would then be replaced. The. safety evaluation concluded that the safety and reliability of the plant will be increased with the addition of an indicating fuse for each solenoid on the feedwater control valve. The evaluation further concluded that the change is not an unreviewed safety item because the probability of an accident previously evaluated will not be increased, and the possibility for an accident of a different type than any previously evaluated will not be created.
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. " Plant D2 sign Change #123 entitled " Freeze Protection For Containment Purge Exhause Line" was completed during the report period.
This change provides a method of draining water from the return purge line and prevents water freezing in the bypass and isolation valves.
The safety evaluation concluded that the change does not increase the probability of occurrence and the consequences of an accident or equipment malfunction. The possibility for a different type of accident other than that previously analyzed does not exist and the margin of safety is not reduced. The change will increase plant reliability representing good engineering practice.
Plant Design Change #128 entitled " Test Panel For Partial Loss of A.C. Coincident With Core Cooling" was completed during the report period. This change provides a neat, orderly central panel for a test which occurs annually. The change vill accomplish both a reduction in the overall ti=e required to perform the tests and will ensure a better method of connecting test instruments to their information source. The safety evaluation concluded that the addition does not constitute an unreviewed safety item.
I Plant Design Change #129 entitled "T-Cold Interlock Circuit Isolation Between Indication and Control" was completed during the report period. This change stops the interaction between the indication portion and the control portion of the circuit. The safety evaluation concluded that the change does not constitute an unreviewed safety item. The design reflects goed engineering practice and should result in improved operational reliability.
Plant Desisrn Change #137 entitled " Temporary Replacement of CD-LCV-1312A" was completed during the report period. The change permits continued plant operation while the heater drains tank normal level control valve is repaired or replaced. The safety evaluation concluded that the procaoliity of occurrence and the consequences of an accident or equipment malfunction are not increased by this plant design change. The possibility for a different type of accident other than that previously evaluated does not exist and the margin of safety is not reduced. This change represents sound engineering judgement and will increase plant reliability.
Plant Design Change #138 entitled " Diesel Generator Day Tanks Overflow Protection" was completed within the report period. The change involves the addition of diesel day tank high level alarms, the extension of the day tank vent through the vall to tie into the underground tank vents ,
and replacement of the fuel transfer pump manual switch with a spring " return to off" type switch. These changes will prevent overfilling the day tanks and overflowing to the diesel generator room floor. The safety evaluation concluded that the probability of occurrence and the consequences of an accident or equipment malfunction are not increased by this plant design change. The possibility for a different type of accident other than that previously evaluated does not exist. The evaluation further concluded that the marjor of safety is not reduced and the change represente sound engineering judgement.
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& REPORT OF RADIOACTIVE EFFUENTS I
racility: Connecticut Yankee Atomie Power company ~
Docket: 50-21)
- Year: 1211 6 Month Summary .
Jan. - July I. LIQUID RELEASES I*
Unita Jan. Feb. Mar. Anr. Mar June July Aug. Sept. Oct. Nov. Dec. Total
- 1. Cross radioactivity (8.y) a) Total release curies b) Avg. concentration 5.t7 (-1 )
e released uCi/m1 f;;1o c) Max. concentration 1.65 (-9) released uCi/ml
- 2. Tritium 8.Bk (-8) a) Total release Curies b) Avg. concentration 1.05 (3)
I released uC1/mi *
- 3. Dissolved noble rases 2.95 (-6) a) Total relesse Curies 1.10
+ b) Avg. concentration e
released uct/ml
- k. Gross alpha radio- 3.31 (-9) activity .
i a) Total release Curies b) Avg. Concentration 1.65 t-3) released pCi/ml L . 6L (-12)
!$ t 5. Volume of liquid vaste i
? I to discharge canal Lit er's
- 8* 6. Volume of dilution water Liters 2.15 CT)
- 6. ,7. Isotopes released Curies i
I 3.56 fil) l y 87
[ I-133 - 1.33 (-2 i I-131 - 1.k9 (-11 Xe-133 k.93 (-2)
I Xe-135 8 1.11 i '
k.62 f-2 i Cs-137 Ce-1kk 6.63 f-2' t Co-60 5.93 i -21 i
Co-55 i 1. Dk ' -l' t Cr-51 6 9.ec E-2 t 6 1.66 i-2 i Mn-Sk i 2.56 (-2i Ru-103
) i 1.20 (-2)
Sr-90 6 1.32 (-A)
Sr-89 '
6 3.11 (-5)
Unidentified 7.03 (-3)
- 5. Percent of tech, spec. i limit for total activity released ** -
_ 1.6L (-1)
- Except tritium and dissolved gases ** Based upon annual projected available dilution water 6
+
-_m - -
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a II. AIRBCRNE REI. EASES Units Jan. I Feb. I Mar. l Apr .l. May I June Jul v Aug. Sert. Oct. Nov. Dec. Total
- 1. Total noble n ses curies 1.21 (1)
- 2. Total haleren, cCuries 6.70 ( h)
- 3. Total particulate Gross radioactivity (s.v) Curies * .
1.84 (-2) h, "otal tritium C Tu ies 5.01
- 5. Total particulate gross alpha radio-retivity Curies *NDA
' 6. Maxinus actle gas r lease rate uC1/sec. 1.28 (2)
- 7. Percent of applicable limit for: "
, n) *:oble nses 5 1.09 (-2) b) Falosens E 7.20 ( 4)
I e) Particulates % 1.69 (-3)
W d) Tritium 1.76 (-4 )
- *8. 1sotore releases: curies 6 I P rticulates i C3 i 2 60 (-2)
Bu ta-ik0 !
Sr-90 t Cs-135 i 7,8p (_3)
Rb-83 i Unidentified i 1.39 (-3)
H-legens !
I-131 i ! l 6.18 ( L)
I-133 , 8 I 2.52 ( h)
I-135 3 i Gases i Kr-85 i 1.20 Xe-133 i 8.30 Kr-53 l 3 5.26 (-1) i Kr-67 l 1.50 (-1)
I Kr t Xe-135 i i f Xe-135m i ! 7.26 (-1)
Xe-135 11.33 Ar-k1 43.37 f-2)
M-J i i i1.i.1 (-1)
'EA = No detectable activity " Based upon annual projected available dilution air i
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SOLID WASTE SHIPMENTS i
SIX MONTH REPORT 1
l January 1, 1973 - July 1, 1973 l
l Volume Curie I Date Material Ft3 Content Disposition ,
t 1-10-73 3 Solidfied Filters 22 83 Ci Offsite Burial i in Drtan
- h-3-73 127 Drums Compacted 958.2 0.kob Ci !
Waste
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h-24-73 14 Drums Solidfied 103 2 913 Ci Filters & Waste TOTALS 1083.2 86.31T i
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1 i ENVIRONMENTAL MONITORING
- 1 J
j The sumary environmental monitoring report has been distributed i separately.
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OCCUPATIONAL PERSONNEL RADIATION EXPOSURE Jan 1, 1973 - July 1, 1973 EXPOSURE INCREMENTS NO. OF PERSONNEL less than 100 mrem 333 100 mrem to 500 mrem 29 500 mrem to 1250 mrem 35 1250 mrem to 2500 mrem 11 over 2500 1 NUMBER OF PERSONNEL RECEVING OVER 500 MREM AND CONSITIONS
- 1. Routine Plant Surveillance and Inspection Operator surveillance 8 Sample collection / analysis , health physics surveys L
- 2. Routine Plant Maintenance Instrument calibration 2
- 3. Special Plant Maintenance Inspection of steam generator 6 Preparation of steam generator for repair 3 Steam generator tube plugging 3 Nuclear instrumentation detector repair 2 Refueling canal gate installation 5 Steam generator manway removal / replacement 14*
- These lh individuals were also involved in routine plant maintenance throughout the report period.
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