ML19284B311

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Semiannual Operating Rept,Jan-June 1975
ML19284B311
Person / Time
Site: Yankee Rowe
Issue date: 06/30/1975
From:
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19284B310 List:
References
FOIA-92-403 NUDOCS 8011100258
Download: ML19284B311 (52)
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Text

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e s YANKEE 1%JWE SEMIA'OUAL REPORP l-1-75 TO 6-30-75 I OPEPATION SUWARY

s I g GENERAL The Yankee Atomic Electric Company Plant at Rowe, Massachusetts operated at power throughout the reporting period. Brief shutdowns and load reductions observed during this period are described in the Operations chronology. A. Changes in Facility Design 1. The following changes requiring authorization frcm the Commission were made: None 2. The following changes not requiring Commission approval were made: a. PDCR 73-5, Waste Liquid Feed to Evaporator and Overhead and Overhead Condenser Vent Interlock, was completed during the report period. Three air operated valves were installed in series with and downstream of Class I & II feed valves WD-726 and WD-755 and the overhead condenser vent valve VD-V-683. A fourth air operated valve was installed in series with and upstream of the overhead condenser vent valve WD-739. This change was made to prevent the release of radioactive gas via the primary vent stack while processing Class I liquids. This change does not impose any unreviewed safety question in that the system will operate in the same manner as covered in the existing safety analysis report. b. PDCR-73-22, Piping Changes to the Evaporator Overhead Condenser, was completed during the report period. The Nylobraid hose on the drain line of the overhead condenser vent to the primary vent stack was removed. A Jerguson sight flow indicator was placed on the vent line of the overhead "ent condenser and was piped to the distillate pump suction. Iso a moisture separator was installed in the Class II Liquid vent line. This change was made to allow safer and more efficient handling of liquid waste. This change does not impose any unreviewed safety question in that the system has been upgraded and will function as designed and covered in the existing safety analysis report. c. PDCR 73-16, Change to Main Coolant Check Valve Internals, was completed during the reporting period. The wear points of the spare clapper assemblies for the main coolant check valves were replaced with wear resistant ones. This change was made to provide longer life for the internals and subsequently decrease the maintenance frequency for their replacements. ! ~l s T --

B. Performance Characteristics None C. Changes in Operating Proceduree 1. The following Operating Procedures were prepared or changed as necessitated in I.A.2. (a & b). OP-2380, Operation of the Waste Disposal Evaporator System 2. The following Operating Procedures were prepared or changed as necessitated by an analysis of plant performance characteristics described in I.B. above. None 3. The following Operating Procedures were prepared or changed to improve the safety of plant operations. OP-2159 Removal of H Blanket from the LPST 2 OP-2475 Vapor Container Access OP-5926 Maintenance of the V.C. Air Cooler Fans & Post Accident H2 Control System Fans OP-6154 Maintenance of the Nuclear Instrumentation OP-4500 Weekly Check of the Station Batteries AP-0018 Bypass of Safety Function and Jumper Control AP-0202 Engineering Design Changes AP-0402 Support from Offsite Security Forces OP-2102 Turbine Startup OP-2105 Plant Cooldown from Hot Shutdown with the Maine Condenser in Service OP-2106 Plant Cooldown from Hot Shutdown with the Maine Condenser Out of Service OP-2107 Changing Generator Load OP-2110 Operator's Bomb Search OP-2111 Supervisor's Standard Search Procedure OP-2112 Operator's VC Bomb Search Procedure OP-3718 Thrust Bearing Pre-Trip OP-3719 Turbine Trip Low Vacuum Alarm

OP-3738 No. 1 Nozzle Low Pressure OP-3739 VC H Filter High Temperature 2 OP-3749 Nitrogen Supply Low Pressure OP-3750 LPSI Accumulator High-Low Pressure OP-3753 Battery No.1, 2 or 3 Voltage Low OP-4230 Steam Generator Safety Valve Tests with the Plant in Hot Standby 0P-4601 NI Surveillance Check OP-4700 VC Continuous Leak Rate Monitoring OP-4801 Calibration Check of the Process Radiation Monitoring System AP-5000 Maintenance Department Surveillance Schedule OP-5107 Inspection and Adjustment of Pipe Hangers AP-6003 I&C Department Maintenance Program OP-6351 BAMT Level Transmitter Recorder Calibration AP-7003 VC Class B&C Penetration Test Guideline OP-3689 Boiler Feed Pump Suction Low Pressure Auto Trip OP-3714 Turbine Stop Valve Solenoid Trip OP-3735 VC Drain Tank High Level OP-3686 Steam Generator Hi/ Low Level 0P-3687 Service Water Low Pressure Auto Start OP-6360 Calibration & Maintenance of the Vari-Orifice Valve Control System AP-7104 Core XI Operational Limits OP-8200 Contamination Containment Limits AP-0211 Material & Service Purchase AP-0403 Security Responsibilities of Plant Personnel OP-9237 Determination of Gross Gamma Radioactivity OP-6605 Installation and Operation of the Temporary Loop Seal Radiation Monitor Channel 0P-6560 Calibraton of Waste Liquid Effluent Flow Channel, FT-301, FRC-301, and FRCV-301

OP-6559 Calibration of the Loop Seal Inlet High Level Switch (HLS-313) OP-6267 Calibration of the Boiler Feed Pump Suction Header Pressure Switch PS-415 OP-6266 Calibration of the Boiler Feed Pump Discharge Header Pressure Switch PS-405 OP-6261 Calibration of Differential Standatrol No. OP-6257 Bailey Narrow Range Level C,mpensating Relay Calibration OP-6200 TcWR Channel Calibration OP-4520 Safety Injection Loop Flow Instrument Calibration, Loop No. OP-4614 Safety Injection Accumulator Pressure Instrument Calibration OP-4208 Flow Test of Two (2) LPSI fumps on Normal AC Power OP-4201 Power Range Channel Calibration OP-2108 Routine Power Operation AP-0404 Emergency Security Procedures AP-0400 General Organization of Security AP-0223 Document Control AP-0001 Plant Procedures AP-0205 Maintenance Request AP-0214 Installation & Maintenance of Safety Classified Systems, Components, or Structures OP-1221 Movement of Reactor Core Components Within the Spent Fuel Pit OP-6563 Calibration of the Waste Gas High Pressure Switch HPS-303 AP-7104 Core XI Operational Limits AP-7105 Normal Operation of the Incore Flux Mapping System AP-7303 Burn-Up OP-8416 Radiation Exposures by Duty Function

k AP-9009 Calibration Schedule for Chemistry Laboratory Instruments OP-9114 Decontamination of a Reactor Coolant Pump OP-2109 Three Loop Operation OP-2120 System / Component Preparation for Inspection / Maintenance & Return to Service OP-2151 Boric Acid Addition to the Main Coolant System OP-2166 Operation of the Neutron Shield Tank OP-2176 Charging Line Removal from Service for Maintenance of Drain & Relief Valve OP-2479 Vapor Container Atmosphere Control System Charging OP-3120 Loss of Flux Indication OP-3311 Emergency Environmental Sample Collection OP-3622 Neutron Shield Tank High Temperature / Vapor Container High Pressure OP-3643 Vapor Container High Pressure Trip OP-3701 Reduced Control Air header & Control Air Header Low Pressure OP-3708 Battery Chargers Auto Trip OP-3766 Loop Seal Outlet, High or Low Level OP-4220 Primary System Water Balance OP-4225 Throttle Valve Surveillance Test OP-4501 Bi-Monthly Check of the Station Batteries OP-4Eil Inspection of Main Coolant Loop Pipe Hangers AP-4900 Chemistry Surveillance Tests OP-5102 Replacement of Fiange Gaskets or Safety Related Equipment OP-5105 Freeze Sealing OP-5202 Replacement of Pressurizer Heater Bundles OP-5214 Inspection, Gaging and Parkerizing Reactor Head Studs OP-5215 Dismantling of Driveshafts and Dashpots for Inspection

OP-5756 Inspection & Maintenance of Safety Related Motor No. OP-5760 Repair of Damaged Control or Power Cables OP-5925 Maintenance of thc Vapor Container Personnel Lock OP-5952 Inspection & Maintenance of the Turbine Hall or Yard Crane AP-6006 Initial and Review Qualification Training of I&C Personnel OP-6101 Nuclear Instrumentation & Reactor Protection System Precritical Check OP-6152 Installation & Testing of Source, Intermediate & Power Range Detectors & Cable OP-6153 Operation of the In-Core Flux Mapping System OP-6155 Operation of the Nuclear Instrumentation OP-6210 Maintenance of the Primary Plant Instrumentation 0F-6211 Calibration of the Charging & Volume Pump Speed Control System OP-6252 Bailey Main Steam Flow Compensating Relay Calibration OP-6258 Steam Flow / Water Flow Ratio Relay No. Calibration OP-6262 Calibration & Maintenance of Steam Bypass Valve (PC-V-402) and Controls OP-6268 Calibration of Boiler Feed Pump No. Minimum Flow Instrumentation OP-6363 Calibration & Maintenance of Purification Flow Controller FIC-202 OP-6555 Calibration of Waste Gas High Pressure Switch HPS-301 OP-6558 Calibration of Loop Seal Outlet High & Low Level Alarm Switches HLS-310 and LLS-310 OP-6561 Calibration of Knockout Drum (TK-35) Pressure Channel PT-302, PP.C-302, PRCV-302 OP-6562 Calibration of Waste Gas Compressor Discharge Cooler Pressure Channel PT-303, PRC-303, PRCV-303 AP-0200 Plant Design Changes AP-0201 Plant Modifications AP-0211 Material & Service Purchase

AP-0212 Material Receipt AP-0215 Control of Measuring & Test Equipment AP-0221 Qualit.v Assurance Records AP-0501 General Plant Training AP-2005 Operations Dept. Surveillance Schedule During Power Operations AP-8014 Respiratory Protection Quality Assurance Program for New Equipment AP-8015 MPC Hour Accountability 0P-8100 Establishing & Posting Controlled Areas OP-8101 Plant Radiological Surveys OP-8103 Surface Contamination Swipe Surveys OP-8105 Breathing Zone Air Samples OP-8302 Health Physics Release of Equipment & Material AP-9000 Training of Chemistry & Health Physics Dept. Personnel AP-9003 Chemistry Instructions, Reports and Records OP-9102 Quality Control Checks of Laboratory Counting Equipment OP-9220 Determination of Gross Beta Radioactivity OP-9221 Main Coolant Gaseous Radionuclide Analysis & Gaseous E Determination AP-0001 Plant Procedures AP-0019 Issuance of Press Releases Concerning Plant Operation AP-0213 Material Identification & Control AP-0600 Initial & Review Qualification Training for Stores Personnel AP-2000 Recall of Off-Duty Personnel OP-2119 Preparation for Maintenance and/or Inspection and Return to Service of Unisolable Maine Coolant System Components 0P-8420 Respirator Issuance, Field Testing, & Wearing

OP-2113 Operation of the Reactor Control Rod System OP-2115 Warm or Cold Weather Operation OP-2141 Idling a Main Coolant Loop et Power Due to a MCP Trouble OP-2153 Boric Acid Control 0P-2161 Primary Plant Corrosion Control System 0P-2178 Diaphr gm Valve Repairs OP-2179 Venting LPST Cover Gases OP-2250 Feedwater Line Isolation & Return to Service to Affect Repairs on Feedwater Line Components OP-2375 Liquid Transfer from the LPST OP-2379 Releasing a Test Tank OP-2381 Concentrating & Drumming Evaporator Bottoms OP-2382 Solid Noncombustible Waste Disposal 0P-2383 Burning of Solid Combustible Waste OP-2384 Disposal of Incinerator Ash OP-2385 Operation of the Waste Gas System OP-2386 Releasing Radioactive Waste Gas from the WGSD to Atmosphere OP-2476 Establishing & Maintaining Normal VC Pressure OP-2477 Operation of the VC Heating & Cooling System OP-2502 Operation of the 120 VAC Vital Bus System OP-2503 Operation of the 125 VDC System OP-2504 Operation of the Station Power System O P-2650 SI Accumulator Makeup OP-2653 Removal of the SI System from Service OP-2654 SI Tank Makeup OP-2707 Operation of the Fire Protection System OP-3000 Emergency Shutdown from Power OP-3003 Emergency Controlled Plant Load Reduction or Shutdown With or Without Cooldown OP-3004 Plant Action in the Event of a Bomb Threat OP-3005 Plant Action in Event of an Earthquake OP-3007 Loss of VC Integrity OP-3009 Loss of Service Water OP-30l l Oil Spill Incident OP-3013 Loss of Supervisory Light Indication

OP-3100 Fuel Cladding Failure OP-3106 Total Loss of Main Coolant OP-3107 Large or Partial Loss of Main Coolant OP-3111 Malfunction of Primary Pressure or Level Channels OP-3250 Loss of 120 VAC Vital BLs OP-3253 Isolation of Vital Bus Feeder Trouble OP-3307 Emergency Training Exercise OP-3601 SI Check Valve Leak OP-3602 Charging Purp Low Oil Pressure OP-3606 Component Cooling MCP Low Flow OP-3610 Waste Disposal 0P-3618 Loop Fill Line High-Low Pressure OP-3628 Fuel Transfer Pit Level 0P-3632 MCP High Temperature OP-3636 Radiation Monitoring OP-3637 LPST Makeup Pumps Discharge Header Low Pressure OD-3638 LPST Safety Valve Discharge Line High Pressure OP-3639 LPST High Temperature OP-3640 LPST High Pressure OP-3641 LPST Level OP-3642 Cam Motors Loss of Voltage OP-3649 Charging Pump Auto Start OP-3650 Purification Pump Discharge Header Low Pressure Auto Start OP-3651 B. A. Mix Tank Minimum Level 0P-3656 Z-126 Auto Trip OP-3657 Y-177 Auto Trip OP-3667 Generator Ground OP-3668 Unit Differential 0P-3669 Generator Differential 0?- 3670 Generator Loss of Field & Overload OP-3671 Generator Low Field OP-3681 Z-126 Stuck Breaker OP-3682 Y-177 Stuck Breaker OP-3688 Boiler Feed Pump Low Pressure Auto Start OP-3705 D.G. Building Floor Drain Sump Tank High Level OP-3717 Turbine Trip L,w Bearing Oil

OP-2109 Three Loop Operation OP-2120 System /Conponent Preparation for Inspection / Maintenance & Return to Service OP-2151 Boric Acid Addition to the Main Coolant System OP-2166 Operation of the Neutron Shield Tank OP-2176 Charging Line Removal from Service for flaintenance of Drain & Relief Valve OP-2479 Vapor Container Atmosphere Control System Charging OP-3120 Loss of Flux Indication OP-3311 Emergency Environmental Sample Collection OP-3622 Neutron Shield Tank High Temperature / Vapor Container High Pressure OP-3643 Vapor Container High Pressure Trip OP-3701 Reduced Control Air Header & Control Air Header Low Pressure OP-3708 Battery Chargers Auto Trip OP-3766 Loop Seal Outlet, High or Low Level 0P-4220 Primary System Water Balance OP-4225 Throttle Valve Surveillance Test OP-4501 Bi-Monthly Check of the Station Batteries OP-4513 Inspection of Main Coolant Loop Pipe Hangers AP-4900 chemistry Surveillance Tests OP-5102 Peplacement of Flange Gaskets or Safety Related E qui pmen t OP-5105 Freeze Sealing OP-5202 Replacement of Pressurizer Heater Bundles OP-5214 Inspection, Gaging and Parkerizing Reactor Head Studs OP-5215 Dismantling of Driveshafts and Dashpots for Inspection OP-5756 Inspection & Maintenance of Safety Related Motor No.

OP-5760 Repair of Damaged Control or Power Cables OP-5925 Maintenance of the Vapor Container Personnel Lock OP-5952 Inspection & Maintenance of the Turbine Hall or Yard Crane AP-6006 Initial and Review Qualification Training of I&C Personnel OP-6101 Nuclear Instrumentation & Reactor Protection System Precritical Check OP-6152 Installation & Testing of Source, Intermediate & Power Range Detectors & Cable OP-6153 Operation of the In-Core Flux Mapping System OP-6155 Operation of the Nuclear Instrumentation OP-6210 Maintenance of the Primary Plant Instrunentation OP-6211 Calibration of the Charging & Volune Pump Speed Control System OP-6252 Bailey Main Steam Flow Compensating Relay Calibration OP-6258 Steam Flow / Water Flow Ratio Relay No. Calibration OP-6262 Calibration & Maintenance of Steam Bypass Valve (PC-V-402) and Controls OP-6268 Calibration of Boiler Feed Pump No. Minimum Flow Ins trume ntation OP-6363 Calibration & Maintenance of Purification Flow Controller FIC-202 OP-6555 Calibration of Waste Gas High Pressure Switch HPS-301 OP-6558 Calibration of Loop Seal Outlet High & Low Level I.larm Switches HLS-310 and LLS-310 OP-6561 Calibration of Knockout Drum (TK-35) Pressure Channel PT-302, PRC-302, PRCV-302 OP-6562 Calibration of Waste Gas Compressor Discharge Cooler Pressure Channel PT-303, PRC-303, PRCV-303

OP-2101 Plant Startup from Hot Standby or Hot Shutdown OP-2102 Turbine Startup OP-2104 Scheduled Plant Shutdown to Hot Standby or Hot Shutdown OP-2113 Operation of the Reactor Control Rod System OP-2141 Idling a Main Coolant Loop at Power Due to a Main Coolant Pump Trouble OP-2153 Boric Acid Control OP-2154 Operation of the Purification System OP-2163 Startup of the Purification System OP-2251 Hydrostatic Testing of Steam Generator & Lines OP-2255 Operation of the Feedwater System OP-2383 Burning of Solid Combustible Waste OP-2650 Safety Injection Accumulator Makeup OP-2652 Preparation of the Safety Injection System for Normal Operation OP-2703 Chemical Cleaning of the Component Cooling Heat Exchangers by an Outside Contractor OP-2705 Operation of the Service Water System OP-3103 Partial or Total Loss of Main Coolant Flow OP-3106 Total Lo',s of Main Coolant OP-3200 Steam Generator High-Low Level OP-3312 Emergency On-Site Medical Procedure OP-3706 Steam Condensate High Conductivity OP-4201 Paaer Range Channel Calibration OP-4202 Control Rod Operability Check OP-4204 Monthly Test of Safety Injection Pumps OP-4207 Periodic Testing of Emergency Diesel Generators OP-4211 Emergency Boiler Feed Pump Surveillance Test

f OP-4212 Monthly V.C. Recirculation System Valve Exercise OP-4506 Inspection of ECCS Circuit Breaker No. OP-4516 Charging Line Inspection OP-4631 Waste Gas Instrumentation Leak Test OP-4702 Vapor Containment Type B & C Penetration Tests OP-4800 Operational Check of Accident - Emergency Environ-mental Monitors (MAP-1) OP-4812 Calibration Check of Gamma Guards AP-5003 Maintenance Department Unanticipated Corrective Maintenance AP-5004 Control of Maintenance Department Measuring & Test Equipment OP-5103 Inspection and Ma.: :tenance of Safety Relief Valve No. OP-5104 Safety Related Valve Maintenance OP-5203 Main Coolant Pump No. Removal and Handling for Maintenance OP 5205 Main Coolant Pump No. Reinstallation After Maintenance OP-5207 Maintenance of Pressurizer Solenoid Operated Relief Valve OP-5208 Installation of a Control Rod Drive Mechanism OP-5209 Maintenance of Pressurizer Code Safety Valves OP-5211 Repair of Control Rod Drive Mechanism No. OP-5216 Inspection, Assembly, Adjustment and Testing of Drive Shaft & Dash Pot OP-5257 Maintenance of the Purification Pump No. OP-5258 Maintenance of the Shutdown Cooling Pumps and LPST Cooling Pump OP-5262 Charging Pump Maintenance OP-5263 No. 2 Charging Pump Service OP-5350 Inspection and/or Maintenance of the Diesel Generator System No.

a 2 s OP-5351 Maintenance of HPSI Pumps OP-5352 Maintenance of LPSI Punps OP-5454 Inspection of Steam Generator Feed Line Check Valves OP-5456 fiaintenance of the Emergency Boiler Feed Pump and Turbine Driver OP-5755 Inspection & Maintenance of ACB and/or Contactor No. OP-5758 Maintenance of the Vital Bus Inverter & Control Cubicle OP-5951 Inspection & Maintenance of the V.C. Polar Crane OP-6000.40 Special Test Core Vibration Monitoring Using Nuclear Instrumentation - Intermediate Power Range Detectors AP-6002 Control of Instrument & Controls Dept. Measuring and Test Equipment OP-6102 Reactor Servo Control System Pre-Startup Check OP-6156 Obtaining Control Rod Drive Coil Voltage and/or Current Traces OP-6204 Bailey Pressurizer Pressure Channel Calibration OP-6269 Calibration of Moisture Separator High Level Switches HLS-414A, 414B, 415A and 415B OP-6361 Calibration & Maintenance of Temperature Controller TC-204, PS-236 and PS-237 OP-6362 Calibration & Maintenance of Pressure Controller PC-223 OP-6364 Calibration of Purification Back Pressure Controller PC-205 and PCV-205 OP-6365 Calibration Check of Neutron Shield Surge Tank Level Switches HLS-223, LLS-224, LLS-229 and HLS-230 OP-6554 Calibration of Waste Gas Low Pressure Switch LPS-301 OP-6556 Calibration of Waste Gas Low Pressure Switch LPS-302 OP-6557 Calibration of Waste Gas High Pressure Switch HPS-302 AP-7301 Temperature Map F RP OP-8G12 Respiratory Protection Training AP-8013 Respirator Fitting

4 OP-2132 Cooldown of an Individual Main Coolant Loop OP-2152 Boric Acid Addition to an Isolated Loop OP-2658 Operation of the Post Accident Vapor Containaent Hydrogen Control System OP-2659 Post Accident Vapor Container Vent System Hydrogen Analyzer Operation OP-2703 Chemi cal Cleaning of the Component Cooling Heat Exchangers by an Outside Contractor OP-3201 Major Rupture of a Main Steam Line OP-3251 Loss of A.C. Supply 0P-3310 Release of Public Information During Site & General Emergencies OP-4206 Flow Test of Two HPSI Punps on Normal A.C. Power OP-4209 Emergency Diesel Generator Test During Refueling Intervals - Emergency Diesel No. OP-4235 Pressurizer Solenoid Relief Valve Te;t (PR-S0V-90) OP-4701 Vapor Container Class "A" Leakage Test OP-4802 Environmental Sampling AP-5005 Standard Welding & Inspection Procedure OP-5100 Valve, Fitting, or Pipe Section Replacement and/or Repai r OP-5200 Main Coolant Check Valve No. Repai r OP-5204 Main Coolant Pump No. Inspection & Repair OP-5206 Inspection & Testing of Pressurizer Heaters OP-5402 Turbine Throttle Valve Maintenance OP-5761 Maintenance of Vapor Container Electrical Penetrations AP-6000 I&C Department Work Log OP-6451 Calibration of the SI Tank High & Low Level Alarm Switches (HLS-219/LLS-220)

OP-9239 Fluoride Determination D. All Surveillance Tests and Inspections required by the Technical Specifications were satisfactorily completed during the report period with the following exceptions: See attached Table 1.D. E. Containment Leak Test 1. The vapor Container Continuous Leak Rate monitoring for the surveillance period ending 2/21/75 is satisfactory. 2. The Vapor Container Continuous Leak Rate monitoring for the surveillance period ending 4/22/75 is satisfactory. 3. The Vapor Container Continuous Leak Rate monitoring for the surveillance period ending 5/20/75 was completed. 4. The Vapor Container Continuous Leak Rate surveillance monitoring is in progress at the end of the reporting period. 5. The following Class "B" test was performed during the report period: On April 17, 1975 the V.C. Personnel Hatch was tested in accordance with attachment "W" of the procedure OP-4702, " Vapor Container Class B & C Penetration Tests". 6. The following Class "C" test was performed during the report period: a. On March 20, 1975 the Main Coolant Drain Isolation Trip valve, TV-202 was tested according to attachment "M" of the procedure OP-4702, " Vapor Container Class B & C Penetration Tests". The line upstream of the trip valve was pressurized to normal main coolant pressure and the amount of leakage past the trip valve was collected and measured over a 30 minute time period. The leakage was <100 cc/hr which satisfies the criterion of the nominal leakage rate. b. On February ll,1975 the Service Air Supply Isolation Valve to the V.C., CAV-688, was tested according to attachment "B" of the proceaure OP-4702, " Vapor Container Class B & C Penetration Tests". Using the pressure decay method, a leak rate of <.2 psig/ min was determined from a starting pressure of 32 psig. This satisfied the criterion of the nominal leakage rate. c. On February 11, 1975 the Fuel Chute Lower Lock Valve was tested according to attachment "D" of the procedure OP-4702, " Vapor Container Class B & C Penetration Tests". Using the pressure decay method, a leak rate of <3 psig/5 min

was determined from a starting pressure of 32 psig. This satisfies the criterion of the nominal leakage rate. d. On February 11, 1975 the Fuel Chute Pump-Back System Valves CV-216 and HCV-215 were tested according to attachment "E" of the procedure OP-4702, " Vapor Container Class B & C Penetration Tests". Using the pressure decay method, a leak rate of <.2 psig/ min. was determined from a starting pressure of 32 psig. This satisfies the criterion of the nominal leakage rate. F. Tests and Experiments 1. The following tests or experiments requiring authorization from the Commission were performed: None. 2. The following tests or experiments not requiring authorization from the Commission were performed: None. G. The following plant key staff changes were made during the report period: None.

h SURVEILLANCE TESTS AND Ih ICTIONS DISCREPANCIES TABLE 1.D DATE TEST DESCRIPTION DISCREPANCY AOR NO. RESOLUTION 1/20/15 Radiation Monitoring System Calibration Unit inoperative The Calibration unit of the Functional Check system was repaired, and the surveillance check rerun with satisfactory results. 1/21/75 Nuclear Instrument Power Range Channel 5 failed to The Intermediate Range Surveillance Check actuate the neutron flux /SUR scram Auxiliary Panel was replaced panalarm which warns the operator during the March, 1975, of a high neutron flux condition shutdown, and the surveillance prior to reaching the trip level. check rerun satisfactorily. 1/20/75 Steam Generator NR Level No. 1 & 3 Steam Generator Low Level The unit was repaired during and Trip System Alarms failed to operate. the Ma-ch, 1975, shutdown 2/19/75 and the surveillance check was rerun satisfactorily. 2/20/75 Nuclear Instrumentation Intermediate Range Channel 3 SUR Adjusted the trip points on IR Surveillance Check scram and alarm were out of the Ch. 3 SUR Scram & Alarm and procedure limit low. Power Range Ch. 7 Level Scram to within Ch. 7 Level Scram was out of the the procedural limits. procedure limit low. 2/27/75 Calibration Check of Process Waste Gas Loop Seal and The Air The monitors were repaired Radiation Monitoring Ejector Radiation Monitor failed and calibrated. The the source calibration check. surveillance check was performed again satisfactorily 4/23/75 Calibration Check of Process No. 1 S/G monitor failed to source The monitor was repaired, Radiation Monitoring check. recalibrated and the surveillance test was rerun with satisfactory results. 5/20,21, Calibration Check of Process Main Coolant Bleed, Primary Vent The Main Coolant Bleed, 22/75 Radiation Monitoring Stack, Air Ejector, Loop Seal, and Primary Vent Stack, and Vapor V.C. Air Particulate Radiation Container Air Particulate Monitors failed to source check. Monitors were adjusted while the Air Ejector and Loop Seal monitors required electron tube replacement. All the radiatim monitors performed satisfac-torily during their retest.

YANKEE ROWE SDITANNUAL REPORT l-1-75 'IO 6-30-75 II POWER GD4ERATION

~ PONER CENERATION TABLE II Jar,aary Februarv March April Mar Jur.e TOTAL Cross Thermal Pawer Generated (.W 'i l 432,270.55 390,055.08 414,475.05 , 418,853.83 413.534*I30 404,385,910 54,102,306,500 F Cross Electrical Power Generated (MWh) 133,042.4 124,5S4.6 123,373.4 133,726.0 131,4?v,'90 128.037,900 783,139,800 humber of fleurs Reactor Critical 744 6 71 727.45 720 724.9 704.55 4,291.90 > umber of !! curs Generator en Line 744 671 720.0'- 720 716.17 ,30.05 4.271.30 set Elecirical :)ower Generated (MWh) 129,914.625 117.240.58 124,521.032 125,855.308 123,601.168 120,408,?72 741,551,035 I I

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YANKEE FOWE SE24IAWJ,% REPORT l-1-75 'IO 6-30-75 III SIUIDC&NS

PLANT SHUiDOWNS TABLE III PLANT MET 110D OF STATUS DURATION SHUTTIhG DURING DATF _. (HOU RS) CAUSE OF OUTAGE DOWN REACTOR OUTAGE CORRECTIVE ACTION 3/22/75 23.92 The plant was shutdown for scheduled Manually controlleJ Hot Shutdown tione operator training and control rod deliberate shut-Condition drop time test. down. 5/13/75 4.6 The Z-126 line was lo c due to an Trip Hot Shutdown tione electrical fault at Sherman Station Condition resulting in loss of fio. 3 Boiler Feed Pump and a low steam generator water level. 5/16/75 5.65 Low Steam Generator water level due Trip Hot Shutdown f!one to loss of. boiler feed pump on low Condition suction pressure. 5/31/75 to 21.58 The plant was shutdown for scheduled Trip Hot Shutdown tione 6/1/75 operator training. (Instrumentation Condition Test) 6/21/75 15.95 The plant was shutdown for scheduled Manually controlled Hot Shutdown fione operator licensing. deliberate shutdam Condition

YNME TOE SD11NGIL REPORT l-1-75 'IO 6-30-75 IV CORRECTIVE MAUTIEWG SUBBMY

CORRECTIVE MAINTENANCE

SUMMARY

TABLE IV I&C DEPAP.TMENT MALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE RESULT SAFE OPERATION TO PREVENT REPETITION Chemical Boric Acid Mix Defective Pilot Erratic operation None None Shutdown Tank Temperatur > Valve Controller Charging & Charging Flow Defective Fitting minute leak None None Volume Control Transmi tter Safety No. 1 Loop Bonnet insufficient-minute leak None None Injection pressure detec-ly seated. tor isolation valve Nuclear Instru-Spare Intermedi - Defective Relays Intermittent Alarm None None mentati on ate Range Aux. Action Panel Reactor Spare Sigaa Defective No 1ow alarm None None P rotection Ind./ Cont. Electronics Safety No. 4 loop flow Fitting Insufficien ;- minute leak None None Injection Transmitter & ly seated Flow Orifice Radiation Loop Seal Circuit Drift Read High on None Nona Monitoring Source ~ Check

CORRECTIVE MAINTENANCE

SUMMARY

TABLE IV I & C DEPARTMENT January 1975 MALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE RESULT SAFE OPERATION TO PREVENT REPETITION Safety Injection HLS-219 SI Ground on Switch Alarm Inoperative rione None Ins trumentation Tank High Level Alarm Radiation VC Air Particu-Pump Failed No Air Flow None None Moni toring late Monitor Through Filter Radiation VC Air Particu-Defective Vanes on Improper Air Flow None None Monitoring late Monitor Pump Through Filter Safety

  1. 1 Loop SI Fitting insufficiently Minute Leak None None Injection Flow Trans-seated mitter Safety
  2. 3 Loop SI Fitting insufficiently Minute Leak None None Injection Flow Trans-seated mitter Radiation V.C. Air Defective HV Power Incorrect None None Monitoring Particulate Supply Indication Radiation Primary Vent Electron Tube Erroneous None None Monitoring Stack Failure Reading Charging &

Charging Flow Resultant Stresses Minor leak None None Volume Control Transmitter on weld produced a through weld minute defect. defect. Radiation Bleed Line Aging Resistor Loss of Power on None None Monitoring Gamma Guard Indication

CORRECTIVE MAINTENANCE

SUMMARY

TABLE IV I&C MALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE RESULT SAFE OPERATION TO PREVENT REPETITION Radiation PAB Cubicle Defective Potenti-Ins trument Indi-Ilone None Moni tori ng Garria Guard ometer & Tubes cates low Safety Injection Flow Transmi tte r Loose Packing Minute Leak None None Loop 4,FT-SI-4 Nuclear In te nnedi a te Unknown Intermittent loss None (Replaced oanel with None Ins trumen tation Range Aux. Panel of Alarm Power spare) Reactor Steam Gen. No. Defective Alarm Loss of low alarm flone None Protecti on 3 Indicator / Uni t Alarm Unit Reactor Steam Gen. No. Defective Alarm High & Low Alarn None None Protection 1 Indicator / Light Inocerative Alarm Unit Safety Injection HPSI Discharge Loose Bolts on Minute Leak None None Flow D/P Cell HPSI Flow Transmi tter Reactor Sigma Ind. Alar i Defective Meter Unable to Non; flone Protecti on Unit for Steam Movement Calib ra te Generator NR Level Radi ati on Air Ejector Defective Detector i High on None None Moni tori ng .. rce Check

CORRECTIVE MAINTENANCE

SUMMARY

TABLE IV I&C DEPARTMENT MALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE RESULT SAFE OPERATION TO PREVENT REPETITION Sa fety No. I loop flou Bonnet insufficient minute leak None None Injection ori fice, low ly seated. side isolation valve Safety No. 3 loop Fitting insufficien t-minute leak iane None Injection flow detector ly seated. Safety No. 1 loop Fitting insufficient minute leak None None Injection pressure trans-ly seated. mitter sensing line Safety No. 2 loop flovFitting insufficient.. minute leak None None Injection transmitter & ly seated. flow orifice Safety No. 1 & 4 SI Insufficient packing minute leak None None Injection flow block compression valve Safety No. 2 SI Flow Fitting insufficient-minute leak None None Injection , Detector low ly seated. side adapter Chemical Shut-CS-V-66 3 Bonnet insufficiently minute leak None None down seated Safety No. 2 loop flow Fitting insufficient-minute leak None None Injection detector ly seated

CORRECTIVE 5!AINTENANCE SU5! MARY TABLE IV + I&C >!ALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE ? RESULT SAFE OPERATION TO PREVENT REPETITION Nuclear Spare UIC/CIC Defective cable and Erratic Operation None None Instrumentation Enclosure Detector Shutdown Cooling Flow Trans-Inadequate thread Minute leak i None Placeda thread sealant on the mitter Plug seal threads of the plug. Leaking Shutdown Cooling Flow Indica-Cracked Weld Minute leak None Cut out weld and replaced tion Sensing with 1/2" tubing and Swagelok Line fi tti ng. I Safety Injection

  1. 1 Loop SI Fitting insufficient-Minute Leak None None Flow Trans-ly seated.

mi tter Shutdown Cooling Flow Indicator Cracked Weld Minute Leak None Cut out weld and replaced with Sensing Line 1/2" tubing and Swagelok fitting. Primary Auxiliary LPST High Dirty Nozzle and Improper None None Level Fump Flapper Operation LLC-221 Shutdown Cooling Sensing line Cracked Weld Minute Leak None Cut out weld and replaced with elbow on D/P 1/2" tubing and Swagelok cell fi tti ng. l

CORRECTIVE MAINTENANCE SUM 5fARY TABLE IV fiAlf1TEi4AfiCE MALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE RESULT SAFE OPERATION TO PREVENT REPETITION Charging & flo. 2 Charging Packing Packing leak fione Tione Volume Control Pump Charging & No. 3 Chargi ng Worn Packing & Leakage fione fione Volume Control Pump Plunger Emergency Power fio. 2 Diesel Defecti ve Oil Line Slight Oil Leak fione fione Generator Vent & Drain fio. 1 Loop Th Loose Packing Gland Leakage None fione Drain Valve Vent & Drain flo. 3 Looo Th Loose Packing Gland Leakage fione fione Drain Valve Pressurizer & flarrow Range Loose Packing On Leakage ilone None Pressure Relief Level Detector Stem flut Bypass Valve Pressurizer & "T" Handle Root Loose Packing Gland Leakage flone None Pressure Relief Isolation Valve Main Coolant tio. 3 Loop Loose Packing Gland Leakage fione fione Bypass Valve Pressurizer & Hydraulic Loose Locknut on Slight Oil Leak None None Pressure Relief Suppressor Adjusting Screw on Plug

CORRECTIVE MAINTENANCE

SUMMARY

TABLE IV MAINTENANCE DEPARTMENT January 1975 MALFUNCTION EFFECT ON CORRECTIVE ACTION TAKEN SYSTEM COMPONENT CAUSE RESULT SAFE OPERATION TO PREVENT REPETITION Charging & No.1 Charging Crack in Weld in Slight Leak flone None Volume Control Pump Strainer Strainer Drain Line Charging & No. 1 Charging Bad ram and packing Excessive None None Volume Control Pump Leakage Charging & No. 3 Charging Worn packing & ram Excessive leakage None None Volume Control Pump Charging & No. 1 Charging Bad gasket on Slight leak. None None Volume Control Pump Suction suction of strainer Line cap Steam Generator Blowdown Line Weld defect Leak at nipple & None None Nipple Cap cap Vapor Container V.C. Personnel Cold Weather Lock difficult None None Penetrations Hatch Air Lock to move. Depressuriza-tion Valve Coolant No. 2 Purifi-Worn Seal Seal Running None None Purification cation Pump Very Hot Seal Shutdown Cooling Flow Orifice Flange Gasket Minute Leak None None Flange

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YANKEE FOWE SD4INNUAL REPORT 1-1-75 'IO 6-30-75 V SLWARY OF PIANT SYSTDI OE41STRY AND RADIOCIiH41STRY

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A YANKEE IDE SD1INMJAL REPORT l-1-75 'IO 6-30-75 VI OCCUPATIONAL PFASOICEL PADIATION EXPOSURE

4 OCCUPATIONAL RADIATION EXPOSURE SUhtt\\RY 1 January 1975 to 30 June 1975 100-250-500-750- <100 250 500 750 1000 1-2 2-3 3-4 4-5 5-6 >6 Personnel Category N.M.E. FRD1 MRDI MRB1 hRB1 MRB1 RD! RB1 RB1 RBI RBI RD1 Permanent 55 25 19 20 3 0 2 0 0 0 0 0 Temporary 618 7 0 0 0 0 0 0 0 0 0 0 No Measurable Exposure All exposures in excess of 500 bEUM during the six month period are tabulated on the attached page(s). A table of reference symbols for the major duty functions of the tabulation is as follows: Symbol Duty Function A Routine surveillance and inspection (normal operation) B Routine Maintenance C Special htlintenance (describe below**) D Routine Refueling Operation E Special Refueling Operation (describe below) F Other job related activities (describe below**) Additional Description of Duty Functions C. 1. Replace Cavity purification line. 2. Repair Steam Generator Blowdown 3. Replace Old Oil Cooler Service Water Pipes 4. Repairs in Core Instrumentation F. 1. Waste Processing NOTE: All categories are expressed as a percent of the total exposure

Personnel Job Total Mrem / Duty Function Number Assignment Exposure (In Rem) A B C D E F 1. Chemist 1.087 66 7 4 0 0 23 2. Tester 1.642 49 30 15 0 0 6 3. Plant 1.178 5 38 57 0 0 0 Mechanic 4. Plant 0.544 4 68 24 0 0 0 Mechanic 5. Shift 0.504 100 0 0 0 0 0 Supervisor 6. Shift 0.614 75 15 9 0 0 1 Supe n'isor 7. Aux. 0.740 18 7 39 0 0 42 Operator

i YANKEE IDE SEF11eWAJAL REPORT 1-1-75 'IO 6-30-75 VII RELE7LSE OF P3.DIOtTI'IVE FMTERIAL AIRBORNE, LIQUID, N O SOLID SIIIPFE"IS

Yankee Atoiaic Electric Company, Rowe, Mass. I Effluent and Waste Disposal Supplemental Information 1. Technical Specifications Limits a. Fission and Annual average <1000 times MPC as described in Activation Gases: 10 CFR 20, Appendix B, Tabic 2, Column 1. b. Iodines: Annual average <l.43 times MPC as described in 10 CFR 20, Appendix B, Table 2, Column 1. c. Particulates-Annual average <1.43 times MPC as described in (T 1/2 >8 days) 10 CFR 20, Appendix B, Table 2, Column 1. d. Liquids Isotopic limits found in 10 CFR 20, Appendix B, Table 2, Column 2. 2. Maximum Permissible Concentrations a. Fission and No MPC Limit Reporting Limits As Specified in Activation Gases; 10 CFR 20 (20.403) and (20.405) b. Iodines c. Particulates n n n n (T 1/2 >8 days) d. Liquid Effluents 10 CFR 20, App. B, Table II, Col. 2 3. Average Energy of Fission and Activation Gases Released = (1st) ES = 0.23 Mev, Ey = 0.16 Mev. (2nd) E6 = 0.20 Mev. Ey = 0.18 Mev. 4. Measurements and approximations of total radioactivity. a. Fission and Activation Gases " Continuous Discharges" - Indirect Measurement. Primary gas samples are taken periodically and analyzed. Assumptions: That in primary to secondary leakage all gases are ejected through the air ejector. In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during flashing or liquid waste processing. " Batch Discharges" - Direct Measurement. b. Iodines: Continuous monitoring, sample drawn from the primary vent stack through a particulate filter and charcoal cartridge, the filter and charcoal cartridge are removed weekly. c. Particulates: The particulate filter as described in (b) above is analyzed weekly. d. Liquid effluents - Direct Measurement Compositing for SR 89, 90, Alpha and Carbon-14 Analysis. No compositing for Beta, Tritium and Dissolved Gases y isotopic analysis (Resin Method) - compositive for continuous discharges and no compositing for batch discharges.

SUPPLEMENTAL INFORR\\ TION ERROR ESTIMATIONS - LIQUIDS I - Errors Associated with Volumes Discharge a. Blowdown = 3 0 ** b. Test Tank = 3*s II

  • Errors Associated with Counting t 20% (Resin Method) a.

Isotopic Analysis huximum = 10#. b. Tritium = 15 ". c. Dissolve Fission Gases = = 1 10% d. Alpha Analysis

  • Sbximum counting error was determined by comparison of cross check sample data with that of Teledyne, N.R.C. nad E.P. A. results.

About equal amounts discharge Fission + Activation Products = via blowdown + test tanks E= - (30)2 (3)2 + (20)2 = ,jl309 = 36% Tritium = 95% discharge via test tanks (3)2 3/109 = 10.9% E= (10) + = Dissolve Fission Gases = About equal amounts discharge via blowdown and test tanks. if(30)2 (3)2 3/1234 35% (15) E= = + = Alpha = About equal amounts discharge via blowdown and test tanks. E= (30)~ + (3)' + (10)' = 1/1009 32% =

1 Supplemental Information ERROR ESTibt\\ TION - GASES 1. Errors Associated with volumes discharge a. Charging pump leakage = 10"e b. Primary to secondary leak rate = 30"e c. Sampic volume for batch discharges = 1 25% d. For Iodines and particulates volume fluctuation at primary vent stack = 1 10". e. Error of uncertaincy that gases at sampling is at equilibrium during the entire period = 50% f. Fluctuation of volume at t ritium samples = 25% II. Errors associated with counting a. Fission and activiation gases - isotopic analysis = 159 b. lodines analysis = 2 0 ', c. Particulates - isotopic analysis = 1 25"6 d. Tritium analysis = 1 10%

  • Maximum counting error was determined by comparison of cross check sample data from that of Teledyne, and NRC results.

about 95% discharge via charging pump leakage FISSION + ACTUATION GASES = }f(50)2+ (10)2 + (15)2 1/2825 53% E= = = 10 DINES Tf(10) (20)2 T/500 22.5% E= + = = PARTICULATES I 3/725 271 E= y (10)~ + (25)~ = = TRITIUM l!(25)2+ (10)2 T/725 ! 27e = = E=

g TABLE 1A EFFLUENT AND h'ASTE DISPOSAL SElII ANNUAL REPORT 1975 GASH 0llS EFFLUENTS - SU:41ATION OF AI.L REl. EASES Unit Quarter Quarter Est. lotal (1) (2) Error, % A. Fission G activation gases

1. Total release Ci 2.5E00 7.6E00 I 5.5E01 l
2. AverarIc~~$ lease rat e for period pCi sec 3.2E-01 9.7E-01
3. Percent of technical specification limit 1

3.0E-02 1.3E-01 II. lodines

1. Total iodine-131 Ci 5.8E-05 2.8E-04 1 2.5E01
2. Average ' release rate for period pCi/sec 7.4E-Ob 3.6E-05 3.

Percent of technical specification limit 1 7.3E-01 4.3E00 C. Particulates

1. Particulates with half-lives >8 days Ci 4.6E-05 6.2E-05 1 3.0E01
2. Averate release rate for period pCi/sec 5.9E-06 7.9E-06 3.

l'ercent of technical specification limit 1.3E-01 2.0E-01

i. Gross alpha radioactivity Ci 4.4E-06 9.2E-06 D. Tritiun
1. Total release Ci 4.7E-01 5.5E-01 1 3.0E01
2. Average release rate for period DCi/sec 6.IE-02 7.0E-02
3. Percent of technical specification limit 1

4.3E-03 6.0E-03 l 1

YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MASS. - TABLE - IB EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT ( 1975 ) GASEOUS EFFLUENTS - ELEVATED RELEASES Continuous Mode Batch Mode Nuclides Released Unit Qua rt er (l) Qua rt er (2) Quarter (1) Quarter (2) Fission Gases Krpt on-85 Ci < 6.8E-03 2.2E-02 < 6.3E-05 < 1.6E-05 Krpton-85M Ci 1.6E-02 3.5E-02 8.6E-04 1.8E-03 Krpton-87 Ci 1.2E-02 2.3E-02 9.6E-04 2.8E-03 Krp t o n-88 Ci 2.lE-02 5.3E-02 1.5E-03 3.5E-03 Xenon-133 Ci 2.0E00 5.4E00 2.4E-02 3.4E-02 Xenon-135 Ci 1.5E-01 6.0E-01 3.2E-03 6.5E-03 Xenon-135M Ci 9.6E-04 7.4E-01 4.8E-04 1.2E-03 Xenon-138 Ci < l.7E-03 1.1E-02 < 6.5E-04 1.8E-03 Others (Sptcify) Ci Xenon-133M Ci 2.1E-02 6.SE-02 4.9E-04 5.9E-04 Argon-37 Ci 3.2E-0a 5.4E-04 3.2E-05 5.3E-06 Argon-41 Ci 1.5E-01

3. Oli- 01 1.3E-02 4.0E-02 Carbon-14 Ci 7.6E-03 5.2E-03 5.6E-05 3.3E-05 Rubidium-88 Ci 6.5E-02 1.2E-01 3.9E-03 7.2E-03 Unidentified Ci Total for l'eriod Ci

< 2.4E00 7.4E00 < 4.9E-02 < 9.9E-02 lodines lodine-131 Ci 5.8E-05 2.7E-04 6.9E-07 1.75E-06 Iodine-133 Ci 1.8E-04 2.2E-04 2.2E-06 1.38E-06 Iodine-135 Ci < 1.2E-05 2.9E-05 < l.4E-07 < 1.9E-07 Total for Period Ci < 2.5E-04 < 5.2E-04 < 3. 9E-06 ' 3.3E-06 Tritium Ci 4.4E-01 5.1E-01 5.3E-03 3.2E-03 Particulates St ront ium-89 Ci 1.4E-07 < l.3E-07 1.7E-GS < 8.1E-10 Strontium-90 Ci 5.9E-08 3.9E-08 7.0E-10 < 2.4E-10 Cesium-134 Ci < 3.0E-07 < l.0E-06 < 3.6E-09 < 6.3E-09 Cesium-137 Ci 4.7E-07 4.5E-07 5.6E-09 < 2.8E-09 Ba rium-Lanthanium-I 40 Ci < 1.lE-06 < 6.7E-07 < l.3E-08 < 4.2E-09 Others (Specify) Ci Cobalt-58 Ci 4.6E-06 2.9E-06 5.5E-08 1.8E-08 Cobalt-60 Ci 2.6E-05 4.2E-05 3.2E-07 2.6E-07 Iron-59 Ci < 8.2E-07 < 7.2E-07 < 9.8E-09 < 4.5E-09 Chromium-51 Ci < l.4E-06 < l.2E-06 < l.7E-08 < 7.5E-09 Zirconium-Niobium 95 Ci < 7.7E-07 < 4.8E-07 < 9.2E-09 < 3.0E-09 Selenium-75 Ci < 2.8E-07 < l.8E-07 < 3.3E-09 < l.lE-09 Silver-110M Ci < l.lE-06 < 1.2E-06 < 1.3E-08 < 7.5E-09 Antimony-124 Ci < 4.2E-07 < 3.9E-07 < 5.0E-09 < 2.4E-09 Ci 8.4E-06 1.0E-05 1.0E-07 6.3E-OS Unidentified Ci Total for Period Ci < 4.6E-05 < 6.lE-05 < 5.5E-07 < 3.8E-07

YANKEE A'IOMIC ELECTRIC COMPANY, ROWE, MASS. - TABLE - IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1975) CASE 00S EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quart er(l) Quarter (2) Quarter (1) Quarter (2) Fission Cases Krpton-85 Ci 0.0E00 0.0E00 0.0E00 0.0E00 Krpton-85M Ci Krpton-87 Ci Krpton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135M Ci Xenon-138 Ci Others(Specify) Ci Xenon-133M Ci Argon-37 Ci Argon-41 Ci Ca rbon-14 Ci Rubidium-88 Ci Unidentified Ci Total for Period Ci 0.0E00 0.0E00 0.0E00 0.0E00 Iodines Iodine-131 Ci 0.0E00 0.0E00 0.0E00 0.0E00 Iodine-133 Ci lodine-135 Ci Total for Period Ci 0.0E00 0.0E00 0.0E00 0.0E00 Tritium Ci 3.3E-02 3.8E-02 0.0E00 0.0E00 Particulates Strontium-89 Ci 0.0E00 0.0E00 4.9E-09 < 2.3E-09 Strontium-90 Ci 1.8E-09 < 1.2E-10 Cesium-134 Ci < 2.5E-08 4.lE-08 Cesium-137 Ci 9.9E-08 4.2E-c8 Parium-Lanthanium-140 Ci < l.3E-08 < l.9E-08 6thers (Specify) Ci Cobalt-58 Ci < l.0E-08 < 9.6E-09 Coba1t-60 Ci 4.0E-08 4.3E-08 Iron-59 Ci < l.7E-08 < 4.8E-09 Chromimn-51 Ci < 4.3E-08 < 2.7E-08 2irconium-Niobium-95 Ci < l.0E-08 1.2E-08 Selenium-75 Ci < 3.2E-09 < 4.6E-09 Silver-110M Ci < 1.6E-07 < 3.4E-08 Antimony-124 Ci < 6.7E-09 < l.8E-08 Manganese-54 Ci 6.5E-09 1.8E-08 Unidentified Ci Total for Period Ci 0.0E00 0.0E00 < 4.4 E- 07 < 2.7 E-07

s TABLE 2A EFFLUENT AND WASTE DISPOSAL St.MI ANNUAL REPORT 1975 LIQUID EFFl.UENTS - SUBS!ATION OF ALL RELEASES Unit Quarter Quarter Est. Total (1) (2)

Error, A. 1:ission and activation products
1. Total release (not including tritium, gases, alpha)

Ci <6.8E-04 1.4E-03 2 4.0E01

2. Average diluted concentration during period pCi/ml 1.0E-Il 2.lE-Il 6.3E-04 1.8E-3
3. Percent of applicable limit B. Tritium
1. Total release Ci 5.7E01 5.8E01 1 1.0E01
2. Average diluted concentration during pe ri od UCi/ml 8.5E-07 8.7E-07 2.6E-02 2.9L-02
3. Percent of applicable limit

-o C. Dissolved and entrained gases

1. Total release Ci

<4.2E-03 <5.9E-03 1 3.5E01

2. Average diluted concentration during period uCi/ml

<6.3E-Il 8.9E-Il

3. Percent of applicable limit t,

2.lE-03 3.0E-03 D. Gross alpha radioactivity

1. Tot al rele :ise Ci

<4.6E-06 <7.9E-07 I 3.0E01 E. Volume of waste released (prior to dilutior.) liters 4.1E06 4.71E06 1 3.0E01 F. Volume of dilution water used during period liters 6.7E10 6.63E10 1 5.0E00 W

YANKEE ATOMIC ELECTRIC COMPANY-RohE, MASS. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1975 LIQUID EFFLUENTS TABLE 2B Continuous Mode Batch Mode Nuclides Released Unit Quart c r(l ) Quarter (2) Quart er (1) Quarter (2) Strontiam.89 Ci < 3.8E-04 < 7.3E-04 < 2.6E-05 < 7.5E-05 1.2E-04 < 2.lE-06 < 7.5E-06 Strontium-90 Ci 4.2E-05 s Cesium-134 Ci 1.3E-05 1.6E-05 < 7.3E-06 1.6E-05 Cesium-137 Ci 2.3E-05 2.8E-05 9.9E-06

1. 8 E- 05 Iodine-131 Ci 1.2L-05 2.lE-05 1.2E-05 1.lE-04 Cobalt-58 Ci 2.9E-06

< l.1E-06 < 2.0E-06 < l.FL-06 Cobalt-60 Ci < 9.6E-06 1.4E-05 2.9E-05 1.1E-05 J.4E-05 Iron-59 Ci < l.7E-06 1.6E-05 < 2.0E-06 '.8E-06 l.8E-07 1.9E-06 Zinc-65 Ci < l.9E-06 Manganese-54 Ci 5.9E-06 < 1.5E-06 1.3E-05 i Di-06 6.6h-t Chromium-51 Ci < 5.2E-06 6.0E-06 < 4.6E-06 Zirconium-Niobium-95 Ci < l.9E-06 < l.7E-06 < l.7E-06 < 5.7E-06 Molybdenum-99 Ci < 1.8E-06 7.8E-06 < 3.2E-06 < 5.9E-06 Technetium-99M Ci < 2.7E-07 1.7E-05 < 2.0E-07 2.6E-06 Ba r ium-Lant hanum-140 Ci < 2.7E-06 < 4.lE-06 < 3.lE-06 < 4.2E-06 Cerium-141 Ci < 6.6E-07 < l.0E-06 < 5.5E-07 < l.3E-06 Other (Speci fy) Ci lodine-133 Ci < l.8E-06 2.8E-05 < 8.5E-07 < l.2E-06 Selenium-75 Ci < 7.7E-07 < 8.3E-07 <J IE-06 < l.7E-06 Silver-110M Ci < 3.6E-06 < 4.0E-06 8E-06 < 4.7E-06 Antimony-124 Ci < l.2E-06 < 2.0E-06 < l.2E-06 < l.5E-06 Carbon-14 Ci 9.8E-06 3.5E-05 2.0E-05 5.6E-06 Ci Unidentified Ci < l.7E-05 < l.6E-05 3.3E-06 Total for Period (above) Ci < 5.4E-04 < l.lE-03 < 1.4E-04 3.0E-04 Xenon-133 Ci < 2.2E-03 < 2.2E-03 1.lE-03 2.8E-03 Xenon-135 Ci < 8.8E-04 < l.0E-03 < 6.8E-05 < 9.0E-05 Tritium Ci 5.9E-01 5.2E-02 5.6E+01 5.8E+01

a TABLE 3 EFFLUENT AND WASTE DISFOSAL SENIANNUAL REPORT SOLID WASTF AND IRRADIATED FUEL SilIPMENTS (1-75 to 7-25) A. SOLID WASTL SillPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1. Type of waste Unit 6-month Est. Total Period Error, 5

a. Spent resins, filter sludges, m

3.3E06 3 + 3.0E01 "vaparator bottoms, etc. Ci 1.lE00 3 1.9E05

b. Dry compressible waste, m

+ 5.0E01 contaminated equip., etc. Ci 1.4E-01

c. Irradiated components, control mf NA hA rods, etc.

C1 3 8.7E04 Decontamination m

d. Other (describe)

Solutio.' Ci 1.3E-01 -+ 2.0E01 3 1.2E06 m + 3.0E01 c. Incinerator Ashes Ci 4.5E-03 2. c3timate of major nuclide composition (by type of waste) a. Cobalt-60 'a 3.7E01 Manganese-54 2.4E01 Cesium-137 1. 71101 b. Cobalt-58 4.lE01 Iron-59 3.3E01 Manganese-54

  • e 1.6E01 C.

None 'o d. Cobalt-60 8.6E01 1.21!01 Manganese-54 e c. Silver-110M 4.0E01 Cesium-137 2.9E01 Cobalt-60 "o 1.2E01 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Truck Moorehead, Ky. B. IRRADI ATED FUEL SilIPMENTS (Disposition) Number of Shipments Mode of Transportation Destination None

YNa22: FOC SD1IR2UAL IEPORT 1-1-75 '10 6-30-75 VIII ABtJOWAL OOCURRDD2s

A. Report Number: 50-29/75-1

Title:

Charging Line Transmitter Leak Occurrence Date: February 8, 1975 Description of Occurrence: On Saturday, 2/8/75, during a routine inspection tour, the auxiliary operator found a minor leak on the charging line flow transmitter. This is a violation of Technical Specification, Appendix A, Section E.4.e. B. Report Number: 50-29/75-2

Title:

Missed Surveillance Occurrence Date: February 11, 1975 Description of Occurrence: The monthly operational check ui the two Safety Injection initiation air pressure switches was missed for the month of January 1975. This is a violation of Technical Specification, Appendix A, Section D.2.i. C. Report Number: 50-29/75-3

Title:

Shutdown Cooling System Flow Indicator Sensing Line Leak Occurrence Date: February 19, 1975 Descrirtion of Occurrence: On Wednesday, 2/19/75, while inspecting a leaiing flow orifice flange on the Shutdown Cooling System, a small leak was noted on one of the sensing lines to the Shutdown Cooling System flow indicator. This is a violation of Technical Specification, Appendix A, Section E.4.e. D. Report Number: 50-29/75-4

Title:

Shutdown Cooling Flow Indicator Sensing Line Leak Occurrence Date: March 11, 1975 Description of Occurrence: On March 11, 1975 at approximately 1145 the supervisor inspecting work in progress in the vicinity of the shutdown cooling flow indicator observed a boron buildup on an elbow leading to the indicator. Further investigation revealed a small leak at %.. eld. E. Report N' S r -29/75-5

Title:

.;c. ergency Diesel Generator DC Control Circuit Failure Occurrence Date: Apr H 13, 1975 Description of Occurrence: At approximately 1650 on April 13, 1975 the auxiliary operator observed that the No. 3 diesel generator DC

s control circuit p. lot lisht located outside the diesel cubicle was g In attempting to check the bulb he found it fused to the out. socket. The control room operator was notified, he in turn.noted that the pilot light located on the Control Room Diesel Panel was also out. An attempt was then made to start the diesel. It failed to start.}}

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