|
---|
Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217A0001998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Haddam Neck Plant ML20217D7381998-02-28028 February 1998 Revised MOR for Feb 1998 Haddam Neck Plant ML20216D6531998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Haddam Neck Plant CY-98-012, Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant ML20198N6681997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Haddam Neck Plant ML20203K4271997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Haddam Neck Plant ML20199B1141997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Haddam Neck Plant ML20198J8811997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Haddam Neck Plant ML20210U9301997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Haddam Neck Plant ML20210L0521997-07-31031 July 1997 Monthly Operating Rept for July 1997 for HNP ML20149E4451997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Haddam Neck Plant ML20140H5241997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Haddam Neck Plant ML20141D4141997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Connecticut Yankee Haddam Neck ML20137W8051997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Haddam Neck Plant ML20137A0801997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Haddam Neck Plant ML20138K5721997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Haddam Neck Plant.W/ ML20133M6121996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Yankee Haddam Neck Plant ML20132B9861996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Connecticut Yankee Haddam Neck Plant ML20134K7331996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Haddam Neck Plant ML20128Q7661996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Connecticut Yankee Haddam Neck Plant ML20029E6001994-04-30030 April 1994 Monthly Operating Rept 94-04 for Apr 1994 for Haddam Neck Plant ML20058P2691993-11-30030 November 1993 Monthly Operating Rept for Nov 1993 for Haddam Neck Plant ML20059M1881993-10-31031 October 1993 Monthly Operating Rept for Oct 1993 for Haddam Neck Plant.W/ ML20057G0561993-09-30030 September 1993 Monthly Operating Rept for Sept 1993 for Connecticut Yankee Haddam Neck Plant ML20057B3041993-08-31031 August 1993 Monthly Operating Rept for Aug 1993 for HNP ML20046D3961993-07-31031 July 1993 Monthly Operating Rept for Jul 1993 for Haddam Neck Plant ML20045H2301993-06-30030 June 1993 Monthly Operating Rept for June 1993 for HNP ML20045B9241993-05-31031 May 1993 Monthly Operating Rept for May 1993 for Haddam Neck Plant.W/ ML20035E6931993-03-31031 March 1993 Monthly Operating Rept for Mar 1993 for Haddam Neck Plant.W/ ML20044C1791993-02-28028 February 1993 Monthly Operating Rept for Feb 1993 for Haddam Neck Plant.W/ ML20128H6131993-01-31031 January 1993 Monthly Operating Rept for Jan 1993 for Haddam Neck Plant.W/ ML20127E5711992-12-31031 December 1992 Monthly Operating Rept for Dec 1992 for HNP ML20126A5011992-11-30030 November 1992 Monthly Operating Rept for Nov 1992 for Haddam Neck Plant.W/ ML20024H0611991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Connecticut Yankee Haddam Neck Plant ML20217A1991990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Haddam Neck Plant ML20058A0891990-09-30030 September 1990 Revised Monthly Operating Rept for Aug 1990 for Haddam Neck Plant Unit 1 ML20059J1301990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Haddam Neck Plant.W/ ML20044B3401990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Haddam Neck Plant ML20043G1161990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Haddam Neck Plant ML20043A1131990-04-30030 April 1990 Monthly Operating Rept for Apr 1990 for Haddam Neck Plant ML20012C1281990-02-28028 February 1990 Monthly Operating Rept for Feb 1990 for Haddam Neck Plant ML20006E8121990-01-31031 January 1990 Monthly Operating Rept for Jan 1990 for Haddam Neck Plant ML19332G2441989-11-30030 November 1989 Monthly Operating Rept for Nov 1989 for Haddam Neck Plant ML19325C6971989-09-30030 September 1989 Monthly Operating Rept for Sept 1989 for Haddam Neck Plant ML20247F6141989-08-31031 August 1989 Monthly Operating Rept for Aug 1989 for Haddam Neck Plant ML20245L8191989-07-31031 July 1989 Monthly Operating Rept for Jul 1989 for Haddam Neck Plant ML20246K1831989-06-30030 June 1989 Monthly Operating Rept for June 1989 for Haddam Neck Plant ML20244E1511989-05-31031 May 1989 Monthly Operating Rept for May 1989 for Haddam Neck Plant ML20247A1291989-04-30030 April 1989 Monthly Operating Rept for Apr 1989 for Haddam Neck ML20244D0831989-03-31031 March 1989 Monthly Operating Rept for Mar 1989 for Connecticut Yankee Haddam Neck Plant 1998-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 CY-99-047, Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use1999-03-23023 March 1999 Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use 05000213/LER-1999-001, :on 990105,main Stack RM R-14A Pressure Compensating Signal Was Not Calibrated.Caused by Personnel Error.Revised Calibration Procedure.With1999-02-0101 February 1999
- on 990105,main Stack RM R-14A Pressure Compensating Signal Was Not Calibrated.Caused by Personnel Error.Revised Calibration Procedure.With
05000213/LER-1997-016, :on 970825,discovered That Negative Pressure Was Not Maintained in Sf Bldg,Per Design Basis.Caused by Sf Bldg Ventilation Sys Being Based on Lower Pab Ventilation Flow Rates.Corrected Ventilation Sys Design.With1999-01-25025 January 1999
- on 970825,discovered That Negative Pressure Was Not Maintained in Sf Bldg,Per Design Basis.Caused by Sf Bldg Ventilation Sys Being Based on Lower Pab Ventilation Flow Rates.Corrected Ventilation Sys Design.With
ML20206F1971998-12-31031 December 1998 Annual Rept for 1998 for Cyap. with CY-99-027, Annual Rept for 10CFR50.59, for Jan-Dec 1998.With1998-12-31031 December 1998 Annual Rept for 10CFR50.59, for Jan-Dec 1998.With ML20198G9101998-12-22022 December 1998 Proposed Rev 2 of Cyap QAP for Haddam Neck Plant. Marked Up Rev 1 Included 05000213/LER-1997-018, :on 971003,discovered That Sf Bldg Exhaust Fan Did Not Meet Design Basis.Caused by Higher than Expected Pressure in Pab.Design of Sf Bldg Ventilation Sys Was Corrected.With1998-12-0808 December 1998
- on 971003,discovered That Sf Bldg Exhaust Fan Did Not Meet Design Basis.Caused by Higher than Expected Pressure in Pab.Design of Sf Bldg Ventilation Sys Was Corrected.With
05000213/LER-1998-009, :on 980915,noted Excessive CV,SW-CV-963,seat Leakage in SW Supply Piping to SFP Heat Exchangers.Caused by Subject Cv Disc Being Stuck in Open Position.Valve Was Exercised & Freed from Stuck Open Position.With1998-10-14014 October 1998
- on 980915,noted Excessive CV,SW-CV-963,seat Leakage in SW Supply Piping to SFP Heat Exchangers.Caused by Subject Cv Disc Being Stuck in Open Position.Valve Was Exercised & Freed from Stuck Open Position.With
05000213/LER-1998-008, :on 980721,determined That Main Stack Radiation Monitor RMS-14B Samples Were Not Analyzed to Required Detection Level.Caused by Inadequate Design.Immediately Controlled Temp of Radiation Monitor Room.With1998-09-29029 September 1998
- on 980721,determined That Main Stack Radiation Monitor RMS-14B Samples Were Not Analyzed to Required Detection Level.Caused by Inadequate Design.Immediately Controlled Temp of Radiation Monitor Room.With
05000213/LER-1997-021, :on 971124,found Contaminated Matls Offsite. Caused by Breakdown of Health Physics Program in Effect at Time Contaminated Matl Was Released from Site.Revised Procedures.With1998-09-0101 September 1998
- on 971124,found Contaminated Matls Offsite. Caused by Breakdown of Health Physics Program in Effect at Time Contaminated Matl Was Released from Site.Revised Procedures.With
ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co 05000213/LER-1998-007, :on 980714,excessive Check Valve Seat Leakage in SW Supply Piping to SFP Heat Exchangers,Occurred.Caused by SW-CV-963 Disc Sticking in Open Position.Increased Test Frequency from Quarterly to Monthly1998-08-13013 August 1998
- on 980714,excessive Check Valve Seat Leakage in SW Supply Piping to SFP Heat Exchangers,Occurred.Caused by SW-CV-963 Disc Sticking in Open Position.Increased Test Frequency from Quarterly to Monthly
CY-98-136, Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line1998-08-12012 August 1998 Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line ML20237B7461998-07-22022 July 1998 1998 Defueled Emergency Plan Exercise Scenario Manual, Conducted on 980722 ML20202D1621998-06-30030 June 1998 Safety Evaluation Supporting Amend 193 to License DPR-61 05000213/LER-1998-005, :on 980511,determined That Design Deficiency Was Found in Main Stack Flow Rate Monitor.Caused by 1974 Mod Change on Original Installation.Declared F-1101 Channel Out of Svc & Develop Means of Estimating Flow1998-06-0909 June 1998
- on 980511,determined That Design Deficiency Was Found in Main Stack Flow Rate Monitor.Caused by 1974 Mod Change on Original Installation.Declared F-1101 Channel Out of Svc & Develop Means of Estimating Flow
05000213/LER-1998-006, :on 980507,design Deficiency Was Found in Stack RM RMS-14B Sampling Lines.Caused by Design Not Meeting ANSI N13.1-1969 Stds.Corrective Action Plan for RMS-14B Is Being Developed1998-06-0808 June 1998
- on 980507,design Deficiency Was Found in Stack RM RMS-14B Sampling Lines.Caused by Design Not Meeting ANSI N13.1-1969 Stds.Corrective Action Plan for RMS-14B Is Being Developed
05000213/LER-1998-004, :on 980507,discovered Design Deficiency in Stack Radiation Monitor RMS-14B Isokinetic Sampling.Caused by Failure to Account for Spent Fuel Bldg Ventilation Flow. Will Develop CAP for RMS-14B1998-06-0404 June 1998
- on 980507,discovered Design Deficiency in Stack Radiation Monitor RMS-14B Isokinetic Sampling.Caused by Failure to Account for Spent Fuel Bldg Ventilation Flow. Will Develop CAP for RMS-14B
05000213/LER-1998-003, :on 980505,compensatory Sampling Frequency Exceeded Time Limit W/Sw Effluent RM Inoperable.Caused by Personnel Error.Individual Was Counseled & Technicians Were Reminded of Sampling within Required Frequency1998-06-0202 June 1998
- on 980505,compensatory Sampling Frequency Exceeded Time Limit W/Sw Effluent RM Inoperable.Caused by Personnel Error.Individual Was Counseled & Technicians Were Reminded of Sampling within Required Frequency
05000213/LER-1998-002, :on 980421,determined That Visual Insp of Switchgear Cable Shaft Sprinkler Sys Was Not Being Performed Once Per 18 Months.Caused by Inadequate Implementation of License Amend.Fire Watch Patrol Established1998-05-19019 May 1998
- on 980421,determined That Visual Insp of Switchgear Cable Shaft Sprinkler Sys Was Not Being Performed Once Per 18 Months.Caused by Inadequate Implementation of License Amend.Fire Watch Patrol Established
05000213/LER-1998-001, :on 980409,seismic Monitor Sp Was Not in Compliance W/Ts.Caused by Inadequate Engineering Review. Submitted Proposed License Amend to Correct Issue1998-05-0707 May 1998
- on 980409,seismic Monitor Sp Was Not in Compliance W/Ts.Caused by Inadequate Engineering Review. Submitted Proposed License Amend to Correct Issue
CY-98-068, Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms1998-04-15015 April 1998 Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms CY-98-045, Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing1998-04-13013 April 1998 Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing ML20217A0001998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Haddam Neck Plant ML20217F0611998-03-31031 March 1998 Historical Review Team Rept ML20217K2101998-03-27027 March 1998 Safety Evaluation Supporting Amend 192 to License DPR-61 CY-98-046, Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal1998-03-12012 March 1998 Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal ML20216D6531998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Haddam Neck Plant ML20217D7381998-02-28028 February 1998 Revised MOR for Feb 1998 Haddam Neck Plant CY-98-012, Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant CY-98-010, Annual Rept for 10CFR50.59,Jan-Dec,19971997-12-31031 December 1997 Annual Rept for 10CFR50.59,Jan-Dec,1997 ML20198N6681997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Haddam Neck Plant ML20217P4861997-12-31031 December 1997 1997 Annual Financial Rept, for Cyap ML20199L5891997-12-24024 December 1997 Independent Analysis & Evaluation of AM-241 & Transuranics & Subsequent Dose to Two Male Workers at Connecticut Yankee Atomic Power Plant 05000213/LER-1997-020, :on 971117,determined That Radioactive Effluent Dose Calculations Were Not Performed within Required Frequency.Caused by Procedure Inadequacy.Will Revise Procedures & Will Enhance Tracking Process1997-12-16016 December 1997
- on 971117,determined That Radioactive Effluent Dose Calculations Were Not Performed within Required Frequency.Caused by Procedure Inadequacy.Will Revise Procedures & Will Enhance Tracking Process
ML20203K4271997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Haddam Neck Plant 05000213/LER-1997-017, :on 970924,identified Three Locations of Detectable Plant Related Radioactivity in on-site Landfill Area.Caused by Failure to Conduct Adequate Survey.Access to Area Controlled1997-11-18018 November 1997
- on 970924,identified Three Locations of Detectable Plant Related Radioactivity in on-site Landfill Area.Caused by Failure to Conduct Adequate Survey.Access to Area Controlled
05000213/LER-1997-019, :on 970808,compensatory Sampling Frequency Exceeded W/Rms Determined Inoperable.Caused by Personnel Error Due to Incorrect Interpretation of Ts.Compensatory Sampling to Be Conducted in Time Frame Required1997-11-17017 November 1997
- on 970808,compensatory Sampling Frequency Exceeded W/Rms Determined Inoperable.Caused by Personnel Error Due to Incorrect Interpretation of Ts.Compensatory Sampling to Be Conducted in Time Frame Required
ML20199B1141997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Haddam Neck Plant 05000213/LER-1997-018, :on 971003,Spent Fuel Building Exhaust Fan Flow Was Found Below Design During Testing.Caused by Personnel Error.Evaluated Replacement of Spent Fuel Building Exhaust Fan Capable of Overcoming Higher Pressures1997-10-30030 October 1997
- on 971003,Spent Fuel Building Exhaust Fan Flow Was Found Below Design During Testing.Caused by Personnel Error.Evaluated Replacement of Spent Fuel Building Exhaust Fan Capable of Overcoming Higher Pressures
ML20198M8101997-10-14014 October 1997 SER Accepting Proposed Revs to Util Quality Assurance Program at Facility ML20198J8811997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Haddam Neck Plant 05000213/LER-1997-015, :on 970813,functional Testing of Radiation Monitoring Sys Was Not Performed as Defined in Ts.Caused by Lack of Understanding of Definition of Acot.Revised Appropriate RMS Surveillance Procedure1997-09-12012 September 1997
- on 970813,functional Testing of Radiation Monitoring Sys Was Not Performed as Defined in Ts.Caused by Lack of Understanding of Definition of Acot.Revised Appropriate RMS Surveillance Procedure
05000213/LER-1996-027, :on 961010,boron Injection Flow Path Below Minimum Required Temperature Was Determined.Caused by Inadequate Design of Heat Trace Controls in Rtd.Boric Acid Flow Paths from Bamt Were Declared Inoperable1997-09-12012 September 1997
- on 961010,boron Injection Flow Path Below Minimum Required Temperature Was Determined.Caused by Inadequate Design of Heat Trace Controls in Rtd.Boric Acid Flow Paths from Bamt Were Declared Inoperable
05000213/LER-1996-016, :on 960801,potential for Inadequate RHR Pump NPSH During Sump Recirculation Was Determined.Caused by Failure to Fully Analyze Containment Pressure & Sump Temperature Response.Redesign of Piping Proposed1997-09-12012 September 1997
- on 960801,potential for Inadequate RHR Pump NPSH During Sump Recirculation Was Determined.Caused by Failure to Fully Analyze Containment Pressure & Sump Temperature Response.Redesign of Piping Proposed
05000213/LER-1997-014, :on 970808,ESFA Occurred Due to Deenergization of High Containment Pressure Actuation Circuits.Reemphasized Expectations of Mgt for Performing non-routine Operational Tasks1997-09-0505 September 1997
- on 970808,ESFA Occurred Due to Deenergization of High Containment Pressure Actuation Circuits.Reemphasized Expectations of Mgt for Performing non-routine Operational Tasks
05000213/LER-1996-021, :on 960828,valve Leakage Resulted in Nitrogen Intrusion Into RCS During Cold Shutdown.Caused by Leaking Valve BA-V-355.Training Has Been Been Provided to Operators on Event & Features & Limitations of Sys1997-09-0505 September 1997
- on 960828,valve Leakage Resulted in Nitrogen Intrusion Into RCS During Cold Shutdown.Caused by Leaking Valve BA-V-355.Training Has Been Been Provided to Operators on Event & Features & Limitations of Sys
05000213/LER-1996-005, :on 960301,spent Fuel Cooling Was Shut Down Due to Discovery of Loose Parts.Caused by Inadequate Design. Piping from Both Sent Fuel Pool Cooling Pumps to Plate Exchanger Were Inspected for Loose Parts w/bore-a-scope1997-09-0505 September 1997
- on 960301,spent Fuel Cooling Was Shut Down Due to Discovery of Loose Parts.Caused by Inadequate Design. Piping from Both Sent Fuel Pool Cooling Pumps to Plate Exchanger Were Inspected for Loose Parts w/bore-a-scope
1999-04-28
[Table view] |
Text
,
[
l Connecticut Yankee Atomic Power Company :
Haddam Neck Plant -
4 '.
4 e
,a:
Haddam, Connecticut -
- .(.
l c
i 1
s
(
-i
.f i
,t
, i r
- r 9.
V
- .('.
-n-t L n
.) t
!}
't
'k
- 1 s
-: 9 i;
Monthly Operating' Report No.90 09
,a For The Month'of September 1990 '
i q.
3 4
i 9010250PA9 900930 PDR ADOCK 65000213 R
I'in;
(
1 Y
{
m.
i
. Plant Onerations Summarv - Sentember 1990
-l e
t..
4 The following is a summary of Plant Operations for September 1990.
e On September 1,1990 at 00:00 hours, the plant was in Mode 1 at 30% power for Chemistry hold. At
- 07
- 02 hours, power ascension resumed.- By 22:55 hours, the plant was at 80% power and conducting
- flux mapping.
On September 3,1990 at 04:57 hours, the plant was manually tripped due to a low suction pressure on the Main Feed Pumps. At 18:10 hours, a primary plant startup was commenced. By 19:11 hours, the plant was in Mode 2, Startup.
On September 8,1000 at 22:55 hours, the plant was phased to the grid. Power was held at 9% because i
- of a Chemistry hold.
On September 9,1990 at 04:29 hours, a load increase was commenced. By 06:35 hours, the plant was -
at 30% power on another Chemistry hold. At 22:43 hours, a load increase was commenced.
j
~ On September 10,1990 at 04:05 hours, the plant was at 80% and conducting flux mapping. At 12:30 hours, the plant reduced load due to Pressurizer level channels 1 and 2 being declared moperable. By t
14:36 hours, the load decrease was stop been declared operable. At 14:59 hours, ped at 70% power because the Pr:ssurizer level a load increase was commenced. By 16:37 hours, the plant was at 80%_ power conducting flux mapping.
On September 14,1990 at 00:24, the plant commenced increasing load. At 02:03 hours, the load o
increase was halted at 83% power due to condensate pump motor current oscillations. At 19:36 hours, a load increase was commenced. At 22:00 hours, the plant was at 90% and holding for completion of steam line break Estrument calibration. By 23:02 hours, a load increase was resumed. At 23:30 hours, the plant was at 92% and power was reduced due to low discharge pressure on the "IB" condensate i
pump. Plant load was then stabilized at 88% power.
H
' On September 15,1990 at 12:30 hours, the plant commenced a load increase. At 12:50 hours, the load was stabilized at 89% power.
['
. On September 16,1990 at 23:03 hours, plant load was reduced due to current oscillations on the condensate pumps.' Load was stabilized at 87 % power.
On Se}itember 19,1990 at 13:10 hours, a load increase was commenced. By 14:00 hours, the plant-was at 92% power and began a load reduction to 88% power due to condensate pump oscillations.
~
On Septetaber 20,1990 at 00:01 hours, the plant commenced a load reduction to troublesh'oot and.
repair the condensate pumps. At 06:28 hours, the load was at 50% power. At 07:15 hours, the Reactor
= was manua.ly tripped due to low feed pump suction caused by the isolation of the "lB" condensate 1
pump. The plant was returned to Mode 3, (Hot Standby).
. On Septemt er 21,1990 at 14:40 hours, the plant entered Mode 4 (Hot Shutdown) to permit working on pressurizer level instrumentation.
On September 24,1990 at 11:40 hours, a plant heatup was commenced. By 12:26 hours, the plant was in Mode 3 (Hot Standby.)
On September 25,1990 at 03:31 hours, the plant reached Mode 2 (Startup).
On September 26,1990 at 03:22 hours, the plant was phased to the grid and in Mode 1,'(Power Operation) at 5%. At 13:28 hours, a load increase was commenced. By 19:45 hours, the plant was at -
30% power and holding for Chemistry. At 21:33 hours, a load increase was commenced.
On September 27,1990 at 20:12 hours, the plant reached at 10Po power.
The plant continued to operate at 100% power for the remainder of the month.
y 1
AVERACE DAILY UNIT POWER LEVEL I
- i 1
n-4 DOCKET NO.
_50-213' Conn. Yankee UNIT Haddam Neck
- DATE 9/90
~,i t
COMPLETED BY K. C. Emons TELEPHONE (203) 267 3654 MONTH:
SEPTEMBER I
?
. t,
.-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.
-(
(MWe-Net)
(MWe-Net)-
1 232 17 497
.2
' 31 18 501 l
4
?
3-n 19 499 4-0 20 106 I
'5 0
21 0
6 0
22 0
p 74 0
23' i
n t
8 o rs 24 0
9 409
.25 e
n
-10 av 26 u
-11 ti3s27-504 i
' 12 -
438' l28 574 i
13 468 29 571-14' 30 568
- f. o5 J 15.'
498 31
.na p
i.
E g'6f j
1
, V,1
- INSTRUCTIONS
~l m
'On this format, list the average' daily unit power level in MWe-Net for each' day
~
..in the. reporting month. ' Complete the nearest whole megawatt.
i i
(9/77) 4 4 k.f, m
~
MAINTENANCE-
'9/90 I.
5 % Tlas
.EFFECT klII CORRECTIVE ACTICII SPECIAL PRECairt100iS -
i M.
MALFUBICTICII SAFE TAKERI TO PREVEIIT-TAKEll-f0 PROVIDE' I
C00ettBEllT CAIISE RESULT OPERATIQM REPETIT10bl FOR REACTOR SAFETY I
Dum w. EEFAIR.
i
- Feedwater-Sten Plug-Loss of Caused Shutdown All valve stem / plug-assemblie
- Regulating Failure Feedwater
' Plant Shutdown s
Valve in stock were inspected and Control xerayed for defects, Stem /plui, assemblies were welded in addition to being pinned, T-2-1B
~ Aux. Feed Pums Water in Found before none Replaced bearing and oil, None
~ Turbine Bearing Oil failure h
a i
4 b
s.
T 4
9 *
._ +
7
~.J -
~
~
?
'i, '.,
1 m r T e
9 of eh 9nop e 0t r or C
S a
Y h
r e t
e OS o' I aw WRT t
G E
f Cbe I
I l r G
S E
Sf ee eo N
p rin T
t t o et e mh m bes e
l CAU I
S s
E M c
A.
LFUNCT 9
I
/
C 9
I
. 0 I
R E
SUL T
O E
P F
ESF R&E
+
APC TET l
o 0
b 0
i 1
TC AO KR RER EliE
, F C
ETT FOI
~
I V
TPE IR CEA I VC I
IT
'II I TCII j
cPTS uOAP aRKE l
EC uRNI
' cE A
ATL RCO ET P
p POPR p
ARRE I
OC i
' RSVA AIU FDT EEI f
T 0
Y t
l i
E
~
J i
b P
J ll{)))
1 lll
p,;
t 3
. 4.
t-i CONNECTICUT YANKEE REACT 6R COOLANT DATA MONTH: SEPTEMBER 1990 4
.{
r
" I<CACTOR COOLANT ANALYSIS MINIfiUM AVERAGE MAXIMUM
!..n.-c....................
L PH-e 25-DEGREES C 5.95E+00 :
6.18E+00
- 6.36E+00-
"! CONDUCTIVITY (UMHOS/CM) 1.33E+01
- 1.75E+01 2.19E+01 CHLORIDES.(PPM)
- <5.00E-02 : <5 00E-02 : <5.00E-02 :
- DISSOLVED OXYGEN (PPB)
- -<5.00E+00 : <5.00E+00 : <5.00E+00 l BORON-(PPM)
- - 1.03E+03 :
1.30E+03 :
1.59E+03 :
1.: LITHIUM (PPM) 1.27E+00 :
1.71E+00 2.09E+00 :
" TOTAL. GAMMA ACT.-(UC/ML) 2.75E-02 :- 3.69E-01 8.82E-01't i
'. IODINE-131 ACT.-(UC/ML) 5.10E-05 4.60E-03 :
2.82E-02 :
I-131/I-133 RATIO 0.00E-01 :
8.30E+00 8.93E+01L:
I CRUD (MG/ LITER)
- <1.00E-02 :
1.04E-01 :
1.60E+00- '
1
! TRITIUM-(UC/ML)'
4.08E-02.:
2.91E-01 :
5.16E-01 :
' HYDROGEN-(CC/KG) 2.45E+01 :
2.90E+01 3.60E+01 l'
AERATED LIOUID WASTE PROCESSED (GALLONS):
1.25E+05 WASTE LIOUID-PROCESSED THROUGH-BORON RECOVERY (GALLONS):
4.20E+04
- AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
5.10E-01 PRIMARY TO SECONDARY: LEAK RATE (GALLONS PER MINUTE):
1.01E-02 f
'g$
- i.
-t-
~;
7
'j hp 1
1
k (g!
+
NRC OPERATING STATU$ REPORT
~
7:
Maddam Neck I
- 1. Docket: 50 213
- 2. Reporting Period: 09/90 Outage + on-line Mourst' 278.1 + 441.9 = 720.0
- 3. Utility
Contact:
J. Stanford (203) 267 3635 t
- 4. Licensed Thermal Power (MWt): 1825-
- 5. Nameplete Reting (Gross MWe):. 667 x 0.9 = 600.3
- 6. Design Electrical Rating (Not MWe): 582 i'
- 7. Maximum Dependable Capacity (Gross MWe): 591.8
- 8. Maalaum Dependebte Capacity (Net MWe): 565
- 9. If changes occur above since test report, reasons are: NONE
.10. Power levet to which restricted, if any (Net MWe): N/A
- 11. Reasons for restriction, !f any: N/A MONTH YEAR TD-DATE CUMULATIVE 12, Report period hours:
720.0 6,551.0.
199,415.0
'13. Mours reactor criticet:
589.5 1,055.5 159,304.7
- 14. Reactor reserve shutdown hours:
0.0
- 0.C 1,285.0
- 15. Nours generator on line 441.9 836.2 152,923.9
- 16. Unit reserve shutdown hours '
O.0 0.0 398.0 17, cross thernet energy generated (MWtH):.
631,715.0 711,527.0 263,578,845.0
- 18. Groes electricot energy generated (MWeH):
201,159.0 212,258.0-86,305,304.0 *
- 19. Net electrical energy generated (MWeH):
185,327.2 166,803.8 81,989,783.8 *
- 20. Unit service factors 61.4 12.8 76.7
- 21. Unit-evellability factor.
61.4 12.8 76.9
- 22. Unit capacity factor using MDC net:
45.6-4.5 74.8
- 23. Unit cepecity factor using DER net 44.2 4.4 70.7
- 24. Unit forced outoge rate:
38.6 25.0 5.7
- 25. Forced outage hours:
2 78.1 279.4 9,255.0 i
- 26. Shutdowns scheduled over next 6 months (type,dete, duration): NONE-
'27. If currently shutdown, estimated startup date: N/A t
"
- Cumulative values frem the first criticality (07/24/67). (The remaining cumulative values are from the first date of commercist operatloc, 01/01/68).
I
.~.-
~. -. -
1811T SMUTD064tS AND POWER REDUCT10blS DOCKET tiA 50-213 1911T NAME Conn. Yankee 3
1.
. DATE 9/90 COMPLETED BY _K. W. Emmons i
REPORT HORITil SEPTEMBER TELEPMotlE : 203-267-3654 i-
~
a
,m-Omn me.
nace o
a,.
9 LER
$e Cau m & Corrective
.a
=
~=
o.
.3 met.
B 81
-Acts to
~ $
j$
j-j
}
er c a.curreac.e -
- 1 Feedwater regulating
'90-03 9/03/90
.F 137.97 A
2 90-01f SJ
.FCV.
valve plug separated fro a; stem.-Stem plug-assemblie a
' modified with welded joi it where plug attached to st :m.
90-04 9/20/90 S
0:
B 4
n/a SD PP Reduced load to 50% power due to cavitation and lo,r discharge pressure on the IB condensate pump 90-05 9/20/90 F
140.12 C/A 2
90-02(
SD PP Premature shutdown of 1
Condensate pump as well a s i
degradation of. flexible ci rubber: coupling on conder sate' pump suction piping. Repl aced ;
rubber coupling with stai alest steel coupling ~
1 2
3.
4 F Forced Ke.ason: -
~Hethod:
Exhibit C-Instructiona.
LS Scheduled A-Equipment Failure (Explaia)
H-Other(Explain 1-Manual
- for Preparation of Das:a B-Maintenance or Test
- 2-Manual Scram C-Refueltag Entry Sheets for Licesses; '
3-Automatic Scram
-Evust Report (LER) Fila D-Regulatory Bestrictica 4-Other(Explain)~
(IInmareOl61).
.E-Operator Training & License Examination F-Administrative 15-C-Operational. Error.(Explaia)
- Exhibit 1 Same Source: ~ _ g ;
y ; g'. ',
-l
-fL
.y j
y; 7.
' V,:,
- Refueline Informatinn Reauest is '
Haddam Neck-t 12.
' Scheduled date for next refueling shutdown.
October 5,1991 3.
Scheduled date for restart following refueling.
1 November 26,1991 4.
(a)
Will refueling or resumption of operatior thereafter require a technical specification change or other license amendment?
3 Yes (b)-
If answer is yes, what, in general, will these be?
Revise Section 5 of Technical Specifications to allow use of zircaloy clad fuel. Obtain an exemption fmm 10CFR50 Appendix K Sections I.D.3, I.D.4 and I.D.5.
(c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated -
with the core reload?
(Ref.10 CFR section 50.59) n/a
-(d)
If no such review has tahn place, when is it t.::heduled?,
]
n/a i
5..
Scheduled date(s) for submitting proposed licensing action and supporting information.
~ The exemption request will be submitted to the NRC in October 1990. The request will be submitted in March 1991:
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, -
unreviewed design or performance analysis methods, significant changes in fuel design, new operating -
procedures.
Conversion to zircaloy cladding.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pcol.
(a) 157 (b)
~709 8.
The prese nt licensed spent fuel pool storage capacity and the size of any increase in licensed storage.
j capacity. hat has been requested or is planned, in number of fuel assemblies.
I168 9..
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
i?%
-,g t
g
i REVISION lR p
8, NRC OPERATING $TATUS REPORT Haddam Neck
.l
- 1. Docket: 50 213.
- 2. Reporting Period: 08/90 Outage + on-line Hours: 349.7 + 394.3 = 744.0
- 3. Utility contact: J. $tanford (203) 267 3635
- 4. Licensed Thermal Power (Wt): 1825-
- 5. Nameptete Rating (0ross We): 667 x 0.9 = 600.3
- 6. Desten Electrical Rating (Wet We): 582
- 7. Maxiaun Dependable Capacity (Gross We): 591.8
- 8. Maxlaun Dependable Capacity (Net We): 565
- 9. If changes occur above since test report, reasons are: NONE
- 10. Power levet to which restricted, if any (Net W e): N/A
- 11. Reasons for restriction, if any: N/A r
MON 1H YEAR TO DATE CUMULATIVE
- 12. Report period hours:
744.0 5,831.0 198,695.0
- 13. Hours reactor critical:
466.0 466.0 158,715.2
.14. Reactor reserve shutdown hours:
0.0 0.0 1,285.0
- 15. Hours generator on line 394.3 394.3 152,482.0
- 16. Unit reserve shutdown hours:
0.0 0.0 398.0
- 17. Gross thernet energy generated (WtH):
79,812.0 79,812.0 262,947,130.0 *
- 18. Gross electrical energy generated (WeH):
11,099.0 11,099.0 86,104,145.0
- 19. Net electrical energy generated (WeH):
1,348.3' 18,523.4 81,804,456.6 *
- 20. Unit ser' ice factors 53.0 6.8 76.7
- 21. Unit availability factor 53.0' 6.8 76.9
- 22. Unit capacity factor using MDC net:
0.0 0.0 74.9 l
23' Unit capacity factor using DER net:
0.0 0.0 70.8
' 24. Unit forced outage rate:
0.3 0.3 5.6 A
l, 25.. forced outage hours:
1.3 1.3
'8,976.9 l?
l>
r l
- 26. Shutdowns scheduled over next 6 months (type,date, duration): NONE i
{;
27 :lf currently shutdown, estientt'd startup date N/A l.
4
- Cuautative values from.the first criticality (07/24/67) (The remaining cunulative values are f rom the first date of comercial operation, 01/01 co).
i
!l:
.('
SI