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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217A0001998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Haddam Neck Plant 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 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
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 ML20206F1971998-12-31031 December 1998 Annual Rept for 1998 for Cyap. 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 ML20217P4861997-12-31031 December 1997 1997 Annual Financial Rept, for Cyap 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 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-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-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-1996-016, :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-1996-030, :on 961102,two Workers Received Internal Exposure Which Potentially Exceeded Federal Limits. Caused by Programmatic Breakdown in Administrative Barriers. Restricted Access to Canal/Cavity.Page 15 of 15,withheld1997-09-0505 September 1997
- on 961102,two Workers Received Internal Exposure Which Potentially Exceeded Federal Limits. Caused by Programmatic Breakdown in Administrative Barriers. Restricted Access to Canal/Cavity.Page 15 of 15,withheld
05000213/LER-1994-015, :on 940616,main Steam Safety Valve Pilot Valves Exceeded Lift Setpoints.Caused by Seat Adhesion.Readjusted Setpoints for Pilot Valves MS-V-1613-2B & MS-SV-1613-3A1997-09-0505 September 1997
- on 940616,main Steam Safety Valve Pilot Valves Exceeded Lift Setpoints.Caused by Seat Adhesion.Readjusted Setpoints for Pilot Valves MS-V-1613-2B & MS-SV-1613-3A
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
,
CONNECTICUT Y A N K E P.
AT O MIC POWER COMPANY HADDAM NECK FMNT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 November 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 CY-970-122 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connectbit Yankee liaddam Neck Plant Monthly Operating Report 97-10 covering operations for the period October 1,1997 to October 31,1997 is hereby forwarded.
Very truly yours, Russell A. Mellor 4
Director of Site Operations and Decommissioning Iladdam Neck Station g { n LJ...
k' RAM /bom cc:
(1)
Regional Administrator, Region I h
U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 I
I (2)
William J. Raymond Sr. Resident Inspector Connecticut Yankee o
.e 4
.m l
R
Connecticut Yankee Atomic Power Company 1laddam Neck Plant Iladdam. Connecticut Monthly Operating Report No. 97-10 For The Month of October 1997
Elantfacratine Summary The Haddam Neck Plant has been shut down since July 22,1996 and on December 4, 1996, the Connecticut Yankeu Atomic Power Company (CYAPCO) Board of Directors voted to permanently and immediately cease operations prior to expiration of its license.
The removal of fuel from the reactor vessel started on November 13, 1996.
As of November 15,1996, all fuel assemblies were permanently removed from the reactor and placed in the spent fuel pool for temporary storage.
On December 5,1996, pursuant to 10CFR50.82(a)(1)(i) and iOCFR50.6 s. ',1)(ii),
CYAPCO provided docketed wrtification to the NRC that it has decided to permanently cease operations at the Haddam Neck Plant and that fuel has been permanently removed from the reactor.
CYAPCO submited the Post-Shutdown Decommissioning Activities Report (PSDAR) and the site-specific decommissioning cost estimate in accordance with 10CFR50.82 on August 22,1997.
On October 27,1997 the NRC held an infomational meeting at the Haddam Killingworth High Schoolin Higganum, CT to solicit public comments on the PSDAR.
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, NRC OPERATING STAWS REPORT Haddam Neck
- 1. Dockets 50 213-
- 2. Repcrting Period 10/97 Outage + On line Hours 745.0 +
0,0 745.0
- 3. Utility contact s K.w. Ennons (20D 267 3654
- 4. Licensed Thermal Power.(Wt)* 2825
- 5. Nameplate Arging (Gross Wels 667 x 0.9
-6 Des' m diectrical Rating (Not We!s 582
-1.
Ma
.mm Dependable. Capacity (Gross We) t 586.9
- . Maximum Dependable Capacity (Not Wel 3 560.1
- 9. If changes occur above since last report, reasor.s are: M it
- 10. P>wer level to which restricted, if any (Net We): N/A 11, Reasons for restriction, if any: N/A MONTH U..R TO.DATE Ct.HULATIVE
- 12. Report period hours:
745.0 7,296.0 261.528.0
- 13. Hours reactor critical
- 0. 0 -
0.0 199,493.6
- 14. Reactor reserve shutdown hours:
0.0 0.0
- 1..* 0 5. 0
- 15. Hours generator on line 0.0 0.0 193.539.3
- 16. Unit reserve shutdown houest 74s.0
%7,295.0 8.341.0
- 17. Gross thermal energy generated (WtH) 0.0 0.0 335.551,124.0 *
- 18. Cro's electrical energy generated (WeHl 0.0 0.0 110,009,804.0 *
- 19. Net electrical energy generated (WeHl:
-1,314.4
-13,832.3 104,500,691.3
- 20 Unit servtce f actori 0.0 0.0 74.0
- 21. Unit availabtllty factor 99.9 100.0 77 3
- 22. (nit capacity f actor uslag MDC net 0.0 0.0 12.1
.23. Unit capacity factor using DER nets-0.0 0.0 68.7
- 24. Unit forced outage rate:
0.0 0.0
-6.3 2 5.: Forc'd-outage hoursi 0.0 0.0 12,970.0 3J. Shutdowns scheduled over next 6 months (tyoe,date, duration; NONb
- 27. If current 1 shutdown, estimated startup dates N/A l
-1 l
I
- e cumulative values f rom the first criticallyyy/24 /67). (The remaining cumulat3ve values are from the first date of
-icommercialoperat' ton,01/olfs,3,
.J a.
- u
-. ~.
- 7.,.-, y
.e d ;.. s -
.+ e
+
1 -
s
.+,
~. -..
w-.
e CLWJTWE REPORT 10/97 CtMJ'JTIVE
- 1. Report rettoi hourst 265,392.0
- 2. h re generator on line, 195,0s3.9
- 3. Hours reactor etaticali 201,702.3 4.
On line net elect rical energy generated (MWeH):
104,74b,s54.2
- 5. Of f-line st ation service electrical energy utilised (MWeH) e 26*,735.5
- 6. Transf orwier losses (MWelt),
276,153.1
- 7. Effective full power dayss 7,734.1
- 9. Ef f ective f ull p<rver hours,
185,617.3
- 9. Cot'e 14srn-u[: (MWtC"PrNii 218.701.8 10 " umber of spector shetdownss 307 Note; all values at. cumulative f rom the first criticality !C104 hrs. 07/24/67).
AVERAGE DAILY POWER LEVEL
- 4 Docket No:
50-213 Unit: Haddam Neck Date:
11/12/97 Completed by:
K.W. Emmons Month: Oct-97 Telephone: (860)447-1791 X6572 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DM (MWe-Net)
DM (MWe-Net; 1
0 17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
1C 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
l
4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-213 UNIT NAME lindram Neck DATE 11/01/97 COMPLETED BY K.W. Emmons TELEPHONE 1860) 447-1791 X6572 l
REPORT MONTH October 1932 No.
Date Typn1 Duration Reason 2 Method of License System Component -
Cause & Corrective (Hours)
Shutting Event Code 4 Codc5 Actiran to Down Reactor 3 Report #
Prevent Recurrence 96-05 07/22/96 S
745 F
4 N/A N/A 1F: Forced 2 Reason 3 Method 41EEE Standard 805 1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual
" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System Identificaticn in C - Refueling 3 - Automatic Scram Nuclear Power Pl ants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E Operator Training & License Examination 5 - Power Reduction (Duration = 0)
F - A'ministrative 6 - Other (Explain)
SIEEE Standard 805A-1983, G - Operational Error (Explain)
" Recommended Practices
1 s
9 I
H + Other (Explain) for Unique identification in-Power Plants and Related -
Facilities - Component Function Identifiers"
I REFUELING INFORMATION REQUEST October 1997 1.
Name of the facility:
Haddam Neck _
2.
Scheduled date for next refueling outage: n/a (decommissioningl 3.
Scheduled date for restart following refueling: n/a (decommissionin;g 4.
(a)
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
DL3 (b)
If answer is yes, what, in general, will these be?
nLa (c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?
n/a (d)
If no such review has taken place, when it it scheduled?
nla 5.
Scheduled date(s) for submitting licensing action and supporting information:
nLa 6.
Important licensing considerations associated with refueling, e.g., new or different fuel dasign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
DLa 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core: (a) Q In Spent Fuel Pool: (b) J 019 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemb!ies:
Etesant storage caoacitv: 1480 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
DLa
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