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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20199L5891997-12-24024 December 1997 Independent Analysis & Evaluation of AM-241 & Transuranics & Subsequent Dose to Two Male Workers at Connecticut Yankee Atomic Power Plant ML20210P8721997-08-31031 August 1997 Post Decommissioning Activities Rept, for Aug 1997 ML20141A0041997-05-31031 May 1997 Independent Assessment of Radiological Controls Program at Cyap Haddam Neck Plant Final Rept May 1997 ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20137C6281997-03-14014 March 1997 Redacted Version of Rev 1 to Nuclear Training Loit/Lout Audit Reviews ML20135E3221997-02-13013 February 1997 Independent Review Team Rept 1996 MP -1 Lout NRC Exam Failures ML20134L2751997-02-0303 February 1997 Draft Rev to GPRI-30, Spent Fuel Storage Facility Licensing Basis/Design Basis ML20134L2911997-01-0808 January 1997 Rev 0 to UFSAR Rev Grpi ML20204B6811996-12-31031 December 1996 Nuclear Lemons Assessment of America Worst Commerical Nuclear Power Plants. 5th Edition ML20237E0751996-12-31031 December 1996 Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant ML20134L2591996-12-31031 December 1996 Rev 0 to Sys Reclassification ML20134L2721996-12-31031 December 1996 Commitment Mgt Grpi ML20134L2481996-12-30030 December 1996 Rev 0 to Sys Needed for Decommissioning Sys Evaluation Process ML20135E2711996-12-26026 December 1996 Evaluation of Intakes by Two Workers at CT Yankee Atomic Power Co ML20134L2841996-12-23023 December 1996 Rev 0 to Spent Fuel Pool Island Studies ML20134L2871996-12-19019 December 1996 Rev 0 to Grpi for Defueled Condition Fire Protection Technical Requirements ML20134L2381996-12-19019 December 1996 Rev 0 to Accident Analysis ML20058G3481993-10-31031 October 1993 Nonproprietary VIPRE/WRB-1 DNBR Thermal Limit for Westinghouse Fuel Types, for Oct 1993 ML20058G6771993-09-29029 September 1993 Rev 0 to Project Assignment 91-006, Connecticut Yankee Event V Mods ML20058L7411993-07-15015 July 1993 QA Svcs Dept Surveillance Rept SS-169, Assessment of Fitness for Duty Program ML20045F3351993-06-30030 June 1993 IPE for Severe Accident Vulnerabilities RA-93-022, Cy Containment Isolation Failure Probability1993-05-18018 May 1993 Cy Containment Isolation Failure Probability ML20127J5391992-11-30030 November 1992 Connecticut Yankee Structural Reevaluation of Plant Structures to Address SEP Topic III-7.B Load Combinations Code Changes ML20125E5661992-03-31031 March 1992 Nonproprietary PWR SG Tube Repair Limits:Technical Support Document for Expansion Zone PWSCC in Roll Transitions Final Rept A08995, Rev 1 to Auxiliary Initiation Event Analysis1990-09-14014 September 1990 Rev 1 to Auxiliary Initiation Event Analysis ML20062G4951990-07-31031 July 1990 Rev 3 to Northeast Utils USNRC Read & Sign ML20055G4951990-07-31031 July 1990 Decommissioning Financial Assurance Certification Rept ML20044A8481990-07-0202 July 1990 Vol 1 to Connecticut Yankee Simulator Certification Submittal:Connecticut Yankee Simulator Design Info & Certification Program Overview ML20055D8931990-06-30030 June 1990 Fracture Mechanics Evaluation:Haddam Neck Pressurizer ML20043A4831990-04-30030 April 1990 Rev 1 to Technical Rept Supporting Cycle 16 Operation ML20012A2281990-03-0101 March 1990 Vol 6 to Probabilistic Safety Study B13388, Zircaloy Clad Fuel Mechanical Design Rept1989-11-30030 November 1989 Zircaloy Clad Fuel Mechanical Design Rept ML20246N9421989-08-31031 August 1989 Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station ML20044G5131989-07-31031 July 1989 Rev 1 to Final Rept J5439-89-001R1, Fluidelastic Instability Analysis of U-Bend Region of Westinghouse Model 27 Sg ML20206J9991988-10-31031 October 1988 Crdr Summary Rept, Per Suppl 1 to NUREG-0737 ML20153G4081988-06-0303 June 1988 Rev 0 to Conneticut Yankee Replace Nuclear Instrumentation Sys, Neo Project Description ML20153G4031988-03-0808 March 1988 Rev 0 to, Connecticut Yankee Modernize Reactor Protection Sys - Phase 2, Conceptual Project Description ML20235B5911987-09-24024 September 1987 Undated Technical Evaluation:Haddam Neck Plant Reanalysis of Non-LOCA DBAs & Tech Spec Change Requests in Support of Reload Cycle 15 B12619, Bimonthly Progress Rept 5:New Switchgear Bldg Const1987-07-31031 July 1987 Bimonthly Progress Rept 5:New Switchgear Bldg Const ML20214R6371987-06-30030 June 1987 Technical Rept Supporting Cycle 15 Operation ML20205Q7011987-04-30030 April 1987 Bimonthly Progress Rept 3:New Switchgear Bldg Const B12480, Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl1987-04-30030 April 1987 Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl ML20238C3751986-12-31031 December 1986 Connecticut Yankee 1986 Core XIII - Xiv Refueling Outage ALARA Rept ML20238C3821986-12-31031 December 1986 Connecticut Yankee 1986 Steam Generator Repair Outage ALARA Rept ML20209C7161986-12-31031 December 1986 Vols 1 & 2 to Isap,Haddam Neck Plant,Final Rept ML20206J8871986-06-30030 June 1986 Isap Public Safety Impact Model Project Analyses Summaries ML20202D5071986-06-30030 June 1986 Non-LOCA Transient Analysis ML20205T1201986-05-19019 May 1986 Steam Generator Tube Insp Rept for 1986 Refueling Outage ML20205T1231986-05-0808 May 1986 Steam Generator Tube W/55% Through Wall Defect Safety Evaluation for Structural Integrity CY-86-031, Rev 1 to 4.10.1(D) Inservice Insp of Steam Generator Tubes (Acceptance Criteria)1986-05-0808 May 1986 Rev 1 to 4.10.1(D) Inservice Insp of Steam Generator Tubes (Acceptance Criteria) 1997-08-31
[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] |
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I CONNECTICUT YANKEE DECOMMISSIONING UFSAR REVISION GRPI Revision 0 January 8,1997 Prepared by'2 O jem Date
/ I E2 (S. (Sarver - UFSAR Lead Engineer)
Approved by Date N9
. d. Hastltine - Design Engineering)
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P PDR
CY DECOMMISSIONING UFSAR Revision GRPI Rev.0 Page 1 of 4 Goals:
The goal of this GRPI is to provide those associated with the decommissioning of j
Connecticut Yankee (CY) the necessary guidance to produce a revised l
Connecticut Yankee (CY) UFSAR that accurately reflects the Licensing Bases and Design Bases (LB/DB) of those Structures, Systems and Components (SSCs) necessary to support the plant as it evolves from cessation of operations I
to a spent fuel storage facility. The UFSAR will also contain the Regulatory Requirements and Programs necessary to support the evolution. The UFSAR will ' e revised to desc-ibe the as-built condition of the plant as it evolves from o
cessation of operations to a spent fuel storage facility.
Roles':
The following states the role of selected groups and individuals associated with the decommissioning of CY.
CY Design Engineering - Overall responsibility for oversight of UFSAR Revisions.
i
- Determine the applicable Regulatory Requirements associated with the plant as it evoives from cessation of operations to a spent fuel storage facility.
Manage the ongoing UFSAR Revision development.
CMP Licensing and Administrative t
CMP UFSAR Group Coordinate the ongoing UFSAR Revision Lead development.
CMP Licensing Identify the licensing commitments applicable to the Commitment Lead plant as it evolves from cessation of operations to a spent fuel storage facility.
CMP Design Group Determine the SSCs and Programs applicable to the plant as it evolves from cessation of operations to a spent fuel storage facility.
Develop the LB/DB of the spent fuel storage facility.
]
CY DECOMMISSIONING UFSAR Revision GRPl Rev.0 1
Page 2 of 4 Process:
The following steps are those considered necessary to define the content of a revised CY UFSAR that represents the plant as it evolves from cessation of 1
operation to a spent fuel storage facility.
Accident Analysis Define and analyze the accidents associated with the plant as it evolves from cessation of operation to a spent fuel storage facility. These accidents will define the Technical Specifications, SSCs, Programs and any Regulatory l
l Requirements that must be retained.
i i
Finalize the design of a spent fuel storage facility l
e It is not necessary that this activity be completed prior to the issuance of the next revision to the UFSAR. It is however, necessary that the UFSAR i
accurately reflects the design when completed.
i Regulatory Requirements j
e identify the Regulatory Requirements required for the plant as it evolves from i
cessation of operation to a spent fuel storage facility. Regulatory l
requirements include General Design Criteria (GDCs), NUREGs,10CFR, etc., and possibly environmental regulations.
l i
4 Revise the UFSAR l
The revised UFSAR will contain information on SSCs and Programs that fit i
into one of the categories described below. The UFSAR contents for each category will be substantially different, depending upon the applicable category. To justify the revised sections, it is necessary that the 10CFR50.59s be evaluated and written to cover activities from cessation of l
operation to removal of the equipment or termination of the program. The l
UFSAR will be revised to specify the abandonment or removal of SSCs, or termination of a program, when the action occurs.
- 1. SSCs and Programs required for a spent fuel storage facility.
The UFSAR contents for this category will consist of normal UFSAR type information where the LB/DB is described in detail. These UFSAR sections are subject to change as the design is nMified.
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CY DECOMMISSIONING UFSAR Revision GRPI Rev.O Page 3 of 4
- 2. SSCs and Programs required for the decontamination / decommissioning process.
The UFSAR contents for this category will c,nsist of information that describes the function of the SSCs or Programs required during the decontamination and decommissioning process. These sections will briefly discuss why the original operating functions are no longer required and what function will be performed during the decontamination and/or decommissioning process. The applicable UFSAR sections will state that when a particular decontamination or decommissioning function has been completed, the SSC can be abandoned and removed, or that the program can be terminated, whichever is applicable.
- 3. SSCs and Programs not required at all.
The UFSAR sections for this category will consist of a discussion of why the SSCs or Programs are not required for the decontamination or the decommissioning process or to support a spent fuel storage facility. These sections will briefly discuss why the original operating function is no longer required. The applicable UFSAR sections will state that the SSC can be
)
abandoned and removed or that the Program can be terminated, whichever is applicable.
Necessary Procedure Changes in order to comply with the actions described in this document, and render the actions specific to CY, Nuclear Group Procedure NGP 4.03, " Changes l
and Updates to Final Safety Analysis Reports for Operating Nuclear Power Plans", will be changed by removing CY from the applicability. The NGP will be replaced with a CY specific Administrative Control Procedure (ACP).
Interpersonal Relations:
The following interpersonal relationship guidelines will be used to improve efficiency of the project and prevent duplication of effoits.
The teams or groups should establish and maintain a liaison with Yankee personnel who have worked on similar areas for the Rowe decommissioning.
Efforts should be taken to learn from Yankee's experience.
CY DECOMMISSIONING l
UFSAR Revision GRPI i
Rev.O j
j Page 4 of 4 l
1 i
t Members of a team or group should maintain open lines of communication.
l Periodic meetings and self assessments within a team or group is strongly i
recommended. These meetings will result in feedback on progress and.
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pitfalls.
I Since several activities contain some degree of overlap, the group leads are.
e encouraged to maintain open lines of communication so that activities
]
between groups is not duplicated.
i g
To ensure that the revised UFSAR is accurate and internally consistent, an Owner and Reviewer Matrix should be developed and issued. The matrix teill assign a single Owner to a particular UFSAR section. The Owner is f
ultimately responsible for the assigned section's accuracy. Several i
Reviewers may be assigned to a particular UFSAR section to assure overall l
consistency.
l
. To assure that all necessary interfaces are established and required i
information is properly exchanged, an interface Matrix should be developed and issued. The matrix will delineate wha' 'oput and output is required to be exchanged between groups.
f UFSAR Revision input l
The following input to the UFSAR Group is required to revise the C r UFSAR 4'
to describe the plant as it evolves from cessation of operation to a spent fuel
)
storage facility.
- 1. SSCs and Programs that are not required at all.
- 2. SSCs and Programs that are required to support decontamination, including specification of the decontamination function to be performed.
- 3. SSCs and Programs required to support a spent fuel storage facility.
1
- 4. LB/DB for a spent fuel storage facility.
- 5. Identification of applicable Licensing commitments, Regulatory Requirements,. Technical Specification changes, UIRs and ACRs.
- 6. 10CFR50.59 Safety Evaluations to support all UFSAR changes.
Docket No. 50-213 B16187 1
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I Haddam Neck Plant Configuration Management Project Schedule Of Activities i
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February 6,1997
03 C CONNECTICUT YANKEE DEFUELED PROJECT SCHEDULE gh az JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC Nk
[
$Q.'$
1997 1997 1 ACCIDENT i
ANALYSIS k__________A m
i a8 a
2 SF HEATUPIDECAY 3 c CALCULATIONS k _ _ _A 55 3 SYSTEMS g ------ g EVALUATION y9O 4 CORRECTIVE ACTION k_________________________________A "a
PROGRAM 3
Ur 5 MANAGEMENT k_________________________________A y-l STANDARDS s
i 6 SYSTEMS k-----------------'----------A RECLASSIFICATION 7 DESIGN CONTROL g ------------------~~------------- g PROCESS t
8 COMMITMENT g -----------------~~-----~~~------ g MANAGEMENT 9
LICENSING BASISI g'-------------------------- ------ g i
DESIGN BASIS 10 QA g ------------~~------------- g PROGRAM 11 SPENT FUEL POOL g~------------------------------------ g ISLAND STUDY 12 FIRE PROTECTION PROGRAM k-___________________________A 13 FIRE PROTECTION TECH REQ MANUAL k____________________________A 14 UFSAR REVISION k______________________________________________A a
r
-