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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 ML20237E0751996-12-31031 December 1996 Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant ML20204B6811996-12-31031 December 1996 Nuclear Lemons Assessment of America Worst Commerical Nuclear Power Plants. 5th Edition 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 ML20134L2381996-12-19019 December 1996 Rev 0 to Accident Analysis ML20134L2871996-12-19019 December 1996 Rev 0 to Grpi for Defueled Condition Fire Protection Technical Requirements 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 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 ML20055D8931990-06-30030 June 1990 Fracture Mechanics Evaluation:Haddam Neck Pressurizer ML20246N9421989-08-31031 August 1989 Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station 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 ML20209C7161986-12-31031 December 1986 Vols 1 & 2 to Isap,Haddam Neck Plant,Final Rept ML20238C3821986-12-31031 December 1986 Connecticut Yankee 1986 Steam Generator Repair Outage ALARA Rept ML20238C3751986-12-31031 December 1986 Connecticut Yankee 1986 Core XIII - Xiv Refueling Outage ALARA Rept ML20202D5071986-06-30030 June 1986 Non-LOCA Transient Analysis ML20206J8871986-06-30030 June 1986 Isap Public Safety Impact Model Project Analyses Summaries 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) ML20138B2001986-03-31031 March 1986 Status of Containment Integrated Leak Rate Test Program ML20138B1831986-03-31031 March 1986 Schedular Exemption Requests Re Type C Leak Testing ML20138B1561986-03-31031 March 1986 Permanent Exemptions Re Types a & C Leak Testing ML20199L0731986-03-31031 March 1986 Probabilistic Safety Study,Northeast Util Svc Company Evaluation of Probabilistic Safety Study Results B12020, Summary of Results of Haddam Neck Probabilistic Safety Study1986-03-31031 March 1986 Summary of Results of Haddam Neck Probabilistic Safety Study ML20155E7591986-02-28028 February 1986 Best Estimate LOCA Analysis, Vol 5 CY-85-062, Rev 2 to Steam Generator Tube Sleeving & Plugging1986-01-22022 January 1986 Rev 2 to Steam Generator Tube Sleeving & Plugging 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 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 ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co 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 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 ML20217F0611998-03-31031 March 1998 Historical Review Team Rept ML20217A0001998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Haddam Neck Plant 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 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 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 ML20210P8721997-08-31031 August 1997 Post Decommissioning Activities Rept, for Aug 1997 ML20217Q3171997-08-31031 August 1997 Addl Changes to Proposed Rev 1 to QA Program ML20210U9301997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Haddam Neck Plant CY-97-082, Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys1997-08-14014 August 1997 Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys 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 ML20141A0041997-05-31031 May 1997 Independent Assessment of Radiological Controls Program at Cyap Haddam Neck Plant Final Rept May 1997 ML20140H5241997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Haddam Neck Plant ML20141K4201997-05-22022 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-61 ML20141D4141997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Connecticut Yankee Haddam Neck ML20138G5901997-04-25025 April 1997 Proposed Rev 1 to Cyap QA Program for Haddam Neck Plant ML20137W8051997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Haddam Neck Plant 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 ML20137A0801997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Haddam Neck Plant ML20135C5101997-02-26026 February 1997 1996 Refuel Outage ISI Summary Rept for CT Yankee Atomic Power Co B16268, Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor1997-02-19019 February 1997 Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor 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 ML20138K5721997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Haddam Neck Plant.W/ ML20134L2791997-01-10010 January 1997 Rev 0 to QA Program Grpi ML20134L2911997-01-0808 January 1997 Rev 0 to UFSAR Rev Grpi ML20134L2721996-12-31031 December 1996 Commitment Mgt Grpi 1999-04-28
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- Connecticut Yankee Decommissioning l
Systems Needed For Decommissioning l System Evaluation Process 1
1 j GRPI
- Revision 0 4
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' Prepared by: h Date: #z-30-96 Duncan A. Sabean 0
Approved by: M/ Date: /1/ M (
fohn D. Hasfitine 9702180381 970206 I PDR ADOCK 05000213
'A P PDR
= ___ - . _ . - - , _. . .__ .
I I
I Systems Needed For Decommissioning
, System Evaluation Process GRPI Revision 0 GOAL The goals of this effort are to:
- 1. Define the system evaluation process.
- 2. Implement the process to determine which of the current plant systems are required and which are not required for plant decommissioning.
i
- This includes placing systems in the following classifications
l e Operable i e Available / Operational ,
e Isolated /In Lay-up l e Abandoned i
I-J' ROLES i The following groups are responsible for activities I through 5, which are identified in the Process section below: i i 1 Activity Resnonsible Groun(s) '
- l. Tech Support System Engineers and SROs
- 2. Tech Support System Engineers and SROs
- 3. Tech Support System Engineers
- 4. Design Engineering and Licensing
- 5. Design Engineering Additional roles and responsibilities for this GRPI are as follows:
- Engineering Director to approve GRPI and provide resource allocation to ensure completion of project in a timely manner. ,
e Tech Support and Design Engineering to revise WCM 2.2-11, presently titled,
" Disposition ofInfrequently Used and Abandoned Equipment", which will control this process.
- PORC to approve the final package.
PROCESS Refer to Attachment 1, "Requimd Plant System Screening Process for Defueled Condition". The process will consist of the following activities:
- 1. Review every plant system and initially determine classification.
- 2. Review and mark-up P& ids for each system using the classifications and corresponding color codes, per WCM 2.2-11, Rev 1 (under draft). Each System Engineer will identify interfaces and insure consistency with interfacing System Engineer.
- 3. Define and document the bases for each system classification per WCM 2.2-11, Rev 1 and include as a package with the marked up P& ids.
- 4. Screen classification packages for acceptability, including the following activities:
- Determine if any Design Basis / Licensing Basis commitments are affected.
- Determine system interface acceptability, e Identify and mark-up electrical / instrumentation requirements on P& ids and one line diagrams.
- Prepare / complete dependency trees (See Attachment 2 for a draft sample).
- Prepare finalized system classifications.
- 5. Collate all system classification packages for PORC approval per WCM 2.2-11, Rev 1.
Note: As a trial run to test the process, four systems will be selected that encompass all
. classifications and activities 1 through 4 above will be completed for each.
(Service Water, Auxiliary Feedwater, Boric Acid, and Reactor Coolant)
The system evaluation process (i.e., the " Systems Needed for Decommissioning" activity) will provide vital input to the following activities identified in the Decommissioning Activities Matrix:
e System Reclassification
. Maintenance Rule e _ RCS Decontamination Study e Dismantling
. Fire Protection e Energy Efficiency e UFSAR Revision e PSDAR Development This process will also provide input to the overall decommissioning schedule and cost estimate.
1 1
INTERPERSONAL The following interpersonal relationship guidelines will be used to improve the efficiency j of the system evaluation process:
- All interested organizations will be included in the preparation of the GRPI, the j WCM revision, and the classification of systems.
. Communication will be made with Yankee personnel who have worked on similar areas for the Rowe decommissioning in an effort to learn from their experience.
. Frequent meetings will be held with personnel from groups having key roles in the i process to maintain open lines of communication between the groups. ,
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ATTACHMENT 1 Required Plant System Screening Process for Defueled Condition JLD 12n7 System Evaluation Systems decom./ Process 4 defueled lists. Need ; ,
PORC Review '
V is system operability Comply with all Has Tech Spec required by Tech yes u applicable PMs, operability r surveillances, etc.
requirements >yes Specs? Jg changed?
no l Y Define / perform applicable 4 "
Does system need to PMs, testing and be available in future 7 yes inspection requirements to permit future operation.
no no Y p Process abandoned is equipmTnt currently Has need for systems per WCM-2.2- yes u future system beir.g used? yes 11, Group Iand 7 operabiliy abandon in place. changed?
Verify that abandoned no fluid systems are drained; abandoned Y d electrical systems are Based on !ayup, maint., y and freeze protection is system part of de-energized.
requirements, process per the Nuclear Island? -
WCM 2.2-11, Group 11 _
V equipment, if feasible. no Formal approval by Consider NOP 2.0-4, Layup Conditions of PDCR and 50.59 necessary prior to Systems / Components. yes V dismantling. Note that Continue applic.
dismantling will not be maint, surv. and V
performed under WCM u layup until formally F '
2.2-11.
tumed over to decom. organiz.
Notes: 1) WCM 2.2-11 is the abandoned equipment procedure. It applies to Group i equipment, which is no longer used and not intended to be used in the future, and Group 11 equipment, which may be used in the future and should be maintained on a minimal basis, either in place or in storage.
- 2) NOP 2.0-4 defines layup conditions for systems and components.
It should be used when specifying layup requirements for equipment which may be used in the future.
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- . . . - . . . .. - .. .-. - . . - . - u.. -
ATT 7HMENT 2 SPENT FUEL POOL SUPPORT SYSTEMS SPENT FUEL POOL .
S YARD CRANE --
[L '
I
......l.....3 BUILDING I I I I SFP MAKEUP I
SPENT FUEL SFP VENT. ! INSTRUMENT: LIGHTING FIRE 4
- .............j HEAT POOL COOL & PURIF PROTECTION
EXHA ST HEATING STM C T ELEC PWR PURIF SYS MAKEUP ELEC PUMP D L 3g C P WCC 2 I I
ELEC PWR P MA Y ELEC PWR FUEL OIL
~~-
MCC 8 MCC 5 MCC 2 BUS 4 BUS 6 ,
l I CLCSED
- FILTERS F.O.SYS COOLING ELEC PWR ELEC PWR :
WA"ER g !
MCC 8 N/A l l MCC 3 :
STACK ELEC PWR ELEC PWR ECOLOCHEM MCC 5 BUS 4 MCC 3 BUS 6 t l
Bt S 11 ELEC PWR l uCC7 4
4
- __.E_R_J SERVICE i _ _WAT
_L _ _WELL l WATER . ..
WELL WATER ELEC PWR !
f ELEC PWR f MCC 3 I L
_.__._-mm.--.m_ _ . _ . - _ _ _ _ . _ _ _ _ _ . _ _ . _ _ -__ __---m--.,.--v.__._,,.r -
i~,.e -- ,..-... ,-.-- .. ,w.,.-,,.-.-.._.,,-~.~.,.,,--.-,...w. . , , - - . . . . . - . . - , . . , , _ . . . -
-. . - . --.v,,,