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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14627, Reactor Containment Bldg ILRT Rept. W/1993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept. W/ ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria ML20127E2901993-01-11011 January 1993 Rev 43 to Corporate Organization for Nuclear Incidents (Coni) Procedure Coni 1.02,page 7.2-2 of 2,Figure 7.2, Cero Staff-Managers Annual On-Call Schedule B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20217A6311990-11-14014 November 1990 Rev 0 to Haddam Neck Plant Reactor Containment Bldg Integrated Leak Rate Test ML20058H0611990-10-31031 October 1990 Core Xvi Startup Physics Test Rept ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases 1999-08-24
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20127E2901993-01-11011 January 1993 Rev 43 to Corporate Organization for Nuclear Incidents (Coni) Procedure Coni 1.02,page 7.2-2 of 2,Figure 7.2, Cero Staff-Managers Annual On-Call Schedule ML20248H1601989-10-0202 October 1989 Inservice Test Pump & Valve Program ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML20196A5591989-01-31031 January 1989 Rev 1 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual & Process Control Program B13041, Rev 1 to Haddam Neck Plant Third 10 Yr Interval Inservice Testing Program1988-10-31031 October 1988 Rev 1 to Haddam Neck Plant Third 10 Yr Interval Inservice Testing Program ML20204J1391988-09-0707 September 1988 Temporary Procedure Change 88-504 to Rev 4 to Procedure E-0, Reactor Trip or Safety Injection ML20204J0391988-08-23023 August 1988 Rev 4 to Emergency Operating Procedure EOP 3.1-28, Turbine Overspeed ML20205A3181988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2525, Std Post-Trip Actions ML20205A3341988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2526, Reactor Trip Recovery ML20205A3521988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2528, Electrical Emergency ML20205A3671988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2532, Loss of Primary Coolant ML20205A3831988-08-0303 August 1988 Rev 5 to Emergency Operating Procedure EOP 2534, Steam Generator Tube Rupture ML20205A3941988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2536, Excess Steam Demand ML20205A4011988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2537, Loss of All Feedwater ML20205A4191988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540A, Functional Recovery of Reactivity Control ML20205A6111988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540B, Functional Recovery of Vital Auxiliaries (AC & DC Power) ML20205A6281988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540C, Functional Recovery of RCS Inventory & Pressure ML20205A6651988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540D, Functional Recovery of Heat Removal ML20205B5571988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-3.2, Post-Steam Generator Tube Rupture Cooldown Using Blowdown ML20205B0171988-06-15015 June 1988 Rev 5 to Emergency Operating Procedure EOP 3509, Fire Emergency ML20205B0401988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 E-0, Reactor Trip or Safety Injection ML20205B0521988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 E-1, Loss of Reactor or Secondary Coolant ML20205B1011988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 E-2, Faulted Steam Generator Isolation ML20205B1271988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 E-3, Steam Generator Tube Rupture ML20205B1751988-06-15015 June 1988 Rev 3 to Emergency Operating Procedure EOP 35 ES-0.1, Reactor Trip Response ML20205B2071988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-0.2, Natural Circulation Cooldown ML20205B3681988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-0.4, Natural Circulation Cooldown W/Steam Void in Vessel (W/O Rvlms) ML20205B3831988-06-15015 June 1988 Rev 4 to Emergency Operating Procedure EOP 35 ES-1.1, Safety Injection Termination ML20205B4031988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-1.2, Post-LOCA Cooldown & Depressurization ML20205B4411988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-1.3, Transfer to Cold Leg Recirculation ML20205B4801988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-1.4, Transfer to Hot Leg Recirculation ML20205B5101988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-3.1, Post-Steam Generator Tube Rupture Cooldown Using Backfill 1999-07-31
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Connecticut Yankee Decommissioning
- Design Control Process GRPI l l
1 Revision 0 )
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// W97 Prepared oy: Date:
l V Jeffrey F. Bibby l
Approved by: Date: #[3/I) l y John D. Hase'Itine 9702180392 970206 I PDR ADOCK 05000213 P PDR
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) Design Control Process GRPI l
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- Modify the Design Control process for Connecticut Yankee to fulfill the commitments .
provided in the December 4,1996 Enforcement Conference and provide appropriate !
controls for the " Nuclear Island" and the remainder of the plant activities for decommissioning. j Roles: !
J. Bibby Responsible for overall process development, coordination i of reviews and process implementation. !
l S. Sarver Responsible for providing needed interface with the new ;
FSAR change process. .
S. Milioti Responsible for providing needed interface with the new Safety Evaluation process.
I F. Perdomo Responsible for providing needed interface with the new Licensing Commitment management process.
D. Sabean Responsible for providing definition of systems needed for l decommissioning to support defining applicability of Design i Controls.
S. Weyland Responsible for providing definition of " nuclear island" to support maintenance of applicability definition.
Group ActivityManagers Responsible for review and comment.
QA Reviewer (TBD) Responsible for QA review and comment.
J. D. Haseltine Responsible for manual / procedure approval.
NTD Representative (TBD) Responsible for developing a training program and qualification process.
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, The plant modi 6 cation process will consist of 2 parts. Systems, structures and components
! (SSC's) that are credited at any time to support spent fuel storage operations (e.g; the ,
I
" nuclear island") will be processed in accordance with an updated version of the current
- Design Control Manual. A revision is currently in progress that will incorporate most of L the lessons learned associated with the Virgilio Inspection. A subsequent revision is ;
i required to address all commitments associated with the December 4,1996 Enforcement i j Conference and to reflect the 2 part process. Changes to these SSC's will be defmed by 3 DCR's, MMOD's or MSEE's.
i The second part will be based on YAEC's " Decommissioning Work Package" process (AP-0103). As with this process, certain Decommissioning activities (e.g; removal of the 4
reactor vessel) may be defined by a DCR dependent on the complexity of the activity. l 1
l Starting with the current 5 unit DCM, a CY umque revision will be generated and a new j Decommissioning Work Package procedure will be developed based on the following
! activities:
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- Coordinate with the Design Control Working Group to fmalize the in-progress i " change 1 to revision 3" of the DCM. This change will incorporate the Millstone based
! (Bob Cox) "PI-10" review, many of the lessons learned from the Virgilio Inspection, j and user feedback from implementation of revision 3.
( , !
!
- Coordinate with Tom Miller (YAEC) to gain a full understanding of Yankee Rowe's l process. Differentiate as appropriate between the controls for " nuclear" changes
! versus " commercial" changes. Utilize input from the definition of systems needed for i decommissioning and the plans for the evolution of the " nuclear island" to support this j differentiation.
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- Gain an understanding of the Design Control process used by other plants in some stage of decommissioning (e.g; Trojan), as well as the best practices from operatmg i plants (e.g; Entergy, NYPA and input from INPO and EPRI PSE) to ensure best !
i practices are incorporated.
1 j' * . Ensure all commitments made relative to the composite of the 1996 Inspections are
- fulfilled. (Formal commitments will be established).
4 j
- Coordinate with other group related efforts to update processes such as 50.59 !
Reviews (Steve Millioti), FSAR Changes (Steve Sarver), maintenance of Licensing
- l Commitments (Fred Perdomo), Corrective Actions (Jim Foley), MEPL Determinations 4 (Pete Clark), and Work Identification and Authorization (formerly controlled by the DCM Chapter 2 EWR process).
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- Generation of a CY unique process will require developing CY unique EDI's.
Coordinate with Seabrook and Millstone to transition from the 5 unit EDI manual. ;
! Incorporate other Instructions determined to be appropriate later to facilitate j unplementation.
I
+ e Generation of a CY unique process will also require updates to various NGP's.
Develop and submit PAR's as appropriate once the DCM is approved.
J e Establish training requirements and coordinate with NTD to train members of the Decommissioning staff. :
i The revised, CY unique Design Control process is planned to be complete by 7/1/97 in !
accordance with the attached schedule. ,
4 i
Internersonal:
i The following interpersonal relationship guidelines will be used to maximize efficiency of the effort and avoid duplication ofefforts:
. A liaison has been developed with Yankee (Tom Miller) to ensure best practices are j incorporated from Rowe's decommissioning experiences. Similarly, contacts should be j made with other permanently shutdown plants such as Trojan. ,
- Contact will be maintained with Millstone and Seabrook Design Process Liaisons to ensure enhancements made to their processes are reviewed for applicability.
e Contact will be maintained with other plants in the industry through INPO to ensure
? best practices are incorporated as applicable.
- Decommissioning of nuclear power plants is relatively new with only limited industry l
'. experience. " Thinking outside the box", particularly with regard to non-nuclear, d commercial changes will be encouraged.
- Feedback from the group leads will be maintained to ensure that the Design Control Process fulfills all needs. Periodic meetings will be attended as necessary.
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ee97 1**S ID Task Name Duration NovlDec Jan l Feb l Mar l Apr l May l Jun l Jul l Aug l Sep l Oct l Nov l Dec Jan l Feb l Mar ! Apr l May l Jun l Jul l Aug l Sep 1 Coordusate with the DCWG to 60d DCM Revision 2 CY PORC Approval 7d C Approval 3 Staff Trained to Rev 3/ Chang 7d Rev 3/ Change 1 Training / implementation 4 Coordinate with YAEC for Bes W E YAEC Input 5 Definition of DCM Related C/ 30d ,
5 Closure of C/A Cmi Li as 7d CIA Commitment Completions 7 Ds.4,+a of Decommissio God Dwp Procedure :L. 4c- :
8 Revision of CY/MP DCM 60d DCM Revision Development l' E 9 50.59 Process Cc.@vea 30d 59.59 Prxedure (Steve Niilloti) 10 FSAR Change Process Devel 30d -
FSAR Cwnge Procedure (Steve Sarver) l 11 MEPL Detemunation Process 30d j '. -MEPL P ocedure (Pete Clark) 12 Work identificatxm and Autho 30d EWR Substitute Proceduie l
13 NGP PAR's submitted for Del 7d l'%:eletion PAR's 14 Review and Comment of Prop 30d eview IWlod 15 Disposition of Comments 7d omment Disposition '
16 QA and JDH Approval 1d 1JMt Approval 17 PORC Approvalof Procedure 7d popC Approval 18 Training Program Developme 15d Training l'
19 DCM Effort Complete 1d f[New Process In-Place Upgrade of EDrs 60d 20 l' pY Unique EDrs Development 21 EDI Approvals 7d EDI Approvals l
Task Summary Roned Up Progress N Project:
Progress - RoNed Up Task 7/gg .
Date: Fri 12/27/96 Milestone $ Rolled Up Milestone Q hf/M Page1
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