|
---|
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 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections 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 ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification 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/ 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 ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation 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 ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20046C1421993-07-0909 July 1993 Rev 12 to Response to Loss of Secondary Heat Sink ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20045H2271993-05-18018 May 1993 Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection ML20045G7991993-05-0707 May 1993 Rev 1 to Project Plan,Cyap Seismic Upgrade Program for Svc Water Sys,Feedwater Sys & Main Steam Sys Outside Containment B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop 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 ML20046C1421993-07-0909 July 1993 Rev 12 to Response to Loss of Secondary Heat Sink ML20045H2271993-05-18018 May 1993 Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program ML20045G7991993-05-0707 May 1993 Rev 1 to Project Plan,Cyap Seismic Upgrade Program for Svc Water Sys,Feedwater Sys & Main Steam Sys Outside Containment ML20035E5451993-04-12012 April 1993 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual,Including Rev 73 to Table of Contents,Rev 23 to Coni 5.01, On-Call Technical Support Team & Rev 26 to Coni 10.01, Corporate EOC Equipment & Erds.. B14504, Eqe Procedure to Perform Seismic Screening Walkdowns for Main Steam,Feedwater & Svc Water Piping at Cyap1993-04-0202 April 1993 Eqe Procedure to Perform Seismic Screening Walkdowns for Main Steam,Feedwater & Svc Water Piping at Cyap ML20044C1551993-03-15015 March 1993 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure,Including Rev 14 to Coni 4.01,Rev 20 to Coni 4.02, Rev 10 to Coni 8.04,Rev 1 to Coni 10.04 & Rev 1 to Coni 10.05 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 ML20043H9901990-06-0606 June 1990 Electromagnetic Interference (EMI) Test Procedure ST 11.7-51, Reactor Protection Sys EMI Environ Test ML20044A8491990-05-23023 May 1990 Revised Vol 2 to Connecticut Yankee Simulator Certification Submittal:Nuclear Simulator Engineering Manual B13041, Rev 2 to Inservice Testing Program1990-03-29029 March 1990 Rev 2 to Inservice Testing Program 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 .. ML20011F3641989-02-0909 February 1989 Special Test Procedure Spl 10.8-9, Testing of Molded Case Circuit Breakers Per NRC Bulletin 88-010 ML20196A5591989-01-31031 January 1989 Rev 1 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual & Process Control Program ML20011F3621988-12-31031 December 1988 Rev 1 to Preventive Maint Procedure PMP 9.8-88, Testing of Molded Case Circuit Breakers & Motor Circuit Protectors 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 ML20205A3521988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2528, Electrical Emergency ML20205A3831988-08-0303 August 1988 Rev 5 to Emergency Operating Procedure EOP 2534, Steam Generator Tube Rupture ML20205A6111988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540B, Functional Recovery of Vital Auxiliaries (AC & DC Power) ML20205A3671988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2532, Loss of Primary Coolant ML20205A3341988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2526, Reactor Trip Recovery 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 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 ML20205A3941988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2536, Excess Steam Demand ML20011F3601988-08-0202 August 1988 Rev 6 to Preventive Maint Procedure PMP 9.5-41, Testing of Molded Case Circuit Breakers ML20205B4801988-06-15015 June 1988 Rev 2 to Emergency Operating Procedure EOP 35 ES-1.4, Transfer to Hot Leg Recirculation ML20205B7751988-06-15015 June 1988 Rev 3 to Emergency Operating Procedure EOP 35 ECA-0.0, Loss of All AC Power 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
[Table view] |
Text
-
E 1
Connecticut Yankee Decommissioning Design Control Process GRPI l
Revision 0
)
1 l
// W97 Prepared oy:
Date:
l V
Jeffrey F. Bibby l
- [3/I)
Approved by:
Date:
l y John D. Hase'Itine 9702180392 970206 I PDR ADOCK 05000213 P
PDR
i a
)
Design Control Process GRPI i
M 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.
4
?
r 2
)
f.GSSEli 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 reactor vessel) may be defined by a DCR dependent on the complexity of the activity.
l 4
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:
i-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 differentiation.
j l
Gain an understanding of the Design Control process used by other plants in some i
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
. Ensure all commitments made relative to the composite of the 1996 Inspections are j'
- fulfilled. (Formal commitments will be established).
4 Coordinate with other group related efforts to update processes such as 50.59 j
Reviews (Steve Millioti), FSAR Changes (Steve Sarver), maintenance of Licensing
- l Commitments (Fred Perdomo), Corrective Actions (Jim Foley), MEPL Determinations (Pete Clark), and Work Identification and Authorization (formerly controlled by the 4
{
DCM Chapter 2 EWR process).
i!-
l m.
y p.
9
_,y
-g_...
a wy.,=g y
.y.
he
s b
f h
3 i i
- i 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 Generation of a CY unique process will also require updates to various NGP's.
+
e Develop and submit PAR's as appropriate once the DCM is approved.
J Establish training requirements and coordinate with NTD to train members of the e
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.
Contact will be maintained with other plants in the industry through INPO to ensure e
?
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.
J a
4 i
. ~...
.~
~
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'
9 50.59 Process Cc.@vea 30d E
59.59 Prxedure (Steve Niilloti) 10 FSAR Change Process Devel 30d l
FSAR Cwnge Procedure (Steve Sarver) j '.
-MEPL P ocedure (Pete Clark) 11 MEPL Detemunation Process 30d l
12 Work identificatxm and Autho 30d EWR Substitute Proceduie l'%:eletion PAR's 13 NGP PAR's submitted for Del 7d 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 l'
Training 18 Training Program Developme 15d f[New Process In-Place 19 DCM Effort Complete 1d l'
pY Unique EDrs Development 20 Upgrade of EDrs 60d 21 EDI Approvals 7d EDI Approvals l
Task Summary Roned Up Progress N Project:
Progress RoNed Up Task 7/g.
Date: Fri 12/27/96 hf/M g
Milestone Rolled Up Milestone Q Page1
. -