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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
[Table view] |
Text
.. . . .- . ._ .. - - . . . _ - . . _ _ . _ _ .
.f i
4 l Connecticut Yankee Decommissioning i Spent Fuel Storage Facility Licensing Basis / Design Basis
! (LB/DB) ;
GRPI-30 l
l Revision Draft
- January 30,1997 d
w I i l
Prepared by h b bV h. Date JA )((
TG. A. J nson - Auxiliaries L6ad Engineer)
Approved by . Date 2!Y/N i
D. Efasbltine - Design Engineering) i 9702180395 970206 PDR ADOCK 05000213 P PDR
CY Decommissioning j Spent Fuel Storage Facility LB/DB GRPI !
Rev.0
, Page1of3
, Goals:
The goal of this effort is to define the LB/DB of the Spent Fuel Storage Facility (SFSF) for CY. The SFSF includes the existing Fuel Pool and all support systems and structures required for safe storage of the existing spent fuel. ,
i
$ i Baln '
l The roles and responsibilities of personnel associated with the process are as follows: I e
. Engineering Director to approve GRPI l
l
. The team leader will be responsible for overall coordination, review and i
, issuance of the deliverables. )
- Support from personnel assigned to the Spent Fuel Pool Island Studies )
will be required and will be assigned ca necessary. l
- Information from the System Reclassification GRPI and the Systems l Categorization activity will be required to complete Revision 0 of the LB/DB of the Spent Fuel Storage Fac;lity (SFSF) for CY.
]
. Information from this GRPI will be required to complete the PSDAR, Spent Fuel Pool Island Studies, Security Plan Revision and Decommissioning !
UFSAR.
. The final report will be prepared, reviewed and approved in accordance with Northeast Utilities Common Engineering Department Instructions (NUC EDI) Procedure 30020 " Engineering Reports"(Latest revision in effect at the time of publication).
Process:
The following steps are those considered necessary to define the LB/DB of the i Spent Fuel Storage Facility (SFSF) for CY.
- List the barriers that preclude exceeding 10CFR20 limits The fundamental Licensing Basis of the SFSF is to ensure that the !
continued storage of CY spent fuel does not result in the release of radiation in amounts exceeding 10CFR20 limits. Spent fuel contains a large inventory of fission products that, if released to the environs in a
CY Decommissioning Spent Fuel Sterage Facility LB/DB GRPI Rev.O Page 2 of 3 short time frame, could exceed limits specified in 10CFR20. In addition, the structural materials of the fuel elements (principally stainless steel and zircelloy) have been activated and contribute to the overall inventory of radioactive material stored in the SFSF. Confinement of these fission and activation products and shielding from the direct radiation being released from these radioactive materials requires a number of barriers to ensure that failure of one barrier will not cause the uncontrolled release of the
- stored activity. The fundamental Design Basis of the SFSF is to protect these barriers. A listing of these barriers provides a benchmark for evaluating the impact that site systems and structures have on the maintenance of these barriers.
- List the Systems Structures and Components (SSC) that comprise the SFSF Once the barriers are identified, a listing of SSC that are required to protect these barriers can be developed. For those systems or structures that also support non-SFSF requirements, boundaries will be defined that includes only those portions required for support of SFSF. The LB/DB for the SFSF will be a compilation of the LB/DB for each listed SSC.
. Document the LB/DB for the Systems and Structures that comprise the SFSF For each of the SSC 1 ted above, the LB/DB will be documented in accordance with ENG 1.7-157, " Documenting LB/DB For Specific Systems, Structures and Components".
- Validate the LB/DB for the SSC that comprise the SFSF Calculations and other design documents will be reviewed to ensure they support the documented LB/DB. Similarly, commitments will be reviewed to ensure they are being satisfied. Procedures will be reviewed to ensure they satisfy the LB/DB. Where discrepancies are identified, these will be resolved in accordance with the Corrective Action Program.
A second validation will be done by comparing the listing of SSC in this document to the listing of SSC in the System Reclassification effort.
- Compare the Systems and Structures that comprise the SFSF against ANSl/ANS 57.7 " Design Criteria for an independent Spent Fuel Storage Installation (Water Pool Type)"
Regulatory Guide 3.49 endorses this Standard for newly constructed Spent Fuel Storage Installations. An SEP-Type evaluation of the existing design and the proposed changes to the existing design necessary to establish the Spent Fuel Storage Building as an Independent Facility will be completed. This evaluation will be documented in a Topical Report. A
CY Decommissioning l Spent Fuel Storage Facility LB/DB GRPI j Rev.0 1 Page 3 of 3 SEP-Type comparison of our existing design and proposed changes against this Standard will provide reasonable assurance that our design will satisfy NU's goal to "...do the right thing..." as well as satisfying any increased scrutiny from the regulator. Any unjustified deviations from the standard will be addressed in changes to the facility as the existing design evolves to an independent spent fuel storage facility. The deliverable will be a Topical Report. !
l l
Interpersonal:
- Open communications are encouraged. Periodic meetings should be conducted to ensure that all group leaders and team members are kept informed and have a forum in which to discuss issues and questions.
- Individual and team self-assessment should be routinely used to ensure I that the LB/DB development is on schedule and continually on track. l Team members are encouraged to bring to the attention of the team i leader any barriers that have the potential to undermine success.
]
. Encourage new ideas and " thinking outside the box" to foster innovation l and creative thinking to solve problems. I e Contact with Licensing will be used to ensure the LB/DB includes the latest License Amendments.
I Tentative Schedule:
2/10/97 List barriers 2/17/97 List Systems and Structures affecting barriers 3/15/97 Document LB/DB for listed systems and structures 4/01/97 Validate LB/DB 5/01/97 Compare original design with ANSI /ANS 57.7 6/01/97 Compare proposed revised design with ANSI /ANS 57.7 6/30/97 Complete final documentation package including Topical Report on ANSI /ANS 57.7 comparison.
