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The following 200 pages are in this category, out of 26,789 total.
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- A06968, Responds to NRC 871215 Request for Addl Info on SEP Topic III-6, Seismic Reevaluation & Clarifies Questions Raised During 880406 meeting.W/13 Oversize Drawings
- A07040, Submits Results of long-term Analysis Per Commitment in 880324 Response to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes
- A07110, Responds to NRC 880303 Request for Addl Info Re How Util Will Maintain Facility for Remaining Lifetime within Conditions Assumed for ATWS Analysis.Process in 10CFR50.59 Will Govern All Mods
- A07122, Forwards Addl Info in Response to IE Bullentin 85-003 Re motor-operated Valve Common Mode Failures.Water Hammer Due to Valve Closure Not Considered in Determination of Pressure Differentials
- A07129, Responds to NRC Re Violations Noted in Insp Rept 50-213/88-01.Corrective Actions:New Format to Clarify Data Recording Has Been Developed & Will Be Implemented Generically on All Inservice Tests
- A07155, Responds to NRC Re Violations Noted in Insp Rept 50-213/87-28.Corrective Actions:Affected Motor Disassembled, Inspected,Degreased,Reassembled W/New Bearings & Retested
- A07250, Forwards Addl Info Re Third 10-yr Interval Inservice Testing Program,Per NRC 880511 Request.Revised Third 10-yr Inservice Testing Program Will Be Submitted by 880901
- A07407, Forwards Response to NRC Re Violations Noted in Insp Rept 50-213/88-12.Response Withheld (Ref 10CFR73.21)
- A07433, Proposed Tech Specs Re Leakage Detection Sys
- A07615, Forwards Response to 881021 Request for Addl Info Re Tech Spec Changes for Generic Ltr 83-37
- A07780, Comments on NRC 890123 SER Approving Inservice Insp Program, Third 10-yr Interval,Rev 1.Util Will Upgrade Classification of Svc Water Supply & Return Lines to Containment Air Recirculation Fan Coolers to ASME Class 2
- A07863, Forwards Addl Info Supporting NRC Review of Atws/Auxiliary Feedwater Sys in Compliance w/10CFR50.62(c) & Westinghouse Generic Package Described in WCAP-10858P-A,Rev 1,Section 2-3,per 890302 Request
- A07884, Responds to NRC Re Violations Noted in Insp Rept 50-213/89-01.Corrective Actions:Procedure ACP 1.0-57 Revised to Require Dept Removing Equipment Labels for Maint to Return Labels to Operations Dept
- A08061, Responds to NRC Re Violations Noted in Insp Rept 50-213/89-05.Corrective Actions:Valve PW-V-600 Placed in Locked Close Position & Labeled as Containment Isolation Valve & Procedures Re Containment Integrity to Be Reviewed
- A08899, Responds to NRC Re Unresolved Item Noted in Insp Rept 50-213/90-08.Corrective Actions:Radiation Detector Installed in Control Room Ventilation Sys
- A08995, Rev 1 to Auxiliary Initiation Event Analysis
- A10848, Forwards Copy of Agreement Entered Into Between Northeast Utilities & PM Blanch,In Response to 930211 Request. Agreement Withheld,Per 10CFR2.790
- A30009, Lighting - Schedules,Notes,Symbols & Details, as-built. Sheet 9
- A40314, Pressure Switch Data Sheet. Sheet 3 of 6
- A97001, Responds to NRC Re Violations Noted in Insp Repts 50-295/96-14,50-304/96-14,50-295/96-17 & 50-304/96-17. Corrective Actions:Equipment Attendant Removed from Assigned Duties
- A97002, Responds to NRC Re Violations Noted in Insp Repts 50-295/96-11 & 50-304/96-11.Corrective Actions:Clarifed Mgt Expectations to Workforce,Revised Procedures & Conducted Enhanced Safety Evaluation Training.Payment Encl.W/O Encl
- A97003, Responds to NRC Re Violations Noted in Insp Repts 50-295/96-20 & 50-304/96-20.Corrective Actions:Training Dept Will Include Discussion of Event in Licensed & non-licensed Operator Training Programs
- A97004, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-08 & 50-304/97-08.Corrective Actions:Will Develop Standard Method of Verification for Audits Prior to Next Performance of Each Audit
- A97005, Forwards Response to Violations Noted in Insp Repts 50-295/97-09 & 50-304/97-09.Corrective Actions:Unsecured Hoses & Cords of Concern Secured According to Station Procedures
- A97006, Provides Copy of Addendum to Renewal of NPDES Permit IL0002763
- A97010, Requests Authorization for Alternative to One Time Augmented Insp of RPV Shell Welds Set Forth in 10CFR50.55a(g)(6)(ii) (A)(2) Per 10CFR50.55a(g)(6)(ii)(A)(5).Authorization to Use Partial Insp Coverage Requested
- A97012, Requests Authorization to Use Alternative to Repair & Replacement Requirements Specified in 10CFR50.55a(g)(4)(v) for Class Mc & CC Pressure Retaining Components & Integral Attachments
- A97013, Transmits Request for Authorization to Use Alternative Requirements of Article IWA-5242(a) for Insp of Rv Flanges During Current Unit 1 & 2 Outages Z1R15 & Z2R14
- A97014, Responds to RAI Re Third Interval ISI Relief Request CR-13 & New Relief Request CR-23
- A97016, Provides Response to 970107 RAI Concerning Containment Coatings at Plant
- A97018, Provides Current Status of Outstanding NUREG-0737,Item II.D.1 Issues.Calculations Associated W/Unit 2 Porvs,Encl
- A97019, Updates Record Copy of Current TS Markup,Accompanying Discussion of Differences,Nureg Mark Ups & No Significant Hazards Evaluation Changes to Reflect Recent Review & Comments by Both Util & NRC Personnel
- A97020, Informs That Pf Cantwell,Jk Duff & J Powers No Longer Need to Maintain Operator Licenses at Plant
- A97023, Provides Response to NRC RAI for Addl Info Re Mod Necessary to Address Issues Identified in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions
- A97025, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-21 & 50-304/97-21.Corrective Actions:Two Operating Personnel Received Remedial Training & Passed Radioactive Matl Shipping Level 1 Training Course & Revised Procedures
- A97027, Monthly Operating Repts for June 1997 for Zion Generating Station,Units 1 & 2
- A97028, Submits Withdrawal of 10CFR50,App R Exemption Requests. Listing of Util Commitments Made in Submittal,Encl
- A97030, Special Rept:On 970625,2B EDG Starting Air Train a Failed. Caused by Air Compressor Dryer 4 Way Selector Valve Sticking & Causing Compressor to Be Dead Headed.Valve Was Repaired & Train Was Tested Satisfactorily
- A97031, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-03 & 50-304/97-03.Corrective Actions:Revised Procedure PT-19,installed Mod to Isolate Vpc from Fhb When Wall Is Down & Enhanced 10CFR50.59 SE Process
- A97032, Provides Clarification of Uncertainties of RHR Operation During Nitrogen Gas Accumulation Event on 970307
- A97036, Monthly Operating Repts for Jul 1997 for Zion Generating Station,Units 1 & 2
- A97037, Responds to NRC Re Violations Noted in Insp Rept 50-295/97-12.Corrective Actions:Revised Station Procedures Which Required Enhancements & Completed Preventive Maint on Sequence Timers Using Electrical Maint Procedure E023-1
- A97038, Forwards Corrections for Mar & Apr 1996 & Jul 1997 Operating Status Repts for Zion Generating Station
- A97040, Forwards Response to NRC Re Violations Noted in Insp Repts 50-295/97-13 & 50-304/97-13.Corrective Actions: Operations Manager Met W/Each Shift Manager & Other Key Supervisors to Point Out Accountability Re Overtime
- A97043, Special Rept 295-201-97-SCAQ00751:on 970813,EDG Tripped Immediately on Starting W/Indication Electronic Governor Speed Sensing Failure.Caused by Magnetic Pick-up Signal Selector Failing.Replaced Mpu Selector Switch
- A97047, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-20 & 50-304/97-20.Corrective Actions:Will Develop, Document & Issue Written Expectations Which Enhance Surveying & Posting Contaminated Areas by 971124
- A97050, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-13 & 50-304/97-13.Corrective Actions:Issued Nuclear Operations Notification to Other Comed Nuclear Facilities & Will Review & Evaluate Training Re Procedures
- A97051, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-17 & 50-304/97-17.CAs:unescorted Access Was Placed on Temporary Hold for Director of Fire Protection,Fire Marshal & 2 Firewatch Supervisors Pending Investigation
- A97052, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-02,50-304/97-02,50-295/97-07 & 50-304/97-07, Respectively.Corrective Actions:Placed Both Units in Cold Shutdown & Removed Operators Involved in Event
- A97055, Forwards Supplemental Info to Annual 10CFR50.46 Rept Re Changes to or Errors Discovered in Acceptable ECCS Cooling Performance Evaluation Model
- A97058, Monthly Operating Repts for Sept 1997 for Zion Generating Station,Units 1 & 2
- A97061, Informs NRC of Rev to NOV Commitment Made in Responding to Violations Noted in Insp Repts 50-295/96-06 & 50-304/96-06.Test Requirements Are Now Assigned from post- Maint Testing Matrix During Work Planning Effort
- A97062, Suppls Previous Submittals W/Proposed Change to LCO 3.3.1 & 3.3.2,adding Info to Bases to Specifically Identify Refs Used in Determining Allowable Values
- A97063, Special Rept 295-123-97-002SR:on 971014,failure of 1B EDG Occurred.Exam of Nipple Fractured Surface Revealed Failure Occurred Through Thread Root.Unit 1 Defueled & Unit 2 in Mode 5 Throughout Event
- A97067, Provides Detailed Response as Committed to in Util Ltrs to NRC & 1103 Re Violations Noted in Insp Repts 50-295/97-19 & 50-304/97-19.Corrective Actions:Sys Engineering Personnel Briefed on Need to Ensure Offsite Svc
- A97068, Forwards Independent Investigation Rept Assessing Safety Conscious Work Environ at Zion Station.Rept Details Team Investigation,Conclusions & Basis for Conclusions,As Requested in
- A97069, Monthly Operating Repts for Oct 1997 for Zion Station,Units 1 & 2
- A97071, Provides Response to Request for Addl Info for Evaluation of Third 10-yr Interval Insp Program Plan Request for Relief CR-25,per NRC
- A97073, Forwards Zion Station Unit 2 SG ISI Results,Fall 1996 Refueling Outage 14 (Z2R14). List of Commitments Made in Submittal,Attached
- A97074, Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance Provided in NUREG-1431 to Produce Set of Improved TSs for Zion Station
- A97075, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-22 & 50-304/97-22.Corrective Actions:Configuration Control Root Cause Investigation Was Completed in Nov 1997
- A97076, Monthly Operating Repts for Nov 1997 for Zion Station,Units 1 & 2
- A97079, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-26 & 50-304/97-26.Corrective Actions:All Other R-key Doors in Building Were Verified Closed & Locked
- A98001, Withdraws Three Applications to Amend App a (TS) to Licenses DPR-39 & DPR-48.Requested Amends Proposed Changes to Ts. Determined That Amends Are No Longer Needed
- A980012, Requests Exemption from 24 Month UFSAR Until 981231.Detailed Discussion of Proposed Exemption,Evaluation Against Criteria of 10CFR50.12 & Commitments,Encl
- A980025, Discusses Applicable Regulations,Disposition of Commitments & Sys Required Following Permanent Shutdown & Defueling of Plant.Listing of Commitments Encl
- A98004, Monthly Operating Repts for Dec 1997 for Zion Station,Units 1 & 2
- A98007, Requests Exemption from Requirements of 10CFR70.24, Criticality Accident Requirement. Commitments Made by Util,Encl
- A98008, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-25 & 50-304/97-25.Corrective Actions:Revised Procedure SOI-61F to Reflect Need to Verify Position of 2MOV-SW0023 & Revised Procedure PT-10-3 to Provide Guidance
- A98009, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-02 & 50-304/97-02.Corrective Actions:Wa Pope Raychem Training Documentation Was Reviewed for Contractor Electricians Who Installed Raychem Splice on 970724
- A98010, Requests That Initial Operator License Exams Scheduled for Wks of 980209 & 16 Be Cancelled.Util Formally Withdraws All Individual License Applications Associated W/Exams
- A98013, Requests NRC Approval of Certified Fuel Handler Training & Retraining Program.Copy of Zion Proposed Certified Fuel Handler Training & Retraining Program Contained in Attachment a
- A98015, Monthly Operating Repts for Jan 1998 for Zion Station,Units 1 & 2
- A98016, Application for Amends to Licenses DPR-39 & DPR-40,restoring Plant Custom TS Replaced by Improved TS by Previous Amend & Reinstating License Conditions Deleted by That Previous Amend
- A98017, Forwards Response to Violations Noted in Insp Repts 50-295/98-03 & 50-304/98-03.Corrective Actions:Monitor in Question Was Correctly Calibrated
- A98018, Informs NRC That Numerous Open Items on Zion Station Docket May Be Closed on Permanently Shutdown Status of Both Units.Commitments Encl
- A98020, Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS
- A98024, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-02 & 50-304/97-02.Corrective Actions:Pmt,Pt 10-3, Containment Isolation Phase B Testing, Was Assigned to WR 960104192 at Time of Failure on 971202
- A98026, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-32 & 50-304/97-32.Corrective Actions:Disciplined Individuals Involved & Distributed Ltr to Personnel Discussing Event & Lessons to Be Learned
- A98029, Monthly Operating Repts for Feb 1998 for Zion Station,Units 1 & 2
- A98033, Monthly Operating Repts for Mar 1998 for Zion Station,Units 1 & 2
- A98034, 1997 Annual 10CFR50.59 Summary Rept
- A98035, Monthly Operating Repts for Apr 1998 for Zion Station,Units 1 & 2
- A98038, Forwards LER 98-S02-00 Which Is Being Submitted as Voluntary Security Event Rept.Commitments Made by Util,Listed in Attachment B
- A98039, Monthly Operating Repts for May 1998 for Zion Generating Station,Units 1 & 2
- A98041, Monthly Operating Repts for June 1998 for Zion Nuclear Station,Units 1 & 2
- A98042, Monthly Operating Repts for July 1998 for Zion Station,Units 1 & 2
- A98047, Forwards Revised Scope of One Commitment Contained in Response to NOV
- A98048, Monthly Operating Repts for Aug 1998 for Zion Station,Units 1 & 2.With
- A98049, Special Rept 304-123-98-001SR:on 980902,valid Failure Rept for 2A EDG Occurred.Cause Unknown.Util Submitted Written Certification of Permanent Cessation of Operations at Zion Station,Units 1 & 2
- A98050, Forwards Zion Station Special Rept Number 30412398002SR.Rept for Reporting Period of Jan 1996-Dec 1997.Attachment B Provides Listing of Commitments Contained in Submittal
- A98051, Forwards List of Revised Regulatory Commitments Which Were Evaluated as Satisfactory Using NEI Commitment Change Methodology
- A98052, Monthly Operating Rept for Sept 1998 for Zion Nuclear Power Station,Units 1 & 2.With
- A98053, Forwards Change Instructions for Update to Zion UFSAR, Rewritten to Reflect Permanent Defueled Condition of Plant. & DSAR,
- A98055, Forwards List of Revised Regulatory Commitments Which Were Evaluated as Satisfactory Using NEC Commitment Change Methodology
- A98056, Forwards List of Revised Various Commitments Originally Contained in Util to Nrc.Changes in Commitments Were Satisfactorily Evaluated Using NEI Commitment Change Methodology
- A98057, Monthly Operating Repts for Oct 1998 for Zion Nuclear Power Station,Units 1 & 2.With
- A98059, Forwards Page Change Instruction for Aug 1998 DSAR for Zion Nuclear Power Station,Units 1 & 2.Instruction Was Omitted from 981110 DSAR Due to Administrative Error
- A98062, Monthly Operating Repts for Nov 1998 for Zion Nuclear Power Station,Units 1 & 2.With
- A99001, Forwards Zion 1998 Annual Rept of Revised Regulatory Commitments
- A99002, Monthly Operating Repts for Dec 1998 for Zion Nuclear Power Station,Units 1 & 2.With
- A99009, Forwards Znps Annual Occupational Exposure Rept, for Exposures Occurring in 1998.Listing of Commitments Contained in Ltr Provided as Attachment B
- A990101, Monthly Operating Repts for Feb 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99011, Responds to NRC Re Violations Noted Insp Repts 50-295/98-02 & 50-304/98-02.Corrective Actions:Uncontrolled Safeguards Documents Were Immediately Taken Into Possession & Controlled by Plant Security Supervisor
- A99012, Radioactive Effluent Release Rept for 1998. with
- A99013, Monthly Operating Repts for Mar 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99014, Provides Description of Actions Comed Has Taken to Reinforce Safety Conscious Work Environ at Zion Nuclear Power Station
- A99016, Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99017, Annual Radiological Environ Operating Rept
- A99018, Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold
- A99019, Monthly Operating Repts for May 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99021, Monthly Operating Repts for June 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99022, Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99023, Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station
- A99026, Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With
- Allens Creek
- Allied-General Nuclear Services
- AmerGen
- ASLBP 22-974-01-LT-BD01, Certification of Record to Commission (LBP-23-05)
B
- B10525, Discusses Mods to Assure That Control Room Remains Habitable Under All Accident Conditions Per TMI Action Item III.D.3.4. Radiation Detector in Outside Air Intake & Smoke Detector in Control Room Air Intake Should Be Included
- B10532, Forwards Revision 8 to Modified Amended Security Plan. Revision Withheld (Ref 10CFR2.790 & 10CFR73.21(b))
- B10755, Forwards Public Version of Rev 13 to Emergency Plan Implementing Procedures EPIP 1.5-2, Notification & Communication & EPIP 1.5-41 Re Core Damage Estimate.W/O Procedure 1.5-41
- B11103, Forwards Draft Exercise Controllers Manual for 840512-14 full-scale Emergency Preparedness Exercise at Plant
- B11313, Submits Addl Justification or Clarification for 10 Open Items from SER for SEP Topic III-5.A, High Energy Pipe Break Inside Containment, Per Section 4.8 of NUREG-0826, Integrated Plant Safety Assessment,Haddam Neck Plant
- B11382, Application for Amend to License DPR-61,revising Tech Specs Re Refueling Cavity Water Level Per Safety Analysis of Cavity Water Level & Seal Redesign.Fee Paid
- B11409, Responds to IE Bulletin 80-06, ESF Reset Control. Trip Signal to Containment Air Activity Pump & Containment Sump Pump Provided.Removal of Safety Injection Actuation Signals from RHR Valves Being Evaluated
- B11502, Radiological Environ Monitoring Program,Annual Environ Operating Rept for 1984
- B11525, Suppls 850128 Response to Insp Rept 50-213/84-28 & 841213 Order Modifying License Re Failure of Reactor Cavity Seal Ring.Possible Misinterpretation of 850128 Response Re Design Changes Deemed Significant Clarified
- B11536, Informs That Combustible Gas Detectors in Chemistry Lab Not Tested or Calibr Per Manufacturer Spec.Detector Sys Turned Over to Plant Operations & Maint Depts.Detectors Will Be Tested & Calibr Prior to Return to Svc
- B11564, Application for Amend to License DPR-61,revising Tech Spec 3.4 Re Combined Heatup,Cooldown & Pressure Limitations to Update Pressure/Temp Limit Curves for Hydrostatic & Leak Testing & for Heatup & Cooldown Rates.Fee Paid
- B11567, Forwards NPDES Monthly Discharge Monitoring Rept for Sept 1997.Addl Samples Taken at NPDES Locations & Analyzed W/ Approved Methods Included in Table 2 & 3
- B11581, Informs That Schedule for Human Factors Review for Fire Protection Will Be Included in Control Room Design Review Program.Review Performed Per Suppl 1 to NUREG-0737.Safe Shutdown Procedures Will Be Implemented Following Mods
- B11583, Provides Info Re Activities Currently Planned for 1986 Refueling Outage,Assuring Continued Operability of Steam Generators.Application to Amend License DPR-61 Will Be Submitted by 851001 to Support Sleeving During Outage
- B11585, Submits Revised Commitment on SEP Topic III-10.A,per Section 4.13 of Integrated Plant Safety Assessment Rept (NUREG-0826),concerning Mods to Butterfly Type Motor Operated Valves Utilized in Svc Water Sys
- B11587, Forwards Rev 3 to Safety-Related Piping Seismic Qualification Program, Per SEP Topic III.6.Changes to Damping Values,Peak Shifting & Independent Support Motion Described
- B11591, Responds to NRC 850618 Request for Addl Info Re 850611 Proposed Rev to Section 3.4 of Tech Specs Re Pressure/Temp Limits.Revised Figures 3.4-1,3.4-8 & 3.4-9 Encl.Amend to License DPR-61 Still Required by 850720
- B11594, Revised Application for Amend to License DPR-61,correcting Typos,Adding Figure & Revising Definitions Section of Tech Specs Submitted w/850529 Application
- B11599, Forwards USGS Info Re SEP Topic II-3.B, Flooding Potential & Protection Requirements, Per 850530 Request.Info Consists of Connecticut River Rating Table at Bodkin Rock & Indicates That Stage Elevation Affected by Tidal Effects Up to 8.0 Ft
- B11603, Clarifies Misinterpretations of Re Insp Rept 50-213/85-07.Ltr Discussed Measures Planned to Approve Coordination & Technical Review of Submittals to Nrc.No Specific Procedures to Fulfill Objective Implemented
- B11625, Advises That Util Plans to Implement Encl Curves, Representing Planned Means for Compliance w/10CFR50,App G Between 14.0 & 22.0 EFPY When Current Curves for Heatup & Cooldown Become Valid at 14.0 EFPY
- B11629, Advises That Util Unable to Meet Jul 1985 Schedule for Submittal of Amend to License DPR-61 Re post-accident Sampling Sys Containment Isolation Valves.Amend Request Will Be Submitted During Third Quarter 1985
- B11636, Clarifies Status of Encl Proposed Tech Spec Changes,Per 850709 Response to Generic Ltr 83-43 Re Reporting Requirements of 10CFR50.72 & 73.Submittal Supersedes May 1983 Proposed Tech Spec Section 6.9 Changes
- B11643, Forwards Info Re Control Room Halon Fire Suppression Sys,In Response to 850715 Request.Total Flooding of Halon Sys Will Be Installed in Facility Control Room During Next Refueling Outage,Per 10CFR50.48 Schedule
- B11646, Forwards Draft Connecticut Yankee Plant Design Change Task Group, Final Rept, Review of Design Change Process, Plant Design Change Evaluations & Screening of Plant Design Changes, Per NRC Request During 850801-02 Audit
- B11652, Discusses Status of Resolution of Unresolved Item 50-213/85-08-04.Inservice Date of 871201 Planned
- B11655, Advises That Proposed Change to Axial Offsite Limits Will Be Requested for Cycle 14 to Allow 3-loop Operation at All Times During Cycle.Vendor Evaluation Indicated 4-loop Axial Offset Limits Not Always Conservative
- B11656, Forwards Clarification of Proposed Rev to Tech Spec 3.13.C(1) Re Refueling Submitted w/850510 Ltr.Revised Page Clarifies That Fuel Returns to Reactor Core,Not Literally to Bottom of Reactor Pressure Vessel
- B11657, Forwards Tech Spec Page 3-4a Inadvertently Omitted from Attachment 1 of 850709 Submittal Re Proposed Changes to Tech Specs in Response to Generic Ltr 83-43 Covering Reactor Coolant Loops
- B11659, Discusses Implementation of Mods Providing Equivalent Level of Protection Required by 10CFR50,App R.Non-outage Mods Implemented.Mods in Control Room Will Be Implemented During Next Refueling Outage for Safety Reasons
- B11660, Provides Informational Update of Analysis of Plant Auxiliary Feedwater Sys.Increased Primary Sys Pressure Predicted for Loss of Main Feedwater Event Has No Unacceptable Safety Impact
- B11702, Forwards Addl Info Supporting Proposed Rev to Tech Spec 6.5.2.8.i, Fire Protection & Loss Prevention Audits. Audits/Insps Will Continue to Be Performed by ANI & Credited Toward Satisfying Tech Spec 6.5.2.8.i
- B11730, Documents Basis for Continued Position That Auxiliary Feedwater Sys Meets Tech Spec & Design Basis Requirements. Areas Addressed Include Design Basis Analysis,Four & three- Loop Operation & Reanalysis Philosophy
- B11737, Concurs W/Nrc That Generic Ltr 85-12 Should Not Apply to Westinghouse Reactors Which Do Not Utilize Westinghouse Owners Group Small Break LOCA Analysis Methodology.No Further Response Forthcoming
- B11743, Provides Pvrc Damping Curve Info to Clarify Proposed Changes to Criteria Document for safety-related Piping Analyses Under SEP Topic III-6, Seismic Design Considerations
- B11768, Informs That Application for Amend to Tech Specs Re post-accident Sampling Sys Will Not Be Submitted Until 851030 Due to Delays in Review Process
- B11796, Forwards Response to Generic Ltr 85-09 Requesting Proposed Tech Specs Needed to Meet Requirements of Generic Ltr 83-28, Item 4.3 Re Reactor Trip Sys Reliability.No Changes to Tech Specs Required
- B11829, Proposed Tech Spec Change,Allowing Testing of Normally Closed Isolation Valves in post-accident Sampling Sys During Operation Modes 1-4
- B11834, Forwards Response to Request for Suppl to Justification for Continued Operation Re 20 RCS Loop Resistance Temp Detectors & 14 Valve Motor Operators Not Fully Environmentally Qualified
- B11855, Discusses Probabilistic Safety Study (Isap Process) Finding Re Postulated Loss of Offsite Power & Failure of Motor Control Ctr.In Case of Loss of Diesel Generator Room Ventilation,Measure Available to Mitigate Adverse Effects
- B11875, Submits Addl Info Re 850502 Application to Revise Tech Spec Section 4.10,Item D Re Reactor Vessel Surveillance Capsule Removal Frequency,Per Request.Analysis of Capsules Removed Show That Embrittlement Comparable to Industrial Trends
- B11885, Discusses Cycle 13 Coastdown,Specifically,Turbine Overspeed Protection Sys Surveillance.Addl Stroke Testing of Turbine Stop & Control Valves in Coastdown Operation Presently Unwarranted.Sep Topic III-4.B Discussed
- B11903, Application for Amend to License DPR-61,revising Tech Spec 4.10.1 Re Inservice Insp of Steam Generator Tubes to Allow Sleeving as Means to Repair Steam Generator Tubes.Fee Paid
- B11904, Forwards Descriptions of Procedures for Insps of Water Control Structures & Methods of Addressing NRC Concerns Re SEP Topic III-3.C, Inservice Insp of Water Control Structures & Isap Topic 1.29, Flooding Evaluation
- B11908, Submits Revised Justification for Continued Operation for Motor-Operated Valve 200 to Reflect Location of Alternative Instrumentation
- B11911, Proposed Tech Specs for Cycle 14 Reload
- B11913, Forwards Listed Encls,Including Current Emergency Operating Procedures,In Response to 851017 Request Re Use of Feed & Bleed in Environ Qualification of Equipment Outside Containment
- B11917, Requests Schedular Exemption for App R Mods Identified in ,Requiring Schedular Relief from 1986 Refueling Outage Implementation Date.Summary of Mods,Basis for Schedule & Interim Fire Protection Provided
- B11919, Informs That Four Zircaloy-clad Lead Test Assemblies Will Be Placed in Nonlimiting Core Locations & steady-state Peak LHGR Will Not Exceed 11 Kw/Ft for Cycle 14.Exemption from 10CFR50.46 & App K Should Remain Valid
- B11920, Responds to Unresolved Items Noted in Insp Rept 50-213/84-13.Corrective Actions:Impact of Readout Accuracy of Results of Local Leak Rate Tests Being Reviewed
- B11921, Forwards Proprietary Rev 1 to WCAP-11008 & Nonproprietary Rev 1 to WCAP-11009, Connecticnt Yankee Steam Generator Sleeving..., Per 851206 Application to Amend License DPR-61.W/o WCAP-11009.WCAP-11008 Withheld (Ref 10CFR2.790)
- B11937, Discusses Reactor Cavity Pool Seal Status.Plant Procedures Used to Respond to Decreasing Reactor Cavity Water Level Remain Valid.New Permanent Seal Design Reviewed Against IE Bulletin 84-03 & All Appropriate Plant Procedures
- B11943, Forwards Results of LOCA Calculations & Proprietary Engineering Hot Channel... & Core Bypass Flow Summary Rept, in Support of 851211 Rev to Tech Specs,For Approval by 860301.Repts Withheld (Ref 10CFR2.790)
- B11947, Forwards Addl Info on 851206 Proposed Rev to Steam Generator Tech Spec,In Response to 851220 Verbal Request.Plugging Limit for Sleeved Steam Generator Tubes Will Be Determined Prior to 1987 Refueling Outage for Cycle 15
- B11949, Advises That Fire Door 1 Between Control Room & Turbine Bldg Will Be Replaced.Request for Exemption from 10CFR50, App R,Dtd 850916,still Needed.Proposed Mods Re Loop Isolation Valves Can Be Deleted.W/One Oversize Drawing
- B11962, Forwards Proprietary WCAP-11042 & Nonproprietary WCAP-11046, Haddam Neck Plant Core Bypass Flow Summary Rept. Westinghouse Ltr Requesting Withholding Also Encl. Proprietary Rept Withheld (Ref 10CFR2.790)
- B11968, Forwards Description of Temporary Change to Modified Amended Security Plan.Temporary Change Will Support Const Efforts During Current Refueling Outage & Will Not Exceed 4 Months. Description Withheld
- B11982, Forwards Nonproprietary & Proprietary Engineering Hot Channel Factor Calculational Methodology,For Cycle 14 Reload License Amend.Affidavit & Addl Info on Core Bypass Flow Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790)
- B11986, Forwards Proposed List of Isap Topics Warranting Probabilistic risk-oriented Evaluations to Be Completed During 860410-0530.Milestones Composing Isap Implementation Schedule Listed
- B11987, Proposed Tech Specs,Allowing Installation of Directional Spray Water Suppression Sys in Cable Spreading Area Hallway & Water curtain-type Automatic Directional Spray Sys Around Four Svc Water Pumps to Protect Safe Shutdown Equipment
- B11994, Requests Exemption from Requirements of App J to 10CFR50. Util Has Initiated Detailed Evaluation of Scope & Schedule for Mods Required to Achieve Compliance W/App J as Part of Facility Isap
- B11999, Forwards BAW-1878, Haddam Neck Plant Technical Rept Supporting Cycle 14 Operation. Cycle 14 Tech Spec Operating Limits Submitted W/Reload License Amend Request Still Valid & Supported by Revised Fuel Burnups
- B12003, Requests Extension to 860326 to Provide Info Requested in Re Response to Generic Ltr 84-04 & SEP Topic III-06
- B12009, Forwards Addl Info Re 851206 Proposed Tech Spec Change Allowing Sleeving of Steam Generator Tubes as Repair Option, in Response to 860221 Request.Special Local Ventilation in Steam Generator Repair Area Provided
- B12012, Semiannual Radioactive Effluent & Waste Disposal Rept, Jul-Dec 1985
- B12014, Application to Amend License DPR-61,revising Tech Specs to Delete Requirement That Operating Crew Senior Reactor Operators Be Qualified in Radiation Protection Procedures. W/O Tech Specs.Fee Paid
- B12016, Provides Addl Info Re Mortar Cracks Identified During 851029 Site Walkdown,Per Response to Request for Info on IE Bulletin 80-11 Concerning Masonry Wall Design.Mortar Joint Cracks Will Be Chipped Out
- B12020, Summary of Results of Haddam Neck Probabilistic Safety Study
- B12022, Forwards Results of Equipment Qualification Reverification Walkdown Program,Per IE Info Notices 86-002 & 86-003. Discrepancies Will Be Corrected Prior to Startup from Current Outage
- B12044, Discusses Small Range of Break Sizes in One Loop of RCS for Which Safety Injection Flow in High Pressure Recirculation Mode Insufficient to Provide Adequate Core Cooling W/O Mod to Procedures or Valve Realignments,Per LOCA Analysis
- B12046, Forwards BAW-1912, Haddam Neck Plant Technical Rept Supporting Cycle 14 Operation. Administrative Tech Spec for Current Surveillance on Quadrant Power Tilt Ratio Implemented.W/O Encl
- B12049, Submits Addl Info Supporting 860307 Fire Protection Schedular Exemption Request W/Respect to Criteria Specified in SECY-85-306,per 860401 Meeting.Info Addresses Status of Engineering Analysis & Design Work Re Switchgear Room
- B12050, Application for Amend to License DPR-61,adding Item (I) to Tech Spec Section 4.10.1,D-1 Providing Addl Acceptance Criteria for Tube Insps.Fee Paid.W/O Fee
- B12051, Advises That Future Refs to Equipment Qualification Temp Should Be 280 F,As Result of Reevaluation of Containment Pressure/Temp Profiles,Per IE Info Notice 84-90
- B12055, Radiological Environ Monitoring Program Annual Environ Operating Rept,Part B,1985
- B12061, Application for Amend to License DPR-61,revising Tech Specs to Add New Section 3.24, RCS Leakage Detection Sys, to Fulfill NUREG-0826 Commitment.Fee Paid
- B12062, Advises That Mod to Install Charging Pump Low Suction Pressure Trip Switch on Safety Sys Lockout Panel in Control Room Will Be Deleted.Charging Metering Pump for Pressurizer Level Control Pump Seal Injection Will Be Used
- B12067, Proposed Tech Specs Allowing Implementation of Measures Approved by NRC as One Element of Response to Previously Addressed Small Break LOCA Issue
- B12071, Requests Temporary Exemption from Single Failure Requirements Applicable to Small Break LOCAs Per 10CFR50.12. Exemption Would Apply Only to Proposed Interim Response Mechanism
- B12074, Formalizes Agreements Reached at 860423 Meeting W/Nrc Re Emergency Operating Procedure EOP 3.1.4, Loss of Coolant, Motor Operator Valves MOV-24 & MOV-874 & Operator Training on Revs to EOP 3.1.4