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The following 200 pages are in this category, out of 26,795 total.
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- 05000155/LER-1978-032, Forwards LER 78-032/03L-0.W/o Encl
- 05000155/LER-1982-018, Forwards LER 82-018/01T-0
- 05000155/LER-1982-019, Forwards LER 82-019/03L-0
- 05000155/LER-1982-020, Forwards LER 82-020/03L-0
- 05000155/LER-1982-021, Forwards LER 82-021/03L-0
- 05000155/LER-1982-022, Forwards LER 82-022/03L-0
- 05000155/LER-1987-009, Responds to NRC Re Violations Noted in Insp Rept 50-155/87-19.Events Cited in 870803 Encl LER 87-009.Issuance of Violation Contradicts NRC Policy to Encourage & Support Licensee Initiative to Identify & Correct Problems
- 05000155/LER-1989-006, Updates 900405 Submittal of LER 89-006,Rev 1 Re Defects in Fire Penetration Seals
- 05000155/LER-1990-002, Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage
- 05000155/LER-1992-002, Advises That Commitment Due Dates for LER 92-002 Re as-found Setpoint Failure of Liquid Poison Relief Valve RV-5049 & LER 92-009 Re Reactor Scram During Plant Startup for Cycle 26 Overdue.Operator Training Delayed Until 930301
- 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable
- 05000155/LER-1992-010, Informs That Initial Pressure Regulator Bellows W/One Operating Cycle (About 12 Months) of Satisfactory Performance Will Be Installed in Lieu of New Bellows,In Response to LER 92-010
- 05000155/LER-1998-001, Forwards LER 98-001-00 Re Discovery During Facility Decommissioning of Severed Liquid Poison Tank Discharge Pipe.Rept Being Submitted IAW 10CFR50.72(b)(2)(iii) & 10CFR50.73(a)(2)(i)(B)
- 05000213/LER-1982-004, Forwards LER 82-004/01T-0
- 05000213/LER-1982-005, Forwards LER 82-005/03L-0
- 05000213/LER-1985-017, Application for Amend to License DPR-61,changing Tech Specs Re Primary Sys Leakage,As Part of Corrective Actions for 850814 LER 85-017 Concerning post-LOCA Release Paths Outside Containment.Fee Paid
- 05000213/LER-1985-024, Corrected LER 85-024-00:on 850910,auxiliary Feedwater auto-initiation Solenoid Operated Valve,Asco Model NP-8320a-185E Failed to Change State Upon Deenergization. Cause Not Determined.Valve Cycled After External Tapping
- 05000213/LER-1989-020, Forwards LER 89-020-01 Which Updates Info Re Fuel Failures Discovered During 1989 Refueling Outage & Identified as Potential Issue in Recent Nrc'S Historical Review Rept. Conclusion from Original LER Remains Unchanged
- 05000213/LER-1996-016, Forwards LER 96-016-01 & LER 96-027-01,retracting Originally Proposed Corrective Actions That Will No Longer Be Implemented as Result of CYAPCO Decision to Cease Operations at Haddam Neck Plant
- 05000213/LER-1996-030, Forwards Suppl LERs 94-015-02,96-019-01,95-001-02,96-021-01, 96-005-01,96-030-01,96-013-01 & 97-003-01 to Retract Originally Proposed CAs That Are No Longer Implemented. Proprietary Page 15 of 15 to LER 96-030-01,encl
- 05000295/LER-1978-078, Forwards LER 78-078/01L-0
- 05000295/LER-1978-082, Forwards LER 78-082/03L-0
- 05000295/LER-1978-084, Forwards LER 78-084/03L-0
- 05000295/LER-1978-085, Forwards LER 78-085/03L-0
- 05000295/LER-1978-086, Forwards LER 78-086/03L-0
- 05000295/LER-1978-087, Forwards LER 78-087/01T-0
- 05000295/LER-1978-088, Forwards LER 78-088/03L-0
- 05000295/LER-1978-089, Forwards LER 78-089/01T-0
- 05000295/LER-1981-002, Forwards Updated LER 81-002/03X-1
- 05000295/LER-1982-020, Forwards LER 82-020/03L-0
- 05000295/LER-1982-021, Forwards LER 82-021/03L-0
- 05000295/LER-1982-022, Forwards LER 82-022/03L-0
- 05000295/LER-1982-023, Forwards LER 82-023/03L-0
- 05000295/LER-1985-035, Special Rept Re Failure to Notify NRC of Quarterly Release of Radioactive Matl in Excess of 2.5 Ci Per Unit on 840513. Failure to Submit Rept Documented in LER 85-035-00 & Insp Repts
- 05000295/LER-1989-008, Forwards LER 89-008-00 Re Room Cooler Svc Water Supply Discrepancy Discovered on 890609
- 05000295/LER-1994-005, Forwards LER 94-005-01 Per 10CFR50.73(a)(2)(iv),which Requires 30 Day Written Rept When Any Event or Condition Resulted in Manual or Automatic Actuation of Any ESF, Including Rps.Commitments,Encl
- 05000295/LER-1996-007, Forwards LER 96-007-01 Which Is Being Submitted to Update Safety Analysis & CA Taken Re Event That Occurred at Zion Nuclear Power Station,Unit 1.Commitments Made within Ltr, Encl
- 05000295/LER-1997-001, Forwards LER 97-001-01,which Clarifies Info on Root Cause,Safety Analysis & Event Description.Corrective Actions Updated to Show Status of Items
- 05000295/LER-1997-002, Forwards LER 97-002-00.Commitments Made by Util Listed
- 05000295/LER-1997-004, Forwards LER 97-004-01,which Clarifies Info on Event Description,Root Cause & Safety Analysis.Cas Have Been Updated.No Commitments Have Been Made
- 05000295/LER-1997-005, Forwards LER 97-005-01,which Requires Thirty Day Written Rept Following Any Operation Prohibited by Plants Tss. Attachment a Provides Commitments Associated with Correspondence
- 05000295/LER-1997-006, Forwards LER 97-006-00 Reporting an Event or Condition That Is Prohibited by Tss.Commitments Made in Rept,Listed
- 05000295/LER-1997-007, Forwards LER 97-007-00 Re Automatic Actuation of Esf. Submitted Table Identifies Actions Committed to by Util
- 05000295/LER-1997-008, Forwards LER 97-008-00 Which Repts Condition That Resulted in Condition of Npp.Listed Commitments Included in Rept
- 05000295/LER-1997-009, Forwards LER 97-009-00 IAW 10CFR50.73(A)(2)(i)(B) Which Requires Listed Corrective Actions
- 05000295/LER-1997-010, Forwards LER 97-010-00 IAW 10CFR50.73(a)(2)(i)(B).Corrective Actions Listed
- 05000295/LER-1997-011, Forwards LER 97-011-02,re Two Supplements Mistakenly Sent to Nrc.Questions or Comments Should Be Addressed to R Godley.Commitments Listed
- 05000295/LER-1997-012, Forwards LER 97-012-00,which Documents 970423 Event That Occurred at Zion Generating Station.Commitments Made by Util,Listed
- 05000295/LER-1997-015, Forwards LER 97-015-01,per 10CFR50.73(a)(2)(iv),which Requires Written Rept When Any Event Occurs That Resulted in Manual or Automatic Actuation of Any Esg.No Commitments Were Made within Rept
- 05000295/LER-1997-016, Forwards LER 97-016-00 Re Failure to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Event Investigation Is Ongoing & Corrective Actions Will Be Provided in Supplemental LER
- 05000295/LER-1997-017, Forwards LER 97-017-01,which Clarifies Info on Event Description,Root Causes & Analysis.Cas Have Been Updated. Attachment a Provides Commitments Associated W/ Correspondence
- 05000295/LER-1997-018, Forwards LER 97-018-01,which Clarifies Info on Event Description,Root Causes & Safety Analysis.Corrective Actions Have Also Been Updated.Commitments Made within Ltr,Encl
- 05000295/LER-1997-019, Forwards LER 97-019-00 Re Failure to Test Safety Related Logic Circuits Required by Tech Specs.Attachment a Provides Commitments Associated W/Correspondence
- 05000295/LER-1997-020, Forwards LER 97-020-00 Per 10CFR50.73(a)(2)(ii) & 10CFR50.72(b)(2)(i).Util Is Unclear Whether Plant Is within or Outside Design Basis,Therefore Event Assumed Reportable. Commitments Made by Util,Encl
- 05000295/LER-1997-021, Forwards LER 97-021-00 Which Requires 30 Day Written Rept When Any Operation or Condition Is Prohibited by Ts,Per 10CFR50.73(a)(2)(ii)
- 05000295/LER-1997-022, Forwards LER 97-022-00 Which Documents Event That Occurred at Zion Nuclear Power Station,Unit 1.Commitments Made within Ltr,Encl
- 05000295/LER-1997-023, Forwards LER 97-023-00,per 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util,Encl
- 05000295/LER-1997-024, Forwards LER 97-024-00,per 10CFR50.73(a)(2)(i)(B). Commitments Made by Util,Encl
- 05000295/LER-1997-025, Forwards LER 97-025-00,re Event Which Occurred at Zion Nuclear Power Station.Commitments Made within Ltr Aslo Encl
- 05000295/LER-1997-026, Forwards LER 97-026-00,per 10CFR50.73(a)(2)(i)(B) Which Requires 30-day Written Rept.Commitments Associated W/Correspondence,Encl
- 05000304/LER-1978-057, Forwards LER 78-057/03L-0
- 05000304/LER-1978-060, Forwards LER 78-060/03L-0
- 05000304/LER-1978-061, Forwards LER 78-061/03L-0
- 05000304/LER-1978-062, Forwards LER 78-062/03L-0
- 05000304/LER-1979-033, Forwards LER 79-033/03L-0
- 05000304/LER-1982-013, Forwards LER 82-013/03L-0
- 05000304/LER-1982-014, Forwards LER 82-014/03L-0
- 05000304/LER-1982-015, Forwards LER 82-015/03L-0
- 05000304/LER-1982-016, Forwards LER 82-016/03L-0
- 05000304/LER-1982-017, Forwards LER 82-017/03L-0
- 05000304/LER-1984-006, Corrected LER 84-006-00:on 830602,during Normal Operation, Wide Range RCS Pressure Channels 403 & 405 Difference Exceeded Allowed Tolerance.Channel 405 Inoperable for 26 Days in Violation of Tech Specs
- 05000304/LER-1985-012, Submits Revised LER Cover Ltr as Update to Cover Ltr Transmitting LER 85-012-01.Original Cover Ltr Inadvertently Ref Unit 1.LER Correct as Originally Transmitted
- 05000304/LER-1985-026, Corrected LER 85-026-00:on 851108,discovered That Spring Loaded Check Valves Installed Backwards on Drain Lines for Reactor Containment Fan Cooler Motor HX Housings.Effect on Drainage Being Studied
- 05000304/LER-1986-005, Forwards Errata to LER 86-005-00,correcting Rept Number to LER 86-010-00
- 05000304/LER-1988-009, Corrects Typo in Transmittal Ltr for LER 88-009-00.Correct Docket Is 50-304 Not 50-204
- 05000304/LER-1996-004, Forwards LER 96-004-01 Re Results of Investigation Into Failure of Unit Containment Inner Air Lock Door.Addl Corrective Action Listed in Attachment a
- 05000304/LER-1997-001, Forwards LER 97-001-00 Per 10CFR50.73(a)(2)(iv) Which Requires Written Rept Using NRC Form 366, License Event Rept, within 90 Days of Discovery of Event.Attachment a Contains Commitments Associated W/Ltr
- 05000304/LER-1997-002, Forwards LER 97-002-00,per 10CFR50.73(a)(2)(v)(B),which Requires 30 Day Written Rept.Commitments Associated W/Correspondence,Encl
- 05000304/LER-1997-003, Forwards LER 97-003-00 Re Unit 2 RHR Sys Declared Inoperable,Per 10CFR50.73(a)(2)(v)(B)
- 05000304/LER-1997-004, Forwards LER 97-004-00,per 10CFR50.73(a)(2)(i).Commitments Associated W/Correspondence,Encl
- 05000304/LER-1997-005, Forwards LER 97-005-00 Which Documents Event That Occurred at Zion Nuclear Power Station,Unit 2.Commitment Made within Ltr,Encl
- 05000304/LER-1997-006, Forwards LER 97-006-00 Per 10CFR50.73(a)92)(ii)(B) Which Requires 30 Day Written Rept When Any Event or Condition Occurs That Resulted in Condition of Nuclear Power Plant. Regulatory Commitments Encl
- 05000304/LER-1997-007, Forwards LER 97-007-00 Per 10CFR50.73(a)(2)(v)(B) Which Requires Written Rept for Any Event or Condition That Could Prevent Fulfillment of Safety Function of Structures or Sys Needed to Remove Residual Heat.W/Commitments Attach
- 05000304/LER-1997-008, Forwards LER 97-008-00 Per 10CFR50.73(a)(2)(i)(B),which Requires 30 Day Written Rept.Attachment a Provides Commitments Associated W/Correspondence
- 05000304/LER-1997-009, Forwards LER 97-009-00,re Event Which Occurred at Zion Nuclear Power Station,Unit 2.Commitments Made within Ltr Also Encl
- 05000304/LER-1998-001, Forwards LER 98-001-00,per 10CFR50.73(a)(2)(iv) Which Requires 30 Written Rept Following Event That Resulted in Manual or Automatic Actuation of Any Esf,Including Rps. Commitments Also Encl
- 05000304/LER-1998-002, Forwards LER 98-002-00 IAW 10CFR50.73(a)(2)(i)(B). Commitments Made within Ltr,Encl
- 05000322/LER-1985-059
- 05000322/LER-1986-011, Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing
- 05000322/LER-1986-014
- 05000322/LER-1986-032
- 05000322/LER-1986-039
- 05000322/LER-1986-046, Advises That Preventive Maint Scheduled Activity Work Sheet Will Be Initiated to Inspect Flap Check Valves & Reducing Rubber Sleeve in Approx 24 Months.Commitment Resolves Questions & Concerns Re LER 86-046
- 05000322/LER-1987-009
- 05000322/LER-1987-012
- 05000322/LER-1987-014, Forwards LER 87-014 & Rev 1 to LER 86-029
- 05000322/LER-1987-022
- 05000322/LER-1987-035
- 05000322/LER-1988-003
- 05000322/LER-1988-015
- 05000322/LER-1988-017
- 05000322/LER-1989-003
- 05000322/LER-1989-005
- 05000322/LER-1990-009, Forwards LER 90-009-00 & LER 90-010-00 Re Unplanned Actuation of ESF Sys
- 05000344/LER-1979-013, Forwards Confirmatory Info to NRC 791229 Question 1 Re LER 79-13 Concerning Stresses in Walls Due to Thermal Gradients. Masonry Walls Subj to Thermal Gradient Across Thickness Will Undergo Deformation.Certificate of Svc Encl
- 05000344/LER-1982-007, Updated LER 82-007/01T-0:on 820514,during Review of Revised Containment DBA Analysis,Nonconservative Spray Modeling Error Identified in Model Used to Justify Tech Spec 3.6.1.4 Re Max Positive Containment Operating Pressure
- 05000344/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl
- 05000344/LER-1982-009, Forwards LER 82-009/03L-0.Detailed Event Analysis Encl
- 05000344/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Encl. Corrected Copy
- 05000344/LER-1982-011, Forwards LER 82-011/03T-0.Detailed Event Analysis Encl
- 05000344/LER-1985-013, Forwards Comments on 860627 Draft Info Notice Re Steam Generator Hydraulic Snubber Failures,Based Primarily on LER 85-13 & Suppl 1 to LER
- 05000344/LER-1986-003, Forwards Clarification of Util Position Re 10CFR50.49 Compliance for 11 ECCS Valves Discussed in Rev 1 to LER 86-003,per 860905 Enforcement Conference & Concerns Raised in Insp Rept 50-344/86-32
- 05000344/LER-1987-014, Advises That Results of Exam to Determine Exact Cause of Corrosion on Internal Surfaces of Both Centrifugal Charging Pumps Discussed in LER 87-014 Will Be Reported in Rev to LER 87-014 by 871101
- 05000344/LER-1988-019, Discusses Issues Discussed in Rev 2 to LER 88-019 Re Containment Hydrogen Vent Sys Absorber Replacement
- 05000344/LER-1988-025, Forwards LER 88-25 Re Event Where Archaeological Significant Area Inadvertently Disturbed by Const Excavation Activities & Portland State Univ Rept, Archaeological Evaluation of Trojan Locality 35C01
- 05000344/LER-1988-046, Informs That Supplemental Rept to LER 88-46 Will Not Be Ready for Submittal Until 890315
- 05000344/LER-1988-049, Responds to NRC Re Violations Noted in Insp Rept 50-344/89-01.Corrective Actions:Temporary Change to Plant Operation Test Procedure 26-2 Implemented Which Appropriately Revised Procedure as Described in LER 88-049
- 05000344/LER-1989-007, Informs That Rev 1 to LER 89-07 Will Be Submitted by 891013, Due to Forced Outage & Difficulties
- 05000344/LER-1989-012, Advises That Rev 1 to LER 89-012 Will Be Submitted by 890920 Due to Extension of 1989 Refueling Outage & Plant Trip of 890809
- 05000344/LER-1990-015, Forwards Rev 1 to LER 90-015-01 on 901015 Presenting Results of Preliminary Calculations
- 05000344/LER-1992-010, Suppls 900706 Response to GL 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Failure Position of All safety-related Active Valves Tested for in IST Program.Design Defect Reported in LER 92-10
- 05000344/LER-1992-026, Forwards LER 92-26,rev 4 & Discusses Addl Degraded Three Hour Fire Barriers & Barrier Penetrations Discovered During 1992 Eighteen Month Fire Barrier Peneratration Surveillance
- 05000409/LER-1979-019, Forwards LER 79-019/01T-0
- 05000409/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Submitted
- 05000409/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Submitted
- 05000409/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Submitted
- 05000409/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Submitted
- 05000409/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Submitted
- 05000409/LER-1982-015, Forwards LER 82-015/01T-0.Detailed Event Analysis Submitted
- 05000409/LER-1982-016, Forwards LER 82-016/03L-0.Detailed Event Analysis Encl
- 05000409/LER-1982-020, Updated LER 82-020/03X-1:on 821119-20,on Three Occasions Vacuum Pump Which Maintains Isokinetic Flow Rate to Stack Activity Monitors Tripped.Caused by Pump & Motor Overheating.Motor Thermal Overload Fuses Upgraded
- 05000409/LER-1983-001, Forwards LER 83-001/03L-0 & Updated LER 82-020/03X-1. Detailed Event Analysis Encl
A
- A01395, Advises That Inservice Date for Containment Level Detection Sys Is Postponed Until 830101,in Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment.
- A01701, Forwards Natural Circulation Test at CT Yankee Nuclear Power Plant, Demonstrating Ability of Facility to Undergo Sustained Natural Circulation Cooldown W/O Formation of Steam Bubble in Reactor Vessel Upper Head Region
- A02398, Clarifies Training & Experience of Shift Technical Advisors, Per NRC Re Util 801231 & 820219 Responses to NUREG-0737,Item I.A.1.1.One Advisor Does Not Hold Current Senior Reactor Operator License.Nureg Requirements Met
- A02425, Responds to NRC Re Violations Noted in IE Insp Rept 50-213/82-07.Corrective Actions:Monthly Check of Power Operated Relief Valve & Safety Valve Position Indication Being Performed.Test Procedure Sur 5.1-15 Will Be Revised
- A02437, Informs That NRC 820414 Draft Evaluation of SEP Topic VI-7.B Re ESF Switchover from Injection to Recirculation Mode Should Be Revised Based on Licensee .Submitted Comments Should Be Incorporated Into Evaluation
- A02441, Submits CT Yankee Atomic Power Co Comments on Draft SEP Operating Experience Rept,Sections 4.2 & 4.5.1.1
- A02452, Forwards Responses to 820414 Request for Info Re Secondary Water Chemistry Control Program.Data Reviewed by Corporate Chemistry Group for long-term Trend Analysis
- A02469, Responds to NRC Re Violations Noted in IE Insp Rept 50-213/82-14.Corrective actions:call-up Method of Staffing Technical Support Ctr Will Be Formalized by 820715 & Emergency Planning Coordinator Appointed
- A03104, Responds to NRC Re Violations Noted in IE Insp Rept 50-213/83-06.Corrective Actions:Cure Time for Drums of Solidified Waste Increased to 7 Days & Independent Check for Residual Water Performed
- A04500, Provides Addl Info to Amend Proposed Tech Specs on Flammable Liquid Control for Control Room,Per 850724 Telcon.Definition of Suitable Containers Consistent w/820716 Submittal & Section 2.2 of SER Issued W/Exemptions from 10CFR50,App R
- A04547, Informs of Status of Commitments in Response to Facility Proposed Design Change Task Group Final Rept,Per . All Commitments Fulfilled.Original Intent of Improvement Plans Unaltered
- A04582, Clarifies Commitment in 850225 Response to Insp Rept 50-213/84-26.All Components Listed in Mepl Will Have Production Maint Mgt Sys QA Indicators Verified as Properly Reflecting QA Status
- A04872, Informs That NRC Misinterpreted 841004 Proposed Resolution of NUREG-0737,Item II.K.3.25 Re Loss of Ac Power on Reactor Coolant Pump Seals.Util Commitment Was to Evaluate Change in Integrated Safety Assessment Program
- A04905, Responds to NRC Re Violations Noted in Insp Rept 50-213/85-03.Corrective Actions:Calibr Procedures Revised, Procedure IC-P-2 Implemented & Plot Developed,Indicating Loop Delta P
- A04919, Responds to NRC Re Violations Noted in Insp Rept 50-213/85-08.Corrective Actions:Review Conducted to Ensure Environ Review Board Audits Subsequent to 1983 Complete
- A04948, Forwards Clarifications of Rev 11 to Modified Amended Security Plan,Per 850612 & 19 Commitments.Clarifications Withheld (Ref 10CFR73.21 & 2.790)
- A05012, Responds to NRC Re Violations Noted in Insp Rept 50-213/85-09.Corrective Actions:Procedure ACP 1.2-7.1 Re Receipt,Insp & Identification of Matls,Parts & Components Revised to Clarify QA Responsibilities of Personnel
- A05034, Forwards Addl Info Re Manual Trip of Reactor Coolant Pumps, Per NRC Request.Westinghouse Owners Group Methodology Being Used on Interim Basis Until Revised Small Break LOCA Analysis Approved by NRC
- A05041, Forwards Review of Isap Topic 1.21, Reg Guide 1.97 Instrumentation, Per 850517 Commitment.Nrc 850703 Concerns Re Status of Compliance W/Rev 2 to Reg Guide 1.97 Also Addressed
- A05050, Submits Licensed Operator Requalification Program Status Rept.Summary of 850628 Requalification Training Meeting Rept 50-213/85-01 Was Provided to Document Commitments Listed
- A05084, Submits Final Response to IE Bulletin 80-11 Re Masonry Wall Design.Cracks Monitored Over 1-month Span.Review of as-built Wall Before Mods Indicates No Cracks.Mortar Joint Cracks Resulted from Const Process of Installing Mods
- A05085, Notifies of Change in 850816 Commitment to Provide Improved Plant Operations Review Committee Review of Plant Design Change Records in Response to Insp 50-213/85-15.Commitment Now Considered W/O Merit & Therefore Eliminated
- A05382, Forwards Page 3-3 of Approved Modified Amended Security Plan (Masp).Rev 11 Change to Section 3.3.1.1 of Msap Withdrawn. Page Withheld (Ref 10CFR73.21)
- A05384, Responds to NRC Re Violations Noted in Meeting Rept 50-213/85-22.Corrective Actions:Design Change Installation Controls & Testing Requirements Improved & Previous Mods to Auxiliary Feedwater Sys Wiring Verified
- A05420, Forwards Addl Info Supporting Util 850916 Request for Exemption from Fire Protection Requirements of 10CFR50, App R,Per NRC 851204 Request.Verbal Responses Provided to NRC During 851210 Site Visit
- A05434, Forwards Util Implementation Ltr Rept Re Inadequate Core Cooling (ICC) Instrumentation Sys,As Committed in Util 850201 Submittal.Spds ICC Display Will Be Confirmed in Informational Ltr After Implementation of SPDS
- A05457, Forwards Results of RCS Seismic Reevaluations & Final Plans for Mods Identified in NRC Safety Evaluation of SEP Topic III-6.All Outstanding Issues Re Generic Ltr 84-04 & SEP Topic III-6 Resolved
- A05515, Responds to Violations Noted in Insp Rept 50-213/85-21. Corrective Actions:Station Supervisor Directed to Apply Disciplinary Action in Cases of Willful & Knowledgeable Noncompliance W/Procedure
- A05664, Responds to NRC Re Violations Noted in Insp Rept 50-213/86-01.Corrective Actions:Design Changes Made from 1979-1984 Reviewed & Revised.Violations Re Design Change Numbering Sys & QA Procedures Unjustified
- A05669, Responds to Violations Noted in Insp Rept 50-213/86-02. Corrective Actions:Procedure RAP 6.3-5 Changed to Stress That Compactor to Be Used Only for Normal Compacting Operations Unless Approved by Health Physics Supervisor
- A05679, Forwards Rev to non-LOCA DBA Analysis on Loss of Normal Feedwater Flow,Per Util 861024 Commitment.Conclusions for Loss of Normal Feedwater Flow Remain Unchanged from 860630 Reanalysis of non-LOCA DBA
- A05700, Responds to NRC Re Violations Noted in Insp Rept 50-213/86-05.Review of Complete Mod Packages Performed Per Tech Spec 6.5.2 by Plant Operations Review Committee
- A05763, Responds to Violations Noted in Insp Rept 50-213/86-03. Corrective Actions:Procedure NOP 2.19-5 Approved on 860409 to Be Routed to All Licensed Operators & Onsite Engineering Personnel by 860627
- A05775, Forwards Updated List of Completed Isap Topics & List of New Topics to Be Evaluated in Isap Program,Per 860509 Request.Deterministic Reviews of Each Topic Will Be Forwarded
- A05804, Responds to NRC Re Violations Noted in Insp Rept 50-213/86-08.Corrective Actions:Util Submitted Request for Schedular Exemption from Requirements of 10CFR50,App J, Pending Resolution of Integrated Safety Assessment 1.03
- A05805, Forwards Response to NRC Request for Addl Info Re Plant Crdr Implementation Plan,Per Suppl 1 to NUREG-0737.CRDR Summary Rept Will Be Provided by 880225
- A05884, Suppls 860729 Response to Violations Noted in Insp Rept 50-213/86-15.Nuclear Review Board Audits Conducted Annually Per Tech Spec 6.5.2.8.Tech Specs Implemented on 860101 & Audited in May & June of 1986
- A05899, Documents 860703 Oral Comments on NRC Isap Review of Facility Operating History Through 1984.All Refs to FSAR Should Be Revised to Facility Description & Safety Analysis
- A05914, Forwards Comments on NRC Contractor Draft Rept Re Probabilistic Safety Study,Per NRC 860716 Request
- A05946, Forwards Response to Open Items Identified During 860508 Meeting Re Proposed Rev to Pump & Valve Inservice Testing Program.Rev IWV-1 Table for Valve Testing Program, Description of ECCS Full Flow Test & Insp Procedure Encl
- A05951, Suppls Response to Violations Noted in Insp Rept 50-213/86-17,per 860903 Mgt Meeting.Info Consisting of Review of Actual Tank Levels & Annunciator Response Procedures for Tank Low Level Alarms Forwarded on 860908-12
- A05983, Responds to NRC Re Violations Noted in Insp Rept 50-213/86-19.Corrective Actions:Requirement to Follow Procedures Will Be Emphasized W/All Employees in Dept Meetings Planned for Sept/Oct
- A05988, Advises That Revised Inservice Testing Program & Associated Relief Requests Will Be Submitted by 870228 for Review. Testing Currently Being Performed Should Be Continued Until Code Required Testing Can Be Performed
- A05996, Remits Class III Fee for 820723 Application,Per
- A06006, Provides Clarification of Issues Raised During 860904 Enforcement Conference & Insp 50-213/86-22 Re Radiation Worker Overexposure Incident.Health Physics Technician Failed to Perform Satisfactorily Due to Inadequate Training
- A06040, Forwards Manual of Containment Boundary Valves Opened During Operation & Assessment of 861008 Event,Per 861014 Commitment in Response to Insp Rept 50-213/86-20.Event Not Reportable as LER Since Intent of Tech Specs Satisfied
- A06070, Requests That Portion of 850510 Amend Request Re Movement of Fuel within Reactor Pressure Vessel Be Retracted,Per Fm Akstulewicz 860903 Request That Util Reconsider Amend Request
- A06097, Submits Addl Info Re SEP Topic III-3.C, Inservice Insp of Water Control Structures, in Response to 860918 Request. Qualified Engineer Will Be Assigned Responsibility for All Phases of Insps
- A06102, Forwards Application Fee for Review & Approval of Interim Acceptance Criteria for Steam Generator Tubes,Per 860724 Submittal,In Response to 860922 Request
- A06113, Forwards Addl Info Re Spds,In Response to NRC 860924 Request on Isap Topic 1.20
- A06149, Forwards Fee for Request for Relief from Insp of Longitudinal & Circumferential Pipe Welds for Facility
- A06207, Forwards Responses to 861106 Request for Addl Info Re Util Request for Relief from Certain Code Category B-J Weld Inservice Insp Requirements.Isometric Drawings Encl
- A06214, Proposed Tech Specs,Providing Limiting Conditions for Operation Per Generic Ltr 83-37
- A06243, Responds to NRC Re Violations Noted in Insp Rept 50-213/86-27 on 861001-1117.Corrective Actions:Amend Request for Tech Spec Changes Will Be Submitted to Allow Opening of Valve CC-V-884 as Well as Other Identified Valves
- A06299, Informs That Insp Fees Noted in Encl Invoice Remitted to Ofc of Resource Mgt
- A06347, Forwards Fee for 861124 Request for Deferrment of Completion of Switchgear Room Halon Sys Mods to 1987 Refueling Outage or First Outage of Last 8 Wk Duration Commencing After 870101
- A06374, Responds to Violation Noted in Insp Rept 50-213/87-01. Corrective Actions:Procedure ACP 1.2-6.4 Revised on 870115 by Indicating That Substitutions Could Be Made Only If Substitute Instrumentation Has Equal or Better Accuracy
- A06384, Informs That Reactor Trip Sys Included in Westinghouse/Util Vendor Interface Program,Per NRC 870224 Request & Generic Ltr 86-38,Item 2.1.2
- A06421, Forwards Response to 870427 Request for Addl Info Re NULAP5. Lack of Water Slug Formation Due to HPI Would Be Independent of Nodalization in Sys Representation
- A06472, Forwards Response to NRC 870402 Request for Addl Info Re Nusco 140-1, Nusco Thermal Hydraulic Model Qualifcation Vol 1 (Retran). Util Staff Available to Hold Meeting During Wk of 870518
- A06508, Remits Fee Re 870401 Submittal of Updated Bimonthly Progress Rept & Design Info for New Switchgear Bldg,Per 870422 Request.Fee Required Since NRC Review Requested
- A06648, Forwards Fee for 870601 Application for Amend to Inservice Insp Programs to Utilize ASME Code Section XI,1983 Edition, Subarticle IWF-3400, Acceptance Stds, Per RM Diggs 870701 Request
- A06649, Updates 870805 Response to NRC Informing of Steps Taken to Correct Deviation Noted in Insp Rept 50-213/87-10. Review of Emergency Operating Procedures Will Be Completed by 880311.Simulator Training Matls Revised
- A06748, Forwards Response to NRC Topic Evaluations Status of Integrated Safety Assessment Program Topics & Review of Draft NUREG-1185.Attachment a Provides Discussion on Scope, Evaluation & Prioritization of Each Topic
- A06800, Responds to NRC Re Violations Noted in Insp Rept 50-213/87-21.Corrective Actions:General Employee Training for Util Personnel as Well as Safety,Security & Emergency Plan Training for Nonutil Personnel Will Be Upgraded
- A06850, Forwards Addl Info Re Miscellaneous Amends/Search Requirements for Amend to Physical Security Plan,Per NRC 871005 Request.Encl Withheld (Ref 10CFR2.790)
- A06867, Forwards Addl Info Re NUSCO-151, Haddam Neck Plant Reanalysis of Non-LOCA Design Basis Accidents, Per NRC 871015 Request.Responses to Questions from 870630 Meeting & Revised Pages for NUSCO-151 Also Encl