0CAN038901, Requests That Violation Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Be Clarified or Rescinded
1CAN128603, Proposed Tech Specs,Incorporating Administrative Changes to Clarify Ambiguities,Remove Outdated Requirements & Provide Consistency
U-601239, Application for Amend to License NPF-62,revising Tech Spec to Support Cycle 2 in Max Extended Operating Domain & W/ Reduced Feedwater Temps.Supporting Documentation Encl.Fee paid.NEDC-31546P Withheld
ST-HL-AE-1901, Forwards Justifications & Specific Data Re Proposed Draft Rev 2 to Tech Specs,Including Markups of Affected Sections
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
HNP-04-008, License Amendment Request: Steam Generator Water Level Instrumentation Usage, Technical Specifications 4.4.1.3.2 and 3.4.1.4.1.b, and Administrative Update to the Index
05000324/LER-1986-025-01, :on 861120,determined That 861119 Surveillance of Reactor Jet Pump Missed.Caused by Personnel Error. Surveillance Performed Satisfactorily.Personnel Disciplined & Training Initiated
05000416/LER-1986-031, :on 860901,prior to Changing from Startup to Run,Aprm Flow Channels Not Checked as Required by Startup Integrated Operating Instruction.Caused by Technician Error in Interpreting Procedure.Procedure Revised
05000312/LER-1987-017, :on 870209 & 0320,discrepancies in Local Leak Rate Test (LLRT) Discovered.Caused by Personnel Error.Tech Specs,Updated Sar,Integrated Leak Rate Tests & LLRT Will Be Revised to Reflect Addl Test Requirements
05000324/LER-1986-025, :on 861119,determined That Surveillance Testing for Reactor Jet Pump Not Performed.Caused by Personnel Error.Personnel Involved discplined.Real-time Training Completed
05000324/LER-1996-004-03, :on 960913,jet Pump Surveillance Was Not Performed Prior to Exceeding 25% Reactor Power.Caused by Human Performance Errors.Appropriate Disciplinary Action Taken W/Individuals Involved
05000269/LER-1995-008, :on 951129,determined That Containment Isolation Valve Inoperable Due to Deficient Design Change. Valve 3RC-5 Disabled in Safety Position (Closed) Until Gear Ratio in Valve Corrected
05000416/LER-1984-041, :on 840909,more than One Jet Pump Failed diffuser-to-lower-plenum Differential Pressure Surveillance Testing.Cause Not Stated.Three Transmitters Replaced & Three Recalibr
05000321/LER-1994-005-01, :on 940501,unplanned ESF Sys Actuations Occurred Due to Loose Connections in Power Distribution Panel.Loose Connections Checked & Tightened
0CAN088107, Responds to NRC Re Violations Noted in IE Insp Repts 50-313/81-18 & 50-368/81-16.Corrective Actions: Sampling of Control Room Ventilation Intake Duct to Establish That No Significant Radioactive Matl Was Present
CEO-88-002, Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid
AECM-83-0422, Application for Amend to License NPF-13,proposing Tech Spec Changes to Enhance Clarity or Provide Consistency W/Plant Design & Operation,Per NRC 821020 Confirmation of Action Ltr.Detailed Description of Proposed Changes Encl
05000366/LER-1980-107-03, /03L-0:on 800719,during Routine Power Ascension, Determined That Method for Verifying Jet Pump Operability Not in Compliance W/Tech Specs.Caused by Inaccurate Method Re Calculating Delta P Variance.Method Revised
05000289/LER-1980-006-01, /01T-0:on 800325,during Periodic Reactor Bldg Local Leak Rate Testing,Containment Isolation Valve RB-V7 Had Excessive Leakage.Cause Suspected to Be Seat Damage. Improved Valve Placed on Order
05000313/LER-1978-031-03, /03T-0:on 781214,barrel Test on Emergency Escape Hatch C4 & Personnel Hatch C2 Not Performed as Scheduled. Caused by Scheduling Error Due to Responsibility Change from One Supervisor to Another
05000397/LER-1991-027, :on 910930,question on Jet Operability & Surveillance Applicability in Operational Conditions 1 & 2 Below 25% Rated Thermal Power Raised.Caused by Inadequate Procedure.Ts Amend Request Will Be Submitted
05000325/LER-1989-011, :on 890404,determined That Reactor Jet Pump Once Per 24 H Operability Surveillance Had Been Missed Prior to Entering Operation Condition 2.Caused by Inadequate Review of Surveillance Rept
05000312/LER-1985-027, :on 851214,licensee Discovered That Testing Requirements for Containment Personnel Air Lock Seals Not in Accordance W/Tech Spec 4.4.1.2.5.(c).Caused by Technicians Not Adhering to Procedures.Retest Conducted on 851216