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Issue date | Title | Topic | |
---|---|---|---|
ML19308D693 | 27 July 1977 | Startup Rept | Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Fuel cladding Power change Overspeed trip |
ML19308D701 | 9 December 1976 | Reactor Containment Bldg Preoperational Integrated Leak Rate Test. | Local Leak Rate Testing |
ML19308D745 | 21 July 1978 | Tech Spec Change Request 31 Re Tech Spec 2.1,2.2 & 3.2, Addressing Removal of Orifice Rod Assemblies & Calculation of Resultant Changes to Core Parameters by BAW-2 DNB Correlation Per BAW-1490,Revision 1 | Fuel cladding |
ML19308D746 | 21 July 1978 | Tech Spec Change Request 32 Re Tech Specs 3.1,3.2,4.1 & 4.2, Incorporating Limiting Condition for Operation,Surveillance Requirement & Related Bases on Physical Insertion of Axial Power Shaping Rod Group | Boric Acid Shutdown Margin |
ML19308D916 | 4 April 1974 | Proposed Tech Spec 15.4.11 Re Snubber Surveillance Program | |
ML19309D450 | 24 March 1980 | Proposed Changes to Tech Specs,App a Re Reactivity Control Sys | Boric Acid Shutdown Margin Stress corrosion cracking |
ML19309F167 | 23 April 1980 | Tech Spec Change Request 51,Revision 1 (App a) Re Organizational Changes to QA Program | |
ML19309G728 | 23 April 1980 | Tech Spec Change Request 62 Re Tech Specs 1-5 for Definitions,Limiting Conditions for Operation,Environ Surveillance & Administrative Controls | |
ML19312D860 | 30 April 1980 | Proposed Tech Spec Pages Re Change Request 61 Addressing Cycle 3 Operation of Facility at Present Licensed Core Power Level | Boric Acid Shutdown Margin Stress corrosion cracking Fuel cladding |
ML19316A744 | 21 May 1980 | Tech Spec Change Request 63 to Change Tech Specs 3/4 & B 3/4 Re Limiting Conditions for Operation & Surveillance Requirements | Offsite Circuit |
ML19317G368 | 21 July 1977 | ETS Change Requests 3 & 6 Re ETS 1.1,2.4,3.1,3.2, & 5.3 Through 5.6,correcting Typographical Errors,Consolidating Reporting Requirements & Deleting Inapplicable Sampling Stations from Preoperational Program Element | Grab sample |
ML19317G403 | 3 December 1976 | App a to License DPR-72,Tech Specs,Sections 1.0-6.12 Re Definitions,Safety Limits & Limiting Safety Sys Settings, Limiting Conditions for Operation & Surveillance Requirements,Design Features & Administrative Controls | Safe Shutdown Boric Acid Shutdown Margin Reactor Vessel Water Level Packing leak High Radiation Area Ultimate heat sink Grab sample Fire Barrier Hydrostatic Operating Basis Earthquake Tornado Missile Protection Stress corrosion cracking Earthquake Fuel cladding Pressure Boundary Leakage Offsite Circuit Continuous fire watch Fire Protection Program Fire Watch Power change Unidentified leakage Eddy-Current Testing Operational leakage |
ML19317G427 | 1 August 1977 | Tech Spec Change Request 7 Re Tech Specs 4-1,allowing Completion of Thermal Plune Survey & Allowing Facility Operation Below 80% Min Capacity | |
ML19317G585 | 6 June 1978 | Tech Spec Change Request 29 Re Tech Specs 3.1,3.2,4.1 & 4.2,changing Min Contained Borated Water Vol & Boron Concentration of Concentrated Boric Acid Storage Sys & Related Bases, & Regulating Rod Group Insertion Limits | Boric Acid |
ML19317H031 | 10 May 1979 | Test Rept for Seismic Qualification Testing of Potential Transformer Model JVM4 & Current Transformer Model JCM4. | |
ML19318B706 | 23 April 1980 | Revised Tech Specs for Administrative Controls | Fire Protection Program |
ML19319C723 | 4 August 1977 | Tech Spec Change Request 8 Re Tech Specs 8-4 & 8-5,extending Allowable Internal Between Surveillance Testing from 90 to Approx 97 Wks | |
ML19319C792 | 20 May 1977 | Tech Spec Change Request 2 Re Tech Specs 6-1 Through 6-13, Revising Offsite Organization for Technical Support & Facility Mgt | Boric Acid Shutdown Margin |
ML19319C811 | 1 September 1977 | Tech Spec Change Request 9 Re Tech Specs 3.6 & 4.6,affecting Reactor Bldg Spray & ECCS Storage Tanks Drawdown Transient Analysis | Stress corrosion cracking |
ML19319C830 | 28 September 1977 | Tech Spec Change Request 10b Re Tech Specs 6.8-6.12,updating Reporting Requirements | High Radiation Area |
ML19319C844 | 11 October 1977 | Tech Spec Change Request 11 Re Tech Spec 1.16,adding Definition of Unplanned Release of Radioactive Matl from Site | Anticipated operational occurrence |
ML19319C862 | 8 November 1977 | Tech Spec Change Requests 12a,12b,12c & 12d Re Tech Specs 1.1-1.7,2.1-2.2,3.1,3.4. & 4.4,deleting All Ref to Operation W/Less than Three Reactor Coolant Pumps in Operation & Deleting Ref to Monitoring Condenser Water Boxes | Hydrostatic |
ML19319C922 | 21 November 1977 | Tech Spec Change Request 13 Re Tech Specs 3.5 & 4.6,adding Detail to Surveillance Requirements to Clarify How Structural Integrity of Tendons Will Be Demonstrated | |
ML19319D074 | 17 March 1978 | Tech Spec Change Request 21 Re Tech Spec 3.2,deleting Measurement Independent Quadrant Power Tilt Values from Table 3.2-2 & Adding Values to Bases for Tech Spec 3.2 | |
ML19319D075 | 17 March 1978 | Tech Spec Change Request 22 Re Tech Spec 4.4.6.2.c,deleting Words W/Modulating Valve Fully Open. | |
ML19319D076 | 17 March 1978 | Tech Spec Change Request 23 Re Tech Specs 5.3 & 5.6,changing Max Enrichment in Weight % of U-235 from 3.50 to 3.30 & Indicating That High Density Spent Fuel Racks to Have 10.5 Inch center-to-center Spacing | |
ML19319D077 | 17 March 1978 | Tech Spec Change Request 24 Re Tech Specs 3.6 & 4.6,changing Tech Spec 3/4.6.3.1 to Apply to Containment Automatic Isolation Valves & Deleting Wording During Cold Shutdown or Refueling Mode in Tech Spec 4.6.3.1.2 | |
ML19319D078 | 17 March 1978 | Tech Spec Change Request 25 Re Tech Spec 3.7 & 4.7,revising Basis for Secondary Water Chemistry Spec | |
ML19319D165 | 9 May 1978 | Refueling Procedure FP-203,Revision 1, Defueling & Refueling Operations. | |
ML19319D169 | 15 May 1978 | Refueling Procedure FP-401,Revision 4, Reactor Vessel Closure Head Removal & Replacement. | |
ML19319D171 | 13 July 1976 | Surveillance Procedure SP-672,Revision 2, Procedure for Load Testing New Fuel Elevator. | |
ML19319D173 | 1 July 1976 | Surveillance Procedure SP-671,Revision 4, Spent Fuel Handling Bridge Load Surveillance. | |
ML19319D174 | 7 July 1978 | Refueling Procedure FP-601,Revision 5, Fuel Handling Equipment Operations. | |
ML19319D178 | 15 May 1978 | Refueling Procedure FP-402,Revision 6, Reactor Vessel Closure Head Stud Removal & Replacement. | Breakaway torque |
ML19319D222 | 22 January 1976 | Surveillance Procedure SP-530, Demonstration of Auxiliary Bldg Overhead Crane (FHCR-5) Interlock Operability. | |
ML19319D223 | 1 July 1976 | Surveillance Procedure SP-531,Revision 2, Spent Fuel Handling Bridge Interlock Surveillance. | |
ML19319D227 | 8 April 1978 | Surveillance Procedure SP-532,Revision 3, Reactor Bldg Main & Auxiliary (FHCR-1 & FHCR-2) Fuel Handling Bridges Electrical Interlock Surveillance. | |
ML19319D232 | 31 May 1978 | Surveillance Procedure SP-434,Revision 2, Fuel Storage Pool Missile Shields. | |
ML19319D238 | 6 July 1978 | Surveillance Procedure SP-601,Revision 4, Procedure for Load Testing Slings & Lifting Fixtures. | |
ML19319D240 | 18 April 1978 | Surveillance Procedure SP-670,Revison 3, Reactor Bldg Fuel Handling Bridges (FHCR-1 & 2) Load Test. | |
ML19319D253 | 15 May 1978 | Refueling Procedure FP-1001,Revisions 2, Spent Fuel Handling. | |
ML19319D256 | 13 April 1973 | Radiological Control Procedure RP-1601,Revision 1, Radiation Protection Manual. | High Radiation Area Overexposure |
ML19323F173 | 6 May 1980 | Operating Guidelines for Once-Through Steam Generator Rupture. Steam Generator Overfill Guidelines & Assessment of Licensed Operator Errors Encl | |
ML19324B534 | 13 October 1989 | Rev 11 to Procedure AR-403, PSA H Annunciator Response. | |
ML19324C262 | 27 October 1989 | Revised Procedures,Including Rev 13 to AP-380, Engineered Safeguards Actuation & Rev 10 to EP-290, Inadequate Core Cooling. | |
ML19324C553 | 17 September 1975 | Test Program Response to Reg Guide 1.79. | Boric Acid Coatings Met Tower |
ML19325E341 | 30 September 1989 | Rev 0 to NOD-39, Environ Qualification Program. | Post Accident Monitoring |
ML19325E358 | 18 October 1989 | Rev 12 to Procedure AP-770, Emergency Diesel Generator Actuation. | |
ML19325E809 | 11 September 1989 | Rev 0 to NEP-232, Equipment Qualification Walkdowns. | |
ML19325E811 | 31 October 1989 | Proposed Tech Specs Re Heatup,Cooldown & Inservice Leak & Hydrostatic Testing Pressure/Temp Limits Based on 15 EFPY of Reactor Operations | Hydrostatic |