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List of results

• B16296, Clarifies What Is Expected to Be Contained within Basis Sections of Procedures at Plant.Comment Fields Do Not Contain Info Used During Performance of Procedure  + (Clarifies What Is Expected to Be Contained within Basis Sections of Procedures at Plant.Comment Fields Do Not Contain Info Used During Performance of Procedure)
• ML20106E305  + (Clarifies When Detailed Results of 12 SG Eddy Current Insp, Completed 921002,will Be Provided to NRC)
• ML20134P998  + (Clarifies Why 961018 50.72 4 H Rept Documenting Capability of Standby Liquid Control Sys to Perform Safety Function When Operating at Elevated Temps During Chemical Additions Was Retracted on 961115)
• ML19242D539  + (Clarifies Withdrawal of .Withdrawal Not Intended)
• ML20212E919  + (Clarifies Wording Inconsistencies Identified in Util License Change Request 92-10 for Plant, & Rev)
• ML19344D936  + (Clarifies Work Items Which Have Had Input on Preliminary Risk Assessment Schedule.Suggests That Meeting Be Held on 800918 or 800824 to Present Interim Rept on Risk Assessment Program)
• ML19347A842  + (Clarifies Workscope W/Westinghouse Hanford Co.Research at Hedl Involved No Water Reactor Work & Has Not Performed Work Sponsored by Water Reactor Industry.Westinghouse Hanford Co Is Separate Corporate Entity from PWR Div)
• W3P84-3237, Clarifies balance-of-plant Piping Preservice Insp Rept,Per .Classification of Class II Welds Based on 1974 Edition of ASME Boiler & Pressure Vessel Code.Insp Conducted Per 1977 Edition Through Summer 1978 Addenda  + (Clarifies balance-of-plant Piping Preservice Insp Rept,Per .Classification of Class II Welds Based on 1974 Edition of ASME Boiler & Pressure Vessel Code.Insp Conducted Per 1977 Edition Through Summer 1978 Addenda)
• ML20079D680  + (Clarifies from Connecticut Power & Light Co & Public Svc Co of New Hampshire.Ferc Has Not Decided on City of Holyoke Gas & Electric Dept Arguments as to New Hampshire Corridor)
• ML20154H372  + (Clarifies near-term Nrc/Doe Comparability Recommendations of Posting Guards at Matl Access Area Portals & Discusses Definition of Matl Access Area)
• LD-83-054, Clarifies plant-specific Info Needed Re CESSAR-F Supplemental Ser,Section 4.4.6, Statistical Combination of Uncertainties. No plant-specific Submittal Planned Since Verification of Values to Be Documented Internally  + (Clarifies plant-specific Info Needed Re CESSAR-F Supplemental Ser,Section 4.4.6, Statistical Combination of Uncertainties. No plant-specific Submittal Planned Since Verification of Values to Be Documented Internally)
• ML19351D457  + (Clarifies to J Axelrad of EPA About 800604 Meeting on Possible Misinterpretation of Statements Re 10CFR60 Changes)
• ML20010H689  + (Clarifies to Jr Miller Re Dismantling Plan.Areas Covered by License R-47 Will Be Transferred to License SNM-778 by Separate Action to Be Taken Subsequent to Final IE Insp.Requested Environ Info Encl)
• ML20203P944  + (Clarifies to NRC Re Spds.Forwards Rev 2 to Procedure EIP-30, Isolator Circuit Differential High Voltage Fault Test Procedure)
• ML20064G396  + (Clarifies to NRC Re Survey Monitoring & Tech Spec Surveillance Requirements.Points Out That Many of the Survey Points Differ Re Established Base Line Survey Compared to Bases Stated in Tech Spec.No Safety Implications in Change)
• ML20248B361  + (Clarifies,In Writing,Tennessee Perspective Re Regulation of DOE Facilities Operated by Various Contractors)
• TSTF-265  + (Clarify 3.4 NON-OPERATING LOOP SRS)
• TSTF-568  + (Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2)
• TSTF-534  + (Clarify Application of Pressure Boundary Leakage Definition)
• TSTF-493  + (Clarify Application of Setpoint Methodology for LSSS Functions)
• TSTF-474  + (Clarify Bases of Vacuum Breaker Functional Test Frequency)
• ML13151A033  + (Clarify Communication Responsibilities at Rhode Island Nuclear Science Center While Searching for New Director)
• TSTF-438  + (Clarify Exception Notes to Be Consistent with the Requirement Being Excepted)
• TSTF-153  + (Clarify Exception Notes to Be Consistent with the Requirement Being Excepted)
• TSTF-526  + (Clarify LCO 3.8.1 SR Notes Regarding Momentary Transients Outside the Load Band)

• TSTF-053  + (Clarify Manual Porvs Are Capable of Mitigating an Overpressure Event)

• TSTF-275  + (Clarify Requirement for EDG Start Signal on RPV Level - LOW, LOW, LOW During RPV Cavity FLOOD-UP)
• TSTF-530  + (Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09)
• TSTF-558  + (Clarify SR Bases Added by TSTF-523)
• TSTF-400  + (Clarify SR on Bypass of DG Automatic Trips)
• TSTF-524  + (Clarify Th Application of SR 3.0.2 to SR 3.1.3.2, Mtc)
• TSTF-147  + (Clarify That RPS and ESFAS Matrix Logic Testing Does Not Affect Operability)
• TSTF-211  + (Clarify That Remove All Power to the CRD System Means Remove Power to CRD Trip Breakers)
• TSTF-529, Clarify Use and Application Rules  + (Clarify Use and Application Rules)
• TSTF-543  + (Clarify Verification of Time Constants)
• TSTF-046  + (Clarify the CIV Surveillance to Apply Only to Automatic Isolation Valves)
• TSTF-464  + (Clarify the Control Rod Block Instrumentation Required Action)
• TSTF-335  + (Clarify the Ice Basket 20 Basket Weight Criteria)
• TSTF-555  + (Clarify the Nuclear Instrumentation Bases Regarding the Detection of an Improperly Loaded Fuel Assembly)
• TSTF-109  + (Clarify the Qptr Surveillances)
• ML19098B470  + (Clarifying Certain Statements Reported in NRC Summary Re Fracture Toughness Requirements of Unit 1 Reactor Vessel)
• ML20211G647  + (Clarifying Decision on Remand Re Adequacy of Nassau County Veterans Memorial Coliseum as Reception Ctr for Monitoring, Decontaminating & Transferring of Evacuees to Sheltering Facilities in Event of Emergency.Served on 861030)
• ML19030A863  + (Clarifying How Fall 1976 and Spring 1979 Commercial Operation Dates Relate to the Reduced Rate of Load Growth)
• RS-09-017, Clarifying Information Concerning Request to Implement Subsequent Edition of ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants  + (Clarifying Information Concerning Request to Implement Subsequent Edition of ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants)
• ULNRC-05353, Clarifying Information Regarding Application for License Amendment to Revise Technical Specification 3.6.7, Recirculation Fluid Ph Control System  + (Clarifying Information Regarding Application for License Amendment to Revise Technical Specification 3.6.7, Recirculation Fluid Ph Control System)
• ML15075A026  + (Clarifying Information Related to Response to Request for Additional Information Proposed License Amendment Request Permanent Fifteen-Year Type a Test Interval)
• ML122790101  + (Clarifying Information for Question No. 4 (with Attachment))
• ML023440140  + (Clarifying Information for Radiological Emergency Response Plan Change Submitted May 6, 2002 for Callaway Plant)
• ML18227B286  + (Clarifying Proposed Tech Spec Changes Re Allowing Full PWR Operation with Up to 25% of Steam Generator Tubes Plugged, Pertaining to Reactor Core Thermal Hydraulic Limits)
• ML102090751  + (Clarifying Relief Request No. 16 Nozzle-to-Vessel Weld Exam)
• ML110740158  + (Clarifying Response to Request for Additional Information: License Amendment Request 236, Automatic Operation of Transformer Load Tap Changers)