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ML17059C621
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Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
ANSI code
ANSI/ANS 3.5-1985 +
Accession number
ML17059C621  +
Agency
New York State Energy Research and Development Authority +
Atomic Element
Iodine +, Hydrogen +  and Zinc +
CFR
10 CFR 50 Appendix B +  and 10 CFR 50 Appendix R +
Cornerstone
Emergency Preparedness +
Docket
05000220  +, 05000410  +, 00220  +  and 00410  +
Equipment trip
Turbine Trip +
From
Crlenjak R +  and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +
Generic letter
NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +  and NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +
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ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +, ML17059C621 +  and ML17059C621 +
Inspection procedure
IP 84750 +, IP 86750 +, IP 83750 +, IP 71001 +  and IP 61725 +
Issue date
April 9, 1999  +
Letter
ML20203G107 +
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16:34:26, 9 January 2025  +
NRC information notice
Information Notice 95-22 +
NUREG
NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +
Page count
76  +
Power source
115kV +  and 4.16kV +
Procedure
Emergency Plan +
Regulatory Guide
Regulatory Guide 1.149 +
SSC
1C-t +
Site
Nine Mile Point +
Site license
Nine Mile Point +
Start date
April 9, 1999  +
State
New York +
System
Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Control Room Emergency Ventilation +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Control Room Envelope +, Rod Worth Minimizer +, Rod Sequence Control System +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-6.8.1 +, TS-4.8.2.1 +, TS-1.4 +, TS-4.3.1.2 +, TS-4.6.6.1 +, TS-3.3.0 +, TS-3.1.4.d +, TS-4.6.2.a +, TS-4.1.4.2 +  and TS-4.7.3.e +
Title
Discusses Results of Plant Performance Review of Nine Mile Point Units 1 & 2 Completed on 990223.Forwards Historical Listing of Plant Issues That Were Considered & Advises of Planned Insp Effort Resulting from Nine Mile Point PPR  +
To
Mueller J +  and Niagara Mohawk +
Topic
Safe Shutdown +, Unanalyzed Condition +, Reactor Vessel Water Level +, High Radiation Area +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Temporary Modification +, Emergency Lighting +, High Energy Line Break +, Double blade guide +, Job Performance Measure +, Feedwater Heater +, Process Control Program +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Operability Determination +, Scaffolding +, Power change +  and Restart +
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http://pbadupws.nrc.gov/docs/ML1705/ML17059C621.pdf  +
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