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ML20035B283
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Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
Accession number
ML20035B283  +
CFR
10 CFR 50.72 +, 10 CFR 21.21 +, 10 CFR 21 +, 10 CFR 50.63 +, 10 CFR 21.1 +, 10 CFR 50.55a#f +, 10 CFR 50.55a#g5ii +, 10 CFR 50.109#c +  and 10 CFR 50.109#a4i +
Docket
05000293  +  and 00293  +
From
Wiggins J +  and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +
Generic letter
NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +, ML20035B283 +  and ML20035B283 +
Hours
2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +
In package
ML20035B284 +
Issue date
March 26, 1993  +
Letter
BECO-92-044, Forwards Rev to 910226 Response to Suppl 3 to Generic Ltr 89-10 Per motor-operated Valve Insp Conducted on 920309-11. Valve Will Operate Under Design Basis Conditions,Based on Review of Inel Test Results +
Manufacturer
General Electric +
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10:47:05, 20 December 2024  +
NRC bulletin
NRC Bulletin 85-03 +
NUREG
NUREG/CR-5140 +
Page count
24  +
Person
Eugene Kelly +
Power source
345kV +
Procedure
ESP +, Emergency Operating Procedure +  and EOP-16 +
Site
Pilgrim +
Start date
March 26, 1993  +
State
Pennsylvania +, Washington +, Massachusetts +  and Idaho +
System
High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Emergency Core Cooling System +  and Low Pressure Coolant Injection +
TS
TS-1.0.E +  and TS-3.1.A +
Title
Responds to ,Containing Questions Re Reactor Vessel Water Level Instrumentation & motor-operated Valves at Pilgram Nuclear Power Station.Encl Response Provides Addl Info Requested  +
To
Mary Lampert +  and DUXBURY NUCLEAR ADVISORY COMMITTEE +
Topic
Reactor Vessel Water Level +, Probabilistic Risk Assessment +, High Energy Line Break +, Loss of Offsite Power +, Operability Determination +, Backfit +  and Basic Component +
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http://pbadupws.nrc.gov/docs/ML2003/ML20035B283.pdf  +
 
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