3F0413-03, Attachment C, Off-Site Dose Calculation Manual, Revision 34
NRC-89-0212, Provides Results of Tasks Re Suppression Pool Temp Measurements.Testing Confirms Acceptability of Methodology Used in Measuring Suppression Pool Bulk Temp
PNO-III-85-073, on 850820,contaminated Resins Used in Condensate Polishing Sys Sent Offsite for Regeneration. Resins Being Returned to Site.No Detectable Radiation Found at Vendor Facility
PNO-III-85-091, on 851022,loss of Offsite Power Occurred Due to Inadvertent Opening of Circuit Breaker in Switchyard. Caused by Personnel Winterizing Equipment.Accumulator Repressurized & Circuit Breaker Closed
PNO-II-85-056, on 850517,reactor Tripped.Caused by Loss of Offsite Power Due to Fire Disabling 500-kV Line Near Util Substation.Unusual Event Declared.All Safety Sys Functioned Normally.Power Restored
IA-87-498, Submits Facility Related Info Re Personnel Conduct & Emergency Support Organization Phone List
PNO-III-86-071, on 860719,lightning Struck Main Transmission Line Immediately Adjacent to Plant,Resulting in Loss of All Offsite Power.Both Diesel Generators Automatically Started, Picking Up All Vital Loads as Designed.Power Restored
PNO-III-87-128, on 871002,facility Tripped from 7% Power Due to High Water Level in One of Four Steam Generators,Creating Loss of Offsite Power.Caused by Personnel Error.Licensee Inspecting Damage to Auxiliary Transformer Disconnect Links
PNO-III-87-097A, on 870714,preliminary Review of Incident Determined That Startup Transformer 1-2 Faulted.Cause of Initial Fault Still Under Investigation
3F0789-25, Responds to 890705 Meeting & Re Alternate Offsite Power Supply Enhancements.Util Actively Pursing Plans to Upgrade Current Alternate Offsite Power Source to One Which Will Have High Capacity
HBL-87-007, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1986
B12318, Discusses NRC Concerns Re Reliance on feed-&-bleed to Address Issues Associated W/Environ Qualification & High Energy Line Breaks.Viewgraphs from 860917 Meeting Encl
PLA-2829, Rev 3 to Emergency Plan Implementing Procedure EP-IP-032, General Ofc Activation & Rev 5 to EP-IP-033, Dose Assessment & Protective Actions. W/Revised Lists of Effective Pages &
3F0288-19, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987
BSEP-88-0105, Semiannual Radioactive Effluent Rept,Jul-Dec 1987
PNO-III-85-071A, circuitry Mods to Plant Transformers Completed & Successfully Tested on 850819.Mods Instituted Due to Failure in Switching Mechanism in Auxiliary Main Station Transformer
JAFP-96-0190, Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995
3F0495-20, Radioactive Effluent Release Rept 1994 Crystal River Unit 3
BECO-83-231, Radioactive Effluent & Waste Disposal Rept Including Radiological Impact on Humans,Jan-June 1983
BECO-91-045, Annual Dose Assessment to General Public from Radioactive Effluents,1990
W3P85-3296, Responds to NRC Re Violation Noted in Insp Rept 50-382/85-23.Corrective Actions:Rev 4 to Procedure EP-2-052 & Rev 6 to EP-1-001,Attachment 7 Revised to Provide Addl Guidance on Required Protective Action Recommendations
BECO-LTR-92-104, Pilgram Nuclear Power Station Radioactive Effluent & Waste Disposal Rept Including Meteorological Data for 920101-0630
LD-92-059, Forwards Nonproprietary & Proprietary Slides Presented at 920319 Meeting W/Nrc Re Sys 80+ Reactor Coolant Pump Seal Design & Performance as Suppl to RAI Responses,In Ref to .Proprietary Slides Withheld (Ref 10CFR2.790)
BECO-LTR-95-028, Radioactive Effluent & Waste Disposal Rept Including Meteorological Data Jul-Dec 1994
05000302/LER-1985-032, :on 851205,confirmed That Equipment Associated w/230 Kv Switchyard Installed on 780701 Not in Compliance W/Design & Regulatory Requirements.Caused by Personnel Error.Changes Made to Protective Relays
JAFP-94-0240, 1993 Radiological Environ Operating Rept Ja FitzPatrick Nuclear Power Plant
HBL-90-012, Semiannual Radioactive Effluent Release Rept Jul-Dec 1989
L-83-372, Public Version of Emergency Plan Implementing Procedure 1102, Duties of Recovery Manager,Offsite Emergency Organization
BVY-90-017, Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989
05000324/LER-1989-009, :on 890617,manual Reactor Scram Initiated Per NRC Bulletin 88-007 Due to Loss of Recirculation Pumps, Causing Loss of Offsite Power & Containment Isolation. Caused by Personnel Error.Hpci Sys Secured
PNO-I-81-096, on 810819,FEMA Informed NRC That State & Local Govt Planning in Event of Accident at Sites Found Adequate.Issues of Offsite Preparedness in NRC Found Satisfactorily Resolved
PNO-I-90-095, on 901031,radioactive Matl Transported Offsite as Nonradioactive Matl