NL-14-067, Reply to Request for Additional Information Regarding the License Renewal Application
L-13-399, Discharge Monitoring Report (NPDES) Permit No. PA0025615
NG-10-0265, Duane Arnold, 2009 Annual Radiological Material Release Report
NG-09-0308, Duane Arnold - 2008 Annual Radiological Material Release Report
JAFP-08-0131, Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C
L-22-171, Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-063
BVY-95-114, Provides Addl Info Re GL 88-20, IPE for Severe Accident Vulnerabilities 10CFR50.54(f)
BECO-83-231, Radioactive Effluent & Waste Disposal Rept Including Radiological Impact on Humans,Jan-June 1983
IA-85-610, Abstracted Records Showing Educ,Training & Work Experience Data for Senior Reactor Operators
3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With
VPN-027-99, Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2
05000416/LER-1985-041, :on 851031,operability of Alternate Method of DHR Not Demonstrated within 24 H Period Per Tech Spec 3.4.9.2.Caused by Inadequate Coordination of Time Changes for Required Action.Shift Checksheet Revised
1CAN089015, Provides Written Documentation to Followup on 900811 Request Re Temporary Waiver of Compliance from Tech Specs 3.3.6 & 3.4.5.1 Re Limiting Condition for Operation.Supporting Info Encl
L-81-233, Forwards Responses to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). No Corbicula Sp or Mytilus Sp Present in Vicinity of Facility
A01877, Forwards Station Procedures OP 302,SP 631.1,SP 631.2, Sp 631.4,SP 631.11,SP 1051,IC 414c,WP-1-24,CNF-7995-4, CNF-F-FFB & CNF-FF & One Oversize Drawing in Response to NRC .Aperture Card Will Be in PDR
A01698, Forwards Info Re SEP Topics VI-2.D & VI-3,concerning Mass & Energy Release for Postulated Pipe Breaks Inside Containment & Containment Pressure & Heat Removal Capability, Respectively.Addl Details Proprietary to GE
L-2017-074, Redacted - St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 12, Radiation Protection
RNP-RA/14-0125, Response to NRC Request for Additional Information Related to Refueling Outage 28 Steam Generator Tube Inspection Report