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List of results

• ML20128L573  + (Forwards Rev 4 to Topical Rept - 066, Oyster Creek Cycle 14 Colr. Rev Reflects Cycle 14 Core Design & Safety Results)
• ML20128L577  + (Forwards Rev 4 to Topical Rept - 066, Oyster Creek Cycle 14 Colr. Rev Reflects Cycle 14 Core Design & Safety Results)
• ML20235K357  + (Forwards Rev 4 to Topical Rept PCC-QAPD, QA Program Description. Rept Describes QA Program for Power Computing Co,In Compliance w/10CFR50 App B.Fee Paid)
• ML20244A738  + (Forwards Rev 4 to Topical Rept STD-R-05-007, Cement Solidified Wastes to Meet Stability Requirements of 10CFR61. Rev Includes Addl Solidification Testing Program Description & Results,Per Request at 890206 Meeting)
• ML20081M556  + (Forwards Rev 4 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21))
• ML20072E892  + (Forwards Rev 4 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21))
• L-86-517, Forwards Rev 4 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 4 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21))
• ML20100K358  + (Forwards Rev 4 to Training & Qualification Plan.Rev Withheld (Ref 10CFR2.790))
• ML20094M748  + (Forwards Rev 4 to Training & Qualification Plan for Security.Rev Withheld (Ref 10CFR73.21))
• ML20045F732  + (Forwards Rev 4 to Training Dept Instruction (Tdi) TDI-514, Fuel Handler Initial Training & Rev 4 to TDI-515, Fuel Handler Continuing Training, in Response to NRC 930528 RAI Re Facility Fuel Handling & TS Changes)
• ML20071N078  + (Forwards Rev 4 to Transport of Toxic Chemicals & Control Room Habitability Study, in Response to NRC Request & in Conjunction W/Suppl 3 to SER)
• ML20135B514  + (Forwards Rev 4 to Trojan Nuclear Plant Defueled Sar. Changes to Page Identified by Margin Bars Adjacent to Change & Rev Numbers at Page Bottom)
• VPN-070-95, Forwards Rev 4 to Trojan Nuclear Plant Defueled Sar. Changes to Page Identified by Margin Bars Adjacent to Change & Rev Numbers at Page Bottom  + (Forwards Rev 4 to Trojan Nuclear Plant Defueled Sar. Changes to Page Identified by Margin Bars Adjacent to Change & Rev Numbers at Page Bottom)
• ML20206U243  + (Forwards Rev 4 to Univ of Fl Training Reactor Operator Requalification & Recertification Training Program Plan for July 1999 - June 2001. Changes,Discussed)
• ML20101L357  + (Forwards Rev 4 to Univ of UT Emergency Plan for Triga Nuclear Reactor)
• L-89-113, Forwards Rev 4 to Updated FSAR & Advises That Cover Ltr for Previous Submittal of 880404 Inadvertently Stated That Rev 3 Covered Period from 861007-871005 Rather than Actual Period of 861007-871006.List of Plant Changes Also Encl  + (Forwards Rev 4 to Updated FSAR & Advises That Cover Ltr for Previous Submittal of 880404 Inadvertently Stated That Rev 3 Covered Period from 861007-871005 Rather than Actual Period of 861007-871006.List of Plant Changes Also Encl)
• ML20070S266  + (Forwards Rev 4 to Updated FSAR & Annual Safety Evaluation Summary Rept 1990)
• ML17056C107  + (Forwards Rev 4 to Updated FSAR & Ser,Providing Description of Changes to Facility Design,Procedures,Tests & Experiments)
• ML17056C108  + (Forwards Rev 4 to Updated FSAR & Ser,Providing Description of Changes to Facility Design,Procedures,Tests & Experiments)
• ML20203F968  + (Forwards Rev 4 to Updated FSAR for Beaver Valley Power Station,Unit 1.App a, QA Program, Revised to Reflect Util Mgt Structure & Current QA Unit Practices)
• ML20211Q870  + (Forwards Rev 4 to Updated FSAR for Cooper Nuclear Station. Changes Through 860122 Reflected in Submittal.Discusses Changes Not Previously Submitted to NRC)
• ML20151L295  + (Forwards Rev 4 to Updated FSAR for LaSalle County Station Units 1 & 2)
• B12084, Forwards Rev 4 to Updated FSAR for Millstone Unit 2.Rev Provides Changes Completed Since 850628 Submittal  + (Forwards Rev 4 to Updated FSAR for Millstone Unit 2.Rev Provides Changes Completed Since 850628 Submittal)
• ML20203F222  + (Forwards Rev 4 to Updated FSAR for North Anna Units 1 & 2. Revised Info up-to-date as of 860101 & Reflects Previously Submitted Info & Analyses)
• ML20203E922  + (Forwards Rev 4 to Updated FSAR for Prairie Island Nuclear Generating Plant.Two New Vols Provided for Reprinting of Apps of Original FSAR)

• SNRC-1773, Forwards Rev 4 to Updated FSAR for Shoreham Nuclear Power Station,Unit 1  + (Forwards Rev 4 to Updated FSAR for Shoreham Nuclear Power Station,Unit 1)

• ML20153F883  + (Forwards Rev 4 to Updated Fire Hazards Analysis for Facilities)
• ML13330B373  + (Forwards Rev 4 to Updated Fire Hazards Analysis for Facilities.W/O Encl)
• ML20055H281  + (Forwards Rev 4 to Updated Fire Protection Plan)
• ML20206T828  + (Forwards Rev 4 to Updated Fsar,Reflecting Changes to Facility,Procedures or Tech Specs & Changes Identified in Annual Rept)
• ML20207L564  + (Forwards Rev 4 to Updated Fsar,Replacing 860630 Transmittal Ltr Lost During Reproduction.Future Submittals Will Require Receipt Ack to Avoid Recurrence of Util Error)
• ML20203E149  + (Forwards Rev 4 to Updated Fsar.Rev Includes Effects of Changes Made to Facility or Procedures,Util Safety Evaluations & Analyses of New Safety Issues.Description of Changes or Additions Also Encl)
• ML20090G708  + (Forwards Rev 4 to Updated Fsar.Revised Figures Listed)
• ML20203E953  + (Forwards Rev 4 to Updated SAR for Davis-Besse Nuclear Power Station,Unit 1.Rev Reflects Mods Implemented Between 850122 & 860122 & Corrects Discrepancies.Program for Equipment Qualification Being Upgraded)
• LIC-89-1026, Forwards Rev 4 to Updated SAR for Fort Calhoun Station. Update Incorporates Changes Re Clarification of Engineered Safeguards Sys  + (Forwards Rev 4 to Updated SAR for Fort Calhoun Station. Update Incorporates Changes Re Clarification of Engineered Safeguards Sys)
• ML20112B545  + (Forwards Rev 4 to Util Generating Station Emergency Plan. Related Correspondence)
• ML20199C241  + (Forwards Rev 4 to Util SER 15737-2-G07-109, TMI-2 Div SER for Core Stratification Sample Acquisition. Rev Clarifies Restrictions Re Limitations Associated W/Drilling Through Flow Distributor.Fee Paid)
• ML20129H645  + (Forwards Rev 4 to Util Salt Deposition Monitoring Program, Per 850603 Request.Rev Will Be Incorporated Into Full Power Licenses When Issued.Related Correspondence)
• ML20107K536  + (Forwards Rev 4 to Util Security & Contingency Plan)
• ML20214D434  + (Forwards Rev 4 to Vogtle Environ Qualification Rept, Clarifying Mechanical Equipment Qualification Section Re Scope of Mechanical Equipment,Per SER Open Item 1.Summary of Mechanical Equipment Qualification Submitted in Ltr GN-1179)
• TXX-6540, Forwards Rev 4 to Vols 1 & 2 of Comanche Peak Response Team Program Plan & Issue Specific Action Plans. Rev Consists of Two Formats,Including Revised Plan & Apps & Forewords to Plan & App a  + (Forwards Rev 4 to Vols 1 & 2 of Comanche Peak Response Team Program Plan & Issue Specific Action Plans. Rev Consists of Two Formats,Including Revised Plan & Apps & Forewords to Plan & App a)
• NSD-NRC-98-5527, Forwards Rev 4 to WCAP-12600, AP600 QA Program Plan, Which Has Been Updated to Reflect Current Project Position on QA Requirements for Sys,Structures & Components to Which Regulatory Treatment on non-safety Sys Criteria Apply  + (Forwards Rev 4 to WCAP-12600, AP600 QA Program Plan, Which Has Been Updated to Reflect Current Project Position on QA Requirements for Sys,Structures & Components to Which Regulatory Treatment on non-safety Sys Criteria Apply)
• ML20079G710  + (Forwards Rev 4 to WVDP-043, Oil,Hazardous Substances & Hazardous Wastes Spill Prevention,Control & Countermeasures Plan)
• ML20087N606  + (Forwards Rev 4 to Westinghouse STS,marked-up to Reflect Proposed Facility Tech Specs)
• ML17199F596  + (Forwards Rev 4 to, 180-Day Rept in Response to IE Bulletin 80-11 for Dresden Nuclear Power Station Units 2 & 3. Rept Prepared in Sept 1984 But Not Submitted)
• ML17199F597  + (Forwards Rev 4 to, 180-Day Rept in Response to IE Bulletin 80-11 for Dresden Nuclear Power Station Units 2 & 3. Rept Prepared in Sept 1984 But Not Submitted)
• ML20150F204  + (Forwards Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations)
• ML20091A542  + (Forwards Rev 4 to, Millstone Unit 2,Cycle 11 Core Operating Limits Rept. Rept Revised to Change Total Integrated Radial Peaking Factor Limit)
• ML17299B303  + (Forwards Rev 4 to, Weld Failure on Palo Verde Nuclear Generating Station Unit 1 Pipe Support Structure, Per 860530 Telcon Request for Clarification)
• ML17299B304  + (Forwards Rev 4 to, Weld Failure on Palo Verde Nuclear Generating Station Unit 1 Pipe Support Structure, Per 860530 Telcon Request for Clarification)
• 3F1287-05, Forwards Rev 4,Suppl 18 to Modified Amended Security Plan W/ Evaluation of Changes.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 4,Suppl 18 to Modified Amended Security Plan W/ Evaluation of Changes.Rev Withheld (Ref 10CFR73.21))