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DD-87-20, Informs That Time Provided by NRC Regulations within Which Commission May Act to Review Directors Decision (DD-87-20) Expired.Commission Declined Review.Decision Became Final Agency Action on 880107.Served on 880114
ST-HL-AE-1124, Final Deficiency Rept Re Potential Superheated Steam Conditions Following Main Steam Line Break Outside Containment.Initially Reported on 840809.Deficiency Not Reportable Per 10CFR50.55(e)
ST-HL-AE-7332, Informs That Full Resumption of ASME safety-related Welding & Preparations for safety-related Complex Concrete Pours on Regular Production Basis Will Be Initiated 811005
ST-HL-AE-1120, Forwards Rev 17 to QA Program Description for Design & Const Phase & Rev 8 to ETR-1001, Nuclear QA Program Manual, Per 10CFR50.55(f)(3)
IA-87-467, Submits Daily Highlight.On 870601,GAP Submitted Motion & Petition Requesting Commission to Quash NRC Subpoena to Bp Garde & Opportunity for Oral Argument.Establishment of Review Team to Investigate Plant Allegations Requested
ST-HL-AE-1103, Final Deficiency Rept Re Flood Protection for Fireproof Doors.Main Cooling Reservoir Will Not Fail Under Any Credible Dbe.Fsar Section 3.4 Will Be Revised.Item Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1104, Final Part 21 Rept Re Comsip,Inc Std Bed Catalyst in Containment Gas Sys Life.Initially Reported on 840516.Beds Being Replaced W/New Beds Meeting Performance Specs
ST-HL-AE-1107, Responds to Request for Addl Info Re 840105 Response to Notices of Violation & Deviation Contained in Insp Repts 50-498/83-20 & 50-499/83-20.Corrective Actions:Program Reconciling Anchor Bolt/Embed Evaluation Records Initiated
ST-HL-AE-1152, Responds to IE Bulletin 84-03 Re Potential for Refueling Cavity Water Seal Failure.Concerns of Bulletin Have No Impact on Project Since Permanent Metal Seal Provided at Annulus to Connect Vessel Flange to Stainless Steel Liner
ST-HL-AE-1146, Forwards Rev 8 to QA Program Description During Design & Const & Rev 9 to Nuclear QA Program Manual
ST-HL-AE-1155, Forwards Current Schedule for Harsh Environ Equipment Qualification Testing,Per 840609 Meeting.Related Correspondence
ST-HL-AE-1138, Forwards Followup Phase II Anchor Bolt Program.Rept Closes Out Activities 4,5 & 7.Related Correspondence
ST-HL-AE-1143, Forwards Proprietary & Nonproprietary Westinghouse 17x17 Xl Hydraulic Flow Testing Results,In Response to NRC Question 231.8.Application for Withholding Proprietary Info (Ref 10CFR2.790) Encl
ST-HL-AE-1140, Revised Final Deficiency Rept Re Design of RHR Sys.Initially Reported on 820326.Re-evaluation Demonstrates That Use of Atmospheric Head Tank Inside of Reactor Containment Bldg Better Design Solution.Revised Design Drawing Encl
ST-HL-AE-1150, Interim Deficiency Rept Re Trapeze Type Support Assemblies. Initially Reported on 841022.Pipe Support Designs Will Be Reviewed to Identify Number of Supports Subj to Deficiency. Personnel Given Addl Training.Next Rept by 850322
ST-HL-AE-1151, Fourth Interim Deficiency Rept Re Corrosion in Safety Injection Sys Weld.Initially Reported on 831020.Welds & Piping Matls Replaced Where Evidence of Corrosion Found.Next Rept Will Be Submitted by 850331
ST-HL-AE-1144, Forwards Amend 41 to FSAR for South Texas Project Units 1 & 2
ST-HL-AE-1145, Final Deficiency Rept Re Defective Rosemount Pressure Transmitters.Initially Reported on 841003.Affected Transmitters Returned to Rosemount for Repair.Item Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1126, Notifies That Revised Fire Hazards Analysis Rept Will Be Submitted by 850201.Meeting W/Nrc on or About 840927 Requested to Discuss Implementation Approach
ST-HL-AE-1114, Responds to IE Bulletin 84-02 Re Failure of Nylon or Lexan-type GE Hfa Relays.No Subj Relays in Use in safety- Related Applications.Any Required Actions Will Be Completed by Mar 1986
ST-HL-AE-1122, Final Deficiency Rept DER 84-016 Re ASTM A-194 Grade 2H & ASTM A563 Grade a Nuts.Initially Reported on 840713.ASTM A563 Grade a Std Hex Nuts Will Be Purged from Site.Item Considered Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1115, Opposes Requirement Re Designing for Arbitrary Intermediate Breaks.Approval for Listed Alternative Pipe Break Criteria Requested,Excluding RCS Primary Loop.Addl Info Supporting Request Encl
ST-HL-AE-1110, Forwards Refinements & Changes to 840221 Response to Notice of Violation in Insp Rept 83-22 Re Improvements to Matl Control Program.Current Program Provides Adequate Control of safety-related Matls
ST-HL-AE-1121, Third Interim Deficiency Rept Re Corrosion in Safety Injection Sys Pipe Weld.Initially Reported on 831020.Next Rept Will Be Submitted by 841116
ST-HL-AE-1119, Forwards Draft in Furtherance Certificate Re Issuance of Pollution Control Revenue Bonds,For Review.Necessary Mods & Signed Certificate Requested by 840915
ST-HL-AE-1077, Forwards Rev 6 to QA Program Description for Design & Const Phase of Facilities.Changes Clarify Definition of Bechtel Div Quality Policies & Defines Responsibilities for Trend Analysis
ST-HL-AE-1019, Forwards Rev 5 to QA Program Description for Design & Const Phases.Includes Revs to Bechtel & Ebasco Programs
ST-HL-AE-1109, Responds to NRC Re Violations Noted in IE Insp Repts 50-498/84-04 & 50-499/84-04.Corrective Actions:Site Std for Nonconformance Reporting Revised
ST-HL-AE-1118, Final Deficiency Rept Re Rear Brackets for Snubbers Supplied by Nuclear Power Svcs.Initially Reported on 840706.B Rear Brackets Will Be Replaced within 6 Months
ST-HL-AE-1096, Requests Exemption from 10CFR50,App A,Gdc 4 Re Elimination of Postulated Circumferential & Longitudinal Breaks in RCS Main Loop Piping & WCAP-10559 & WCAP-10560.Repts Withheld (Ref 10CFR2.790)
ST-HL-AE-1064, Responds to NRC Re Violations Noted in Insp Repts 50-498/83-24 & 50-499/83-24.Corrective Actions:Pittsburgh Testing Lab Redirected to Perform Future Density Testing in Strict Conformance W/Astm D2049-69
ST-HL-AE-1102, Forwards Amend 39 to South Texas Project,Units 1 & 2 FSAR, Incorporating Revised Response to NRC Questions & Miscellaneous FSAR Text Revs & Editorial Changes
ST-HL-AE-1136, Interim Deficiency Rept Re Safety Injection Sys Piping. Initially Reported on 791025.Bechtel Recommended Mods to Emergency Sump Recirculation Piping Design Encl.Guard Pipe & Anchor Outside Containment Eliminated
ST-HL-AE-1105, Forwards Comments on Weaknesses Noted in SALP Repts 50-498/83-26 & 50-499/83-26 for Dec 1982 - Nov 1983,as Discussed at 840510 Public Meeting
ST-HL-AE-1106, Responds to NRC Re Violations Noted in IE Insp Repts 50-498/84-07 & 50-499/84-07.Corrective Actions:Amend Recording Errors Corrected,Records Reviewed & Distribution Matrices Reviewed Against Station Files
ST-HL-AE-1131, Suppl to Final Part 21 & Deficiency Rept Re Snubber Assembly Rear Brackets Provided by NPS Industries,Inc. Encl Correspondence & Memo from Bracket Manufacturer Indicates Item Reportable Per Part 21
ST-HL-AE-1089, Final Deficiency Rept DER 84-003 Re ESF Load Sequencer Logic Design.Initially Reported on 840224.Design Will Be Revised to Inhibit Closure of Feeder Breaker & to Eliminate Restrip of First Load
ST-HL-AE-1137, Clarifies Cost Allocation Methods Used for Cooling Water Reservoir Sys & Boron Recycle Sys Described in 840814 Submittal.Requests That Pollution Control Bond in Furtherance Certificate Be Issued by 841008
ST-HL-AE-1135, Second Interim Deficiency Rept Re Commingling of Round Rod Matls.Initially Reported on 840430.Problem Limited to Rod Matl Mfg During Period When Matl Control Identification Indicated by Color Coding & Ribbon Striping
ST-HL-AE-1108, Forwards Characterization of FSAR Changes Since Dec 1981,per 840612 Commitment.Documents That Have Been or Will Be Submitted for NRC Review Listed
ST-HL-AE-1091, Final Deficiency Rept Re Pumps Mfg by Hayward Tyler Pump Co. Initially Reported on 830216.No Specific Corrective Action Required to Resolve Deficiency.Util Will Be Testing Pumps Delineated in Response to IE Bulletin 83-05
ST-HL-AE-1098, Final Deficiency Rept Re Main Control Room Habitability - Hazardous Chemical Release.Initially Reported on 840302. Design Revised to Delete Function of Automatically Starting Makeup Intake Subsys Fans Following Loss of Offsite Power
ST-HL-AE-1087, Submits Final Response to IE Bulletin 83-06, Nonconforming Matls Supplied by Tube-Line Corp Facilities at Long Island City,Ny.Houston,Tx & Carol Stream,Il. No Subj Matls Utilized at Plant
ST-HL-AE-1099, Interim Deficiency Rept Re Commingling of Round Rod Matls. Initially Reported on 840430.Interim Measures Implemented to Define Previously Field Fabricated Components Susceptible to Matl Commingling.Next Rept Expected by 840928
ST-HL-AE-1093, Final Deficiency Rept Re Insufficient Procedures for Evaluation of Design Basis Flood.Initially Reported on 830830.Circulating Water Piping Will Be Modified by Exposing Concrete Chute at Embankment Crest
ST-HL-AE-1043, Responds to NRC Re Violations & Deviations Noted in IE Insp Repts 50-498/83-20 & 50-499/83-20.Corrective Actions:Bechtel Energy Corp Anchor Bolt/Embed Evaluation Program Will Assure Bolts & Embeds Meet Requirements
ST-HL-AE-1084, Suppl to Final Deficiency Rept Re Faulted Condition Heat Loads in Design of Portions of HVAC Sys.Initially Reported on 810508.Containment Atmosphere Hydrogen Monitors Relocated Outside Control Room to Reduce Unnecessary Exposure
ST-HL-AE-1076, Documents Util Understanding of Items Discussed in 840301 Meeting in Houston,Tx Re Engineering Assurance Program. Engineering Assurance Procedure Manual Encl
ST-HL-AE-1052, Confirms That Response to 840105 Notice of Violation Contained in IE Insp Repts 50-498/83-22 & 50-499/83-22 Will Be Submitted by 840221,per 840131 Telcon
ST-HL-AE-1070, Final Deficiency Rept Re Seepage of Oil from Cable Supplied by Okonite Industries.Exam Revealed No Oil Seepage Occurred. Condition Not Reportable Under 10CFR50.55(e).Item Closed
ST-HL-AE-1057, Final Deficiency Rept Re Reactor Containment Bldg post- Tensioning Sys Tendons.Initially Reported on 830826.Damaged Tendons Will Be Replaced.Tendons Will Be Mfg in Time Frame to Preclude Need for long-term Storage
ST-HL-AE-1063, Final Deficiency Rept Re Pipe Stress Analysis Design Process.Initially Reported on 831228.Evaluation Complete. Item Determined Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1017, Final Deficiency Rept Re Computer Program Verification. Initially Reported on 810508.Verification Program for Review & Acceptance of Brown & Root Computer Calculations Implemented
ST-HL-AE-1008, Supplemental Final Deficiency Rept Re Westinghouse Supplied Pressure & Level Transmitters.Transmitters Will Be Provided for Applications Described in ,Per Westinghouse Group B & WCAP-8587 Generic Qualifications
ST-HL-AE-1011, First Interim Deficiency Rept Re Design Basis Flood Calculations Not Considering Erosion Effects of Postulated Embankment Breach.Initially Reported on 830830.Next Rept Expected by 840120
ST-HL-AE-1004, Revised Final Deficiency Rept Re Essential Cooling Water Intake Structure Gantry Crane.Initially Reported on 790516. Crane Design Revised for Severe & Extreme Environ Loadings to Retain Structural Integrity
ST-HL-AE-1085, Final Deficiency Rept Re NSSS Model Used in Seismic Analyses.Initially Reported on 830727.STP Design Basis Seismic Response Spectra Revised to Incorporate New Spectra at NSSS Support & Nozzle Attachment Points
ST-HL-AE-1074, Forwards Amend 38 to Fsar.Amend Revises FSAR to Incorporate General Update to Sections 2.3,2.5,3.10-12,5.4,6.2,4-5 & App 7A,rev to Chapter 13,revised Responses to NRC Questions & Text Revs & Editorial Changes.Affidavit Encl
ST-HL-AE-1081, Second Interim Deficiency Rept Re Corrosion in Safety Injection Sys Weld.Initially Reported on 831020.Expert Retained to Determine Bacteria Source & Assist in Formulating Recurrence Control Program.Next Rept by 840810
ST-HL-AE-1078, Forwards Rev 2 to Security Personnel Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)
ST-HL-AE-1097, Responds to NRC Re Violations Noted in IE Insp Repts 50-498/84-02 & 50-499/84-02.Corrective Actions: Indication on Original Radiograph Caused by Rough Id Surface.Requests Violation Be Withdrawn
ST-HL-AE-1080, Forwards Final Rept Re Control Room Design Review,Addressing NRC Audit Comments
ST-HL-AE-1041, Final Deficiency Rept Re Installation of Cathodic Protection Devices on Stainless Steel Piping.Initially Reported on 831202.Affected Piping Will Be Cut & Replaced Per ASME Code & Weld Specs.Sys Installation Documents Will Be Revised
ST-HL-AE-1034, Forwards Response to Generic Ltr 83-10C Re TMI Action Item II.K.3.05, Automatic Trip of Reactor Coolant Pumps. Response to Item 1.2 Will Be Provided by 840515
ST-HL-AE-1039, Final Deficiency Rept Re Tight Seal on Target Rock Pilot Actuated Solenoid Valves.Initially Reported on 831118.Valves May Be Replaced or Supplemented.Item Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1040, Forwards Responses to NRC Questions Re Probabilistic Evaluations of Tornado & hurricane-generated Missile Hazards to Containment Isolation Valve Compartment Equipment
ST-HL-AE-1031, Forwards Response to Generic Ltr 81-07, Control of Heavy Loads. Deviations from Established Load Paths Will Require Written Alternatives Approved by Plant Safety Review Committee
ST-HL-AE-1035, Final Deficiency Rept DER-019 Re Potentially Overstressed Containment Mechanical Penetration Welds.Initially Reported on 831115.Penetration Assemblies Modified by Replacing Carbon Steel Plate W/Stainless Steel Plate
ST-HL-AE-1029, Supplemental Deficiency Rept Re Westinghouse Steam Generator Tube Rupture Analysis.Initially Reported on 820119.Design of Pressurizer PORV Changed to safety-grade,active,solenoid- Operated Valves Powered by Class IE Sources
ST-HL-AE-1032, Advises That Anchor Bolt/Embed Evaluation Program in Response to Violations Noted in IE Insp Repts 50-498/83-02 & 50-499/83-02 Will Be Completed by End of First Quarter 1984
ST-HL-AE-1028, Forwards Addl Info Re Isolation Valve Cubicle Roof Design, Per NRC Request.Addl Info Provided for Certain Questions Re 830913 Submittal
ST-HL-AE-1026, First Interim Deficiency Rept Re Corrosion in Safety Injection Sys Weld.Corrective Actions Will Be Established Upon Completion of Investigation to Determine Extent of Corrosion.Next Rept by 840420
ST-HL-AE-1025, Submits Proposed Schedule for Responding to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Equipment Classification & Vendor Interface Programs Will Be Completed by June 1985
ST-HL-AE-1022, Interim Deficiency Rept Re Anchor Bolt Defects. Presentation Documenting Specific Program & Schedule for Completion of Activities Required to Resolve Issue Encl. Final Rept Expected on 840401,per 830919 Meeting
ST-HL-AE-1014, Seventh Interim Deficiency Rept Re Nonconformances of Welds in vendor-fabricated Category I Structural Steel. Initially Reported on 810108.Review Continuing.Final Rept Will Be Submitted by 831230
ST-HL-AE-1055, Final Deficiency Rept Re Reactor Vessel Core Support Tolerance.Initially Reported on 830726.Evaluations Disclosed That out-of-levelness Condition on Reactor Vessel Support Ledge Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1056, Second Interim Deficiency Rept Re NSSS Model Used in Seismic Analysis.Initially Reported on 830727.Bechtel Computing Corresponding Response Spectra at Attachment Points within Reactor Coolant Loop.Next Rept Expected by 840427
ST-HL-AE-1007, Final Deficiency Rept Re Auxiliary Feedwater Sys Containment Isolation Valves.Initially Reported on 830822.Sys Design Modified to Require Performance Sys Function of safety-grade Active Valves.Also Reported Per Part 21
ST-HL-AE-1051, Forwards Amend 37 to Fsar,Incorporating General Update to FSAR Sections 12.1 & 12.2,revising Responses to NRC Question & Adding Miscellaneous FSAR Test Revs & Editorial Changes
ST-HL-AE-1006, First Interim Deficiency Rept Re Corrosion on Reactor Containment Bldg post-tensioning Sys Tendons.Initially Reported on 830826.Evaluation Underway to Determine If Condition Impairs Tendon Strength.Next Rept by 840229
ST-HL-AE-1001, Informs That Applicant Has Not Received NRC in-progress Audit Rept of Control Room Design Review (Crdr).Final Crdr Cannot Be Submitted Until at Least 9 Wks After Receipt of Audit.Rept Schedule Must Be Revised
ST-HL-AE-1044, Interim Deficiency Rept Re Failure of Auxiliary Feedwater Pump Wearing Rings.Initially Reported on 831227.Written Info from Bingham-Willamette Co Confirmed Failure as Isolated Incident.Item Not Reportable Per 10CFR50.55(e) or Part 21
ST-HL-AE-1049, First Interim Deficiency Rept Re Pipe Stress Analysis Design Process.Initially Reported on 831228.Evaluation of Concerns Listed in Engineering Assurance Program Design Assessment Review 83-3 Continuing.Next Rept by 840301
ST-HL-AE-1038, Eighth Interim Deficiency Rept Re Nonconforming Welds in Vendor Fabricated Category I Structural Steel.Initially Reported on 810108.Bechtel Will Provide Recommendations. Final Rept Anticipated by 840323
ST-HL-AE-1036, Forwards Amend 36 to Fsar,Consisting of Responses to NUREG- 0737,Item II.E.4.2,revised Responses to NRC Questions & Miscellaneous FSAR Test Revs & Editorial Changes
ST-HL-AE-1046, Second Interim Deficiency Rept Re Design Basis Flood. Initially Reported on 830830.Studies Initiated to Demonstrate Integrity of Main Cooling Reservoir Embankment. Final Rept Expected by 840525
ST-HL-AE-1045, Final Deficiency Rept Re Control & Issuance of Design Related Drawings.Initially Reported on 831216.Configuration Control Program Assures Compliance W/Technical Requirements. Item Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1018, Revises Response to IE Bulletin 80-05, Vacuum Condition Resulting in Damage to Chemical Vol Control Sys Holdup Tanks. Revised Sys Summary Table Encl
ST-HL-AE-1013, Forwards Amend 34 to Fsar,Updating Section 3.7 Re Seismic Design
ST-HL-AE-1015, Revises 830228 Response to Generic Ltr 83-01 Operator Licensing Exam Site Visit. Applications Will Be Submitted in Feb 1984 for 10 Persons Scheduled for Sept 1984 Instructor Certification Exam
ST-HL-AE-1003, Forwards Info Re Comparison of Alternatives for Isolation Valve Cubicle Roof Design & Probabilistic Evaluations of hurricane-generated & Tornado Missile Hazard to Containment Isolation Valve Compartment Equipment
ST-HL-AE-1050, Forwards Annotated Corrected Pages to June 1982 Const Status Repts Updating NUREG-0030 Through Fourth Quarter 1983
ST-HL-AE-1021, Forwards Corrected Pages from Oct 1982 Const Status Rept for Update of NUREG-0030 Through Third Quarter 1983.Dec 1982, Mar,June & Sept 1983 Repts Not Yet Received
NUREG-0780, Forwards Partial SER for South Tx Project
ST-HL-AE-1142, Final Deficiency Rept Re Incomplete Expansion of Steam Generator Tubes.Initially Reported on 840924.Tubes Will Be Reworked to Assure Each Tube Expanded for Full Depth of Tube Sheet.Item Not Reportable Per 10CFR50.55(e)
ST-HL-AE-1094, Final Deficiency Rept Re Weld Irregularities in shop-welded Structural Steel Fabricated by American Bridge.Initially Reported on 810108.More Stringent Insp & QA Programs at Vendor Site Resulted in Improved Weld Quality
ST-HL-AE-1059, Responds to IE Bulletin 83-08, Electrical Circuit Breakers W/Undervoltage Trip Feature in Use in Safety-Related Application Other than Reactor Trip Sys. No Circuit Breakers W/Undervoltage Trip Attachment Utilized