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Category:ARCHIVE RECORDS
MONTHYEARML20154H9871998-08-28028 August 1998 Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release ML20154P8941998-05-13013 May 1998 Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas ML20217N7191998-03-28028 March 1998 Rev 0 to Calculation 50097.05, Borated Water Storage Tank Seismic Fragility ML20217N7121998-03-28028 March 1998 Rev 0 to Calculation 50097.05, Condensate Water Storage Tank Seismic Fragility ML20217E1661998-03-18018 March 1998 Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust ML20217E1971998-03-17017 March 1998 Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening ML20217E1171998-03-17017 March 1998 Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability ML20217F9501997-07-24024 July 1997 Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers ML20133F6511997-01-14014 January 1997 Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel ML20134M2121996-11-22022 November 1996 Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants ML20148T7361996-11-0808 November 1996 Rev 0 to Calculation 6612-96-030, RMS Levels Corresponding to NUMARC Eals ML20148T7511996-11-0606 November 1996 Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level ML20134D5471996-10-28028 October 1996 Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened ML20128Q3321996-10-18018 October 1996 Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants ML20129E9941996-10-10010 October 1996 Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity ML20148T6971996-09-11011 September 1996 Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs ML20148T6801996-09-0606 September 1996 Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level ML20217N6311994-08-0909 August 1994 Rev 0 to Calculation 42107.07-C-004, TMI Ipeee:Nuclear Svc Water Heat Exchanger Seismic Fragility ML20217N6601994-08-0505 August 1994 Rev 0 to Calculation 42107.07-C-009, TMI IPEEE:480V Load Ctr (Switchgear & Transformer) Svc Fragility ML20148F0251994-02-0808 February 1994 Rev 0 to Condensate Storage Tank B ML20148F0081994-02-0808 February 1994 Rev 0 to Condensate Storage Tank a ML20148F0321993-12-0808 December 1993 Rev 0 to Bwst ML20148F1331993-09-30030 September 1993 Rev 0 to Make-Up Tank ML20058P1681993-09-27027 September 1993 Package Consisting of Attachment to Employee Concerns Programs ML20148F1601993-09-27027 September 1993 Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways ML20148F0541993-09-17017 September 1993 Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A ML20057B9641993-09-10010 September 1993 AX114 & AX115 Ci Loading ML20148F1451993-09-0101 September 1993 Rev 0 to Nuc Serv Closed Cooling Water Surge Tank ML20057C0201993-09-0101 September 1993 Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20148F1221993-08-31031 August 1993 Rev 0 to Intermediate Closed Cooling Chem Mix Tank ML20057C0191993-08-31031 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20148F1521993-08-31031 August 1993 Rev 0 to Nuc Svc Cool Chem Mix Tank ML20148F1071993-08-31031 August 1993 Rev 0 to Intermediate Colsed Cooling Surge Tank ML20057C0211993-08-30030 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20057B9581993-08-27027 August 1993 FH109/FH300 Ci Estimate ML20057C0161993-08-26026 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20126M2391992-07-13013 July 1992 Package of Documents,Including Index of Briefing Papers & Actual Papers Re License Renewal,Design Certification Process,Below Regulatory Concern & Resident Inspector Program ML20196K6431991-07-20020 July 1991 Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis ML20034C9851990-04-0202 April 1990 Safety & Performance Improvement Program Implementation Audit Rept,Tmi Unit 1 ML20006A3071989-10-0606 October 1989 Event Notification 16785:on 890925,two Contract Employees Performing Decontamination Work at Plant Held Contaminated Nut from Decon Grating for 4-10 S.Licensee Notified DOE at Inel to Determine Radioactive Exposure of Subj Employees ML20042D5291989-10-0404 October 1989 Package of Director Highlights for TMI-1 & TMI-2,GPU News Releases & Undated Critique Re Potential Extremity Dose Exceeding Federal Limits ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20213A0411987-01-29029 January 1987 Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island IA-86-608, Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island1987-01-29029 January 1987 Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island IA-86-293, Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response1986-10-0909 October 1986 Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response ML20215L2161986-10-0909 October 1986 Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response ML20154M5021985-05-23023 May 1985 Notation Vote Response Sheet Approving SECY-85-153,providing Info to Advisory Panel on TMI-2 Cleanup ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20126B8311984-12-11011 December 1984 Supporting Documentation Re once-through Steam Generators ML20135H3531984-06-19019 June 1984 Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2 1998-08-28
[Table view] Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20154H9871998-08-28028 August 1998 Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release ML20154P8941998-05-13013 May 1998 Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas ML20217N7121998-03-28028 March 1998 Rev 0 to Calculation 50097.05, Condensate Water Storage Tank Seismic Fragility ML20217N7191998-03-28028 March 1998 Rev 0 to Calculation 50097.05, Borated Water Storage Tank Seismic Fragility ML20217E1661998-03-18018 March 1998 Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust ML20217E1171998-03-17017 March 1998 Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability ML20217E1971998-03-17017 March 1998 Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening ML20217F9501997-07-24024 July 1997 Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers ML20148T7361996-11-0808 November 1996 Rev 0 to Calculation 6612-96-030, RMS Levels Corresponding to NUMARC Eals ML20148T7511996-11-0606 November 1996 Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level ML20129E9941996-10-10010 October 1996 Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity ML20148T6971996-09-11011 September 1996 Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs ML20148T6801996-09-0606 September 1996 Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level ML20217N6311994-08-0909 August 1994 Rev 0 to Calculation 42107.07-C-004, TMI Ipeee:Nuclear Svc Water Heat Exchanger Seismic Fragility ML20217N6601994-08-0505 August 1994 Rev 0 to Calculation 42107.07-C-009, TMI IPEEE:480V Load Ctr (Switchgear & Transformer) Svc Fragility ML20148F0251994-02-0808 February 1994 Rev 0 to Condensate Storage Tank B ML20148F0081994-02-0808 February 1994 Rev 0 to Condensate Storage Tank a ML20148F0321993-12-0808 December 1993 Rev 0 to Bwst ML20148F1331993-09-30030 September 1993 Rev 0 to Make-Up Tank ML20148F1601993-09-27027 September 1993 Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways ML20148F0541993-09-17017 September 1993 Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A ML20057B9641993-09-10010 September 1993 AX114 & AX115 Ci Loading ML20148F1451993-09-0101 September 1993 Rev 0 to Nuc Serv Closed Cooling Water Surge Tank ML20148F1071993-08-31031 August 1993 Rev 0 to Intermediate Colsed Cooling Surge Tank ML20148F1221993-08-31031 August 1993 Rev 0 to Intermediate Closed Cooling Chem Mix Tank ML20148F1521993-08-31031 August 1993 Rev 0 to Nuc Svc Cool Chem Mix Tank ML20057B9581993-08-27027 August 1993 FH109/FH300 Ci Estimate ML20196K6431991-07-20020 July 1991 Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis ML20024B5861982-09-15015 September 1982 General Calculations ML20024B5871982-09-15015 September 1982 Verification Analysis Calculation ML20024B5721980-05-0505 May 1980 General Calculations from 205FA Small Break Evaluation Program ML20024B4691979-12-0505 December 1979 General Calculations:Task 27 Sys Analysis of TMI-2 790328 Accident ML19224A7821979-05-25025 May 1979 Meteorology Dose Calculations ML19221A3921979-05-21021 May 1979 Calculations Re Solubility of Gas in Primary Sys ML19221A5901979-05-21021 May 1979 Task 108:Particle Bed Investigation ML19224B3651979-05-19019 May 1979 Radwaste Disposal Leakage Recovery Sys Analysis ML19220C9271979-05-14014 May 1979 Hydrogen Bubble Analysis ML19220C9381979-05-14014 May 1979 Xenon Vol Calculations ML19220C8881979-05-14014 May 1979 Miscellaneous Data on Reactor Core ML19220D0351979-05-14014 May 1979 Estimates Released Source Term for TMI ML19220C8921979-05-14014 May 1979 Calculations Re Dose Consequences ML19289F8241979-05-0404 May 1979 Special Sample Log Re Condensate Storage Tank Activity ML19221A2811979-04-27027 April 1979 Water Scheduled to Be Processed Through EPICOR-II as of 4am, 790427 ML19221A2781979-04-27027 April 1979 Water Scheduled to Be Processed Through EPICOR-2 (Augmented) ML19220D0391979-04-24024 April 1979 Debris Bed Calculations ML19221A6391979-04-21021 April 1979 Task 29:Natural Circulation,Degraded Core Geometry, Calculation of Temp ML19224B3031979-04-21021 April 1979 Forwards Computer Listing of Reactimeter Patch Data.W/O Encl ML19221A6411979-04-20020 April 1979 Task 23:Examine High Counting Rate of BF3 Neutron Detector ML19221A2801979-04-19019 April 1979 Submits Water Scheduled to Be Processed Through EPICOR-1 as of 6:30 Am 790419 ML19221A3041979-04-18018 April 1979 Discusses Impact of Incident on Future of Nuclear Power. Environ & Economic Costs & Loss of Public Confidence in Safety of Nuclear Plants Pose Largest Threat 1998-08-28
[Table view] |
Text
. . . . .. - .. -- - .. - . .. - .
05-15-97,08:25:52 1 GPU NUCLEAR B/A No. 128108 W/O No. 95-552A-52108 SEISMIC QUALIFICATION No. SQ - T1 - T e -T g og g REVISION 0 4
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VENDOR CATALOG / DATA /tNSTRUCTON MANUAL .,_ i s
INSTALLATON SPECIFICATON ,, ,,,,
SEISMC ANALYSIS / TEST REPORTS /CALCS ,,,,,,, ,,_
f CONCRETE OR PAD DRAWINGS, SPECS, BLOCX WAtis EMBEDDED STEEL DRAWINGS _
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- DISPOSITION NEED MORE DATA J KNOWN OUT1.lER SEISMC DATA ACCEPTABLE. CONFLMATON WALKDOWN ONLY ANCHORAGE CALCULATIONS: _ EXIST _ PERFORM IN FELD COMMENTS NOT /A .56L u G- b P F# 8 A5 C -
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Seismic Capacity Engkwer (SCE) sumwe use mwise akte for COMMENTS.
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05-15-97*08:25:52 Status Y N U <
SCREENING EVALUATION WORK SHEET (SEWS) Sheet 1 of 2 Equip. ID No. IC-T-0001 Equip. Class 21 - Tanks and Heat Exchangers Equipment Description ICCW SURGE TANK _
Location: Bldg. FHB Floor El. 348 Room, Row / Col E OF TANK NS-T-1 Manufacturer, Model, Etc. (optional) -
404 9 A /- 93 , A Me s .a?, 2 9,2 9, so,31 SHELL CAPACITY VS DEMAND Buckling capacity of shell of large, flat-bottom, vertical tank is equal to or greater than demand: Y N U i
ANCHOR BOLTS AND EMBEDMENT .
I Capacity of anchor bolts and their embedments is equal )
to or greater than demand: Y N U N/A 6ee. hh0M& O - . -
CONNECTION BETWEEN ANCHOR BOLTS AND SHELL I Capacity of connections between the anchor bolts and the tank shell is equal to or greater than the demand: Y N U N/A j; S ee bhde~ls b W(J Y f
' Il FLEXIBILITY OF ATTACHED PIPING I Attached piping has adequate flexibility to accommodate I motion of large, flat-bottom, vertical tank: Y N U TANK FOUNDATION Ring-type foundation is not used to support large,
- flat-bottom, vertical tank: Y N U /A IS EQUIPMENT SEISMICALLY ADE0VATE? Y N U 4
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