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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
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
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
ML20148F1521993-08-31031 August 1993
Rev 0 to Nuc Svc Cool Chem Mix Tank
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
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
ML20151M9601987-07-20020 July 1987
Package of NRC Administered Requalification Exam Results Summary
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
ML20213A0411987-01-29029 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
ML20024B4941983-07-0606 July 1983
Slide Presentation Entitled Control Room Indications.
ML20078B6461983-04-0505 April 1983
Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to Svc
ML20083N6661982-10-19019 October 1982
TMI-1 Once-Through Steam Generator Repair Process Update & Return to Svc Overview
ML20082R1511982-09-15015 September 1982
Slide Presentation Entitled, TMI-1 Once-Through Steam Generator Repair Process Description/Qualification
ML20083N6581982-08-0404 August 1982
Informal Technical Communication Re 820721 Meeting in Livingston,Nj Concerning Schedule for Qualification Program of Tube Repair & Results of Preliminary Tests.Ornl 820817 Memo Re 820808-09 Meeting & Summary of 820915 Meeting Encl
ML20054K0801982-06-10010 June 1982
Request for OMB Review & Supporting Statement Re Psychological Stress of TMI-1 Restart on Residents Living in General Vicinity.Estimated Respondent Burden Is 853-h
ML20071J0471982-04-0707 April 1982
Slide Presentation Entitledd Gpu Nuclear TMI-1 Once-Through Steam Generator Status Review
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
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
ML20148F0081994-02-0808 February 1994
Rev 0 to Condensate Storage Tank a
ML20148F0251994-02-0808 February 1994
Rev 0 to Condensate Storage Tank B
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
ML20136B1461979-04-0303 April 1979
Calculations Made for Hydrogen Bubble in Reactor Vessel
ML20136A9851979-03-30030 March 1979
Hydrogen Burn Vessel Explosion Possibility Calculations
ML20136B1421979-03-30030 March 1979
Calculations Re Containment Hydrogen Bubble
ML20125D8981978-08-31031 August 1978
Calculation Data Re Davis-Besse 1 Pressurizer Levels During Reactor Trips
ML20076J8441977-08-14014 August 1977
Graph of Reactivity Worths at 532 F & 2155 Psig
1998-08-28
[Table view] |
Text
'
d5-159I08:27:28 GPU NUCLEAR B/A No. 128108 W/O No. 95-552A-52108
'l SEISMIC QUALIFICATION No. SQ - T1 *E c -T- O CO '2-REVISIO O I
COMPONENT 2 O~ I* d# 82- ~~
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SQW' DATA FILE INDEX COMPONENT TAG NUMBER 1 C' D # V DESC7uPTON lV1bX bWO(A-W O M Eb C o n/W4- QV4A A IX Q,vg
- DOCUMENTS NUMBERS / STATUS SEWS /
GMS 2 (TECHNICAL FUNCTONS DATA SURVEY) p (, s #69 PHYSICAL DRAWING / ASSEMBLY DRAMNG (4I'lBo) _
/
VENDOR CATALOG / DATA /INSTRUOTON MANUAL INSTA11ATON SPECIFICATON
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SEISMIC ANALYSIS / TEST REPORTS /CALCS CONORETE OR PAD DMWIN35. SPECS. BLOCK WALLS EMEEDDED STEEL DRAWtNGS ANCHORAGE DRAWING /DETAjLS/A[g3 (-h8-34 p/
FIELD CHANGE DOCS /MNOR'S OTHEA N ~ l N ~ # 1 ~ O r /
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- GENERIC ISSUES POTENTIAL O'JTUEA
_ BASE PLATE PLUG WELDS OTHERS
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- DISPOSITION NEED MORE DATA KNOWN OUTUER SEfSM:C DATA AOCE7' TABLE. CONF 4MATON WALKCOWN ONLY ANOHORAGE CALCULATONS: _ EXIST _ PERFORM IN FIELD COMMENTS b37 E*a r t ' 7)' ~
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051,is-97'08:27:28 Status Y N U SCREENING EVALUATION WORK SHEET (SEWS) Sheet 1 of 2
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Equip. ID No. IC-T-0002 Equip'. Class 21 - Tanks and Heat Exchangers Equipment Description ICCW CHEM MIX TANK Location: Bldg. AB Floor El. 305 Room, Row / Col 10'S OF IC-P-1B Manufacturer, Model, Etc. (optional)
AAfh & 3 2r-n , pense as rs og SHELL CAPACITY VS DEMAND l
' Buckling capacity of shell of large, flat-bottom, vertical tank is equal to or greater than demand:
Y N U@
I 1
l ANCHOR BOLTS AND EMBEDMENT
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Capacity of anchor bolts and their embedments is equal i to or greater than demand:
co n ,,, u r No . I i3 g i+1 we w M r A
$N U'N/A il
- l l CONNECTION BEIWEEN ANCHOR BOLTS AND SHELL Capacity of connections between the anchor bolts and [
the tank shell is equal to or greater than the demand: hN U N/A ;
com wr No . /
r
! FLEXIBillTY OF ATTACHED PIPING Attached piping has adequat.e flexibility to accommodate trotion of large, flat-bottom, vertical tank: ,
Y N U@
TANK FOUNDATION 1
Ring-type foundation is not used to support large, -
flat-bottom, vertical tank:
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SCREENING EVALUATION WORK SHEET (SEWS) Sheet 2 of 2 s i Equip. ID No. IC-T-0002 Equip. Class 21 - Tanks and Heat Exchangers Equipment Description ICCW CHEM MIX TANK COMMENTS
/. THE /t Gritod STEEL TA r./st; /$ 34tet*twirro By 7320 /h/ErfoNrM
/si pg ct A"P1 N Ho t a Asc CP/1ccA jne r tes t t Y, /g " Aone r. ygg ,pi[c Cin /s Att Ca/ess rse /M, 7*H; /,07, sc g ,s r Vc,r y ir A-c AjAtL ,ey 5/$ rarc c BAeJ D fv'<W 5anof 7 Lac /'rsoa) 8.1ftDfD rs? THE As e E Cd A' 4*
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