|
|---|
Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20217E0811998-03-24024 March 1998
Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident
ML20202D8491997-11-0606 November 1997
Rev 0 to Topical Rept 116, Leakage Assessment Methodology for TMI OTSG Kinetic Expansion Examination
ML17353A4341995-10-31031 October 1995
Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range.
ML17264A1181995-07-31031 July 1995
Response to Part (1) of GL 92-01,Rev 1,Suppl 1.
ML20084C9831995-05-0909 May 1995
Rev 0 TMI-1 Evaluation of Thermo-Lag Fire Barriers
ML20080R5251995-01-23023 January 1995
Steady State Reactor Physics Methodology for TMI-1
ML20081G2731995-01-0606 January 1995
TMI-1 Transient Analyses Using Retran Computer Code
ML20137J4021993-12-31031 December 1993
External Circumferential Crack Growth Analysis for B&W- Design Rv Head CR Drive Mechanism Nozzles
ML20067A5241990-12-31031 December 1990
Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.'
ML20247N5911989-05-18018 May 1989
Rev 2 to TMI-1 Cycle 7 Core Operating Limits Rept
ML20245L6351989-04-20020 April 1989
Rev 1 to TMI-1 Cycle 7 Core Operating Limits Rept
ML20236E0151987-06-30030 June 1987
Analysis of Capsule TMI1-C,...Vessel Matl Surveillance Program,Suppl 1 Pressure-Temp Limits
ML20237J6101987-04-30030 April 1987
TMI-1 Nuclear Power Plant Leak-Before-Break Evaluation of Margins Against Full Break for RCS Primary Piping
ML20137M8631986-01-31031 January 1986
Pressurized Thermal Shock Evaluations in Accordance W/10CFR50.61 for B&W Owners Group Reactor Pressure Vessels
ML20154H1491985-12-30030 December 1985
Rev 0 to Final Verification & Validation Rept on TMI-1 Spds
ML20151N7691985-12-19019 December 1985
Rev 0 to Comparison of Steam Generator Tube Plugging W/TMI-1 Design Basis
ML20135A5571985-08-31031 August 1985
B&W Owners Group Cavity Dosimetry Program
ML20138P1541985-07-0202 July 1985
Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation, Topical Rept
ML20126L2881985-07-0202 July 1985
Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation
ML20093K2961984-08-31031 August 1984
TMI-1 Reactor Coolant Pump Shaft Failure Analysis
ML20084F6761984-04-30030 April 1984
TMI Safety Parameter Display Sys Safety Analysis,Topical Rept 018
ML20077H8631983-03-29029 March 1983
Rev 2 to Topical Rept 008, Assessment of TMI-1 Plant Safety for Return to Svc After Steam Generator Repair
ML20072K7301983-02-28028 February 1983
Evaluation of Small Break LOCA Operating Procedures & Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating Nsss
ML20065T4331982-11-30030 November 1982
B&W Small Break LOCA ECCS Evaluation Model
ML20076J8591979-08-31031 August 1979
Integrated Control Sys Reliablilty Analysis
ML20027A7671979-08-0707 August 1979
Sys Response to Total Loss of Steam Generator Heat Sink.
ML20125D9021977-09-30030 September 1977
Decay Heat Removal Problems Associated W/Recovery from Very Small Break LOCA for B&W 205-Fuel Assembly Pwr
ML19332B2381977-07-31031 July 1977
to ECCS Analysis of B&W 177-Fuel Assembly-Loop Nss. Related Correspondence
ML19260A1221977-01-31031 January 1977
Analysis of Capsule TMI-1E from Met Ed TMI-1:Reactor Vessel Matls Surveillance Program, Jan 1977.Prepared for Met Ed
ML19337A4251972-05-31031 May 1972
Overpressure Protection for B&W Pwr. Related Correspondence
1998-05-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for TMI-1.With
ML20211H5111999-08-31031 August 1999
Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis
ML20211Q3551999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With
ML20210R4791999-08-13013 August 1999
Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2
ML20210U4791999-07-31031 July 1999
Monthly Operating Rept for July 1999 for TMI-1.With
ML20209G0011999-07-0909 July 1999
Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1
ML20210K7651999-07-0909 July 1999
Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca
ML20209H8251999-07-0101 July 1999
Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station
ML20209H1421999-06-30030 June 1999
Monthly Operating Rept for June 1999 for TMI-1.With
ML20195H0751999-06-0808 June 1999
Drill 9904, 1999 Biennial Exercise for Three Mile Island
ML20195H9261999-05-31031 May 1999
Monthly Operating Rept for May 1999 for TMI-1.With
ML20209G0351999-05-31031 May 1999
TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo)
ML20207B6621999-05-27027 May 1999
SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05
ML20206R0571999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With
ML20206D4201999-04-20020 April 1999
Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2
ML20209G0071999-03-31031 March 1999
Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion)
ML20205K6851999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With
ML20210C0161999-03-0101 March 1999
Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246
ML20207M8461999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for TMI-1.With
ML20196K3561999-01-22022 January 1999
Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits
ML20207A9291998-12-31031 December 1998
1998 Annual Rept for TMI-1 & TMI-2
ML20196G4661998-12-31031 December 1998
British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl
ML20196F6861998-12-0202 December 1998
Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection
ML20198B8641998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for TMI-1.With
ML20195C6921998-11-12012 November 1998
Safety Evaluation Supporting Amend 52 to License DPR-73
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20196B7191998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for TMI-1.With
ML20203G1211998-10-30030 October 1998
Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt
ML20155E7511998-10-15015 October 1998
Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing
ML20154L5541998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for TMI Unit 1.With
ML20153A9941998-09-16016 September 1998
Safety Evaluation Denying Request to Remove Missile Shields from Plant Design
ML20151U8821998-09-0808 September 1998
SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2
ML20151V2811998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With
ML20237A8331998-08-12012 August 1998
Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1
ML20237C6411998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Tmi,Unit 1
ML20236R2201998-06-30030 June 1998
Monthly Operating Rept for June 1998 for TMI-1
ML20236W9961998-06-0909 June 1998
1998 Quadrennial Simulator Certification Rept
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20249A1061998-05-31031 May 1998
Monthly Operating Rept for May 1998 for TMI-1
ML20247G0761998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1
ML20212A2191998-04-22022 April 1998
Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2
ML20248H6991998-04-0808 April 1998
Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris
ML20216K1061998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1
ML20217E0811998-03-24024 March 1998
Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident
ML20212E2291998-03-0404 March 1998
Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected
ML20216F0981998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1
ML20202F8121998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1
ML20199G8371998-01-22022 January 1998
SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1
ML20198N2901998-01-12012 January 1998
Form NIS-1 Owners' Data Rept for Isi
ML20199J3251997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1
1999-09-30
[Table view] |
Text
'
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TMI-I CONTROL ROOM HABITABILITY FOR MAXIMUM HYPOTHETICAL ACCIDENT !
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1 TOPICAL REPORT #121 REV.0 s,.
AUTHOR:
O Lah- p sluju Ardesar A trani DATE (Contributors: K.G. Boughton.P. A. Bennett. T.Y. Byoun. DJ. Distel. B A. Parfitt)
APPROVALS:
SECTION MANAGER DATE AR dA DEPARTMENTDIRECTOR
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.e Topical Report #121 Rev.O
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Page 25 cf 29 e
(*) Emergency Posanon AN AM'C354/I ATMOSPMERE
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- Topical Repon #121 Rev.O Page 26 of 29 FIGURE 3 North I Turbine Bldg ;
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Service i Bldg Control
'*Bldg Control Building Ventilation l exhausts at this location via Patlof AH.D37 3 eactor X f
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- o' t Topical R3 port #121 f Rev.O Page 27 of 29 FIGURE 4 - STARDOSE MODELS MODEL FOR TE1 CONTROL ROOM DOSE ANALYSIS . BASE CASE (NQ FALURES) 10 CFM 0 S/0 25 CFM esto CFM TO ENVIRONMENT I [ 9000CFM C 9 l 0402/007 90% FLTER t w s cFM CFM UNSPRAYED SPRAYED REGION 067 CFM _ , , ,
REGION 56000 (SPRYRG) .
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AUXLIARY & FUEL CONTROL 90 %
HANOLWG SLDO BW5T SUILDING rlLygg (ESFAm) EphELOPE CORE 04/02l001 CFM J
MODEL FOR TE1 CONTROL ROOM DOSE ANALYSIS CASE 1 (AH 0-28 FAILURE) 10 CFM 0 54 25 CFM 110104010 CFM 11000S000 CFM 5 70 ENVIRONMENT ( ,
g I g '
0442/007 90% FILTER 1 M SCFM l CFM UNSPRMED SPRAYED REGION 10 067CFM _
REGION 56000 (SPRYRG)
(UNSPRYRG) CFM 90% 7LTER 90% FLTER " !'
b # m 30000 CF4 '
T T, AUXLIARY & FUEL CONTROL 90 %
HANDLING 8LDG BWST BUILDING r lLTER CORE iESFAiR) ENVELOPE D 40 2/0 01
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_ _ _ _ _ . _ _ _ _ . _ . _ _ _ . _ . _ _ _ _ _ . . _ _ _ . _ _ _ _ . _ _ _ . . _ . _ _ _ _ _ _ _ _ . __.___m.___ ___.________________________a__ _
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Topied R port #121 i Rev.0 l Page 28 of 29 ;
i FIGURE 4 - STARDOSE MODELS (continued) i I
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MODEL FOR 7851 CONTROL Ro0M DOSE ANALYsas . CASE 2 (AH4-37/3s FA8 LURE) l i
I l' io CFM 0 2 2$CFM 4010m10 CFM l
- [ 4000reeC0CFM l i TO EWIRONMENT ( ,
I 0 de0 M 07 90% FILTER i
$ a t run 4 cru l CFM l .
j UNSPRAYED SPRAYED REGION _1067 CFM , , _
i REGION $8 000 ($PRYRG) % '
l (UNSPRYRG) .A , w 9n% FLTER 90% FILTEf l l tr # ._
se 'A CFM T T AUXILIARY & FUEL CONTROL 90 %
l l , HANDLING BLOG SW$7 8UILDING FILTER l .' CORg (ESFe R) ENVELOPE 3 M M 0i CFM
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Topical RCport #121 Rev.O Page 29 pf 29 Figure 5 - TMi 1 Control Room Habitability Analysis (Source-ReceptorConfQuration)
(OT80p *112 METERS) ic~ <wa v.<>
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