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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211H5111999-08-31031 August 1999
Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis
ML20210R4791999-08-13013 August 1999
Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2
ML20210K7651999-07-0909 July 1999
Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca
ML20209G0071999-03-31031 March 1999
Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion)
ML20236W9961998-06-0909 June 1998
1998 Quadrennial Simulator Certification Rept
ML20210P4461997-08-31031 August 1997
Update 2 to TMI-2 Post-Defueling Monitored Storage Sar
ML20210T3411997-08-31031 August 1997
Rev 0 to TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis
ML20199E5841997-08-18018 August 1997
Limited Liability Company Agreement of Amergen Energy Co, LLC Among PECO Energy Co,British Energy PLC & British Energy,Inc
ML20133D8771996-12-23023 December 1996
Rev 2 to TMI-1 Evaluation of Thermo-Lag Fire Barriers
ML20137F1301996-08-27027 August 1996
Rev 0 to Auxiliary Bldg Sump Sludge Prevention (Regulatory Required)
ML20117H6621996-07-20020 July 1996
Rev 1 to TR 094 TMI-1 Evaluation of Thermo-Lag Fire Barriers
ML20129G9291996-06-17017 June 1996
TMI-1 Reload Design & Setpoint Methodology
ML20148F0831996-04-0202 April 1996
Rev 0 to EDG 1B Air Start 2 Reservoir Tank
ML20148F0611996-04-0202 April 1996
Rev 0 to SQ-TI-EG-T-0001B-1, EDG 1B Air Start 1 Reservior
ML20098B1291995-09-19019 September 1995
Rev 1 to Pages 3 & 30 of TMI-1 USI A-46 Seismic Evaluation Rept
ML20100L6581995-05-25025 May 1995
Div 1/2 Mod Design Description for New TMI-1 Radwaste Demineralizer Sys Three Mile Island Unit 1,Nuclear Generating Station, Rev 2
ML20087J5281995-05-11011 May 1995
Nonproprietary Page 2 of TMI Unit 1 USI A-46 Seismic Evaluation Rept
ML20082G4191995-03-22022 March 1995
Rev 0 to Topical Rept 093, TMI-1 Reactor Bldg Twenty Yr Tendon Surveillance (Insp Period 6)
ML20082Q8051995-03-10010 March 1995
TMI-1 Core Thermal-Hydraulic Methodology Using VIPRE-01 Computer Code
ML20082G4441995-02-22022 February 1995
Vols I & II 20th Yr Physical Surveillance of TMI-1 Containment Bldg
ML20079B0911994-12-16016 December 1994
TMI-1 IPE for External Events
ML20100L6321994-08-0303 August 1994
Shipment of Miscellaneous Waste Evaporator Concentrates
ML20059M2181993-11-30030 November 1993
Amend 19 to Pdms Sar
ML20148F1011993-10-28028 October 1993
Rev 0 to Air Accumulator for FW-V-16B
ML20148F0931993-10-28028 October 1993
Rev 0 to Air Accumulator for FW-V-16A
ML20059F0471993-08-31031 August 1993
Amend 18 to Post-Defueling Monitored Storage (Pdms) Sar. W/Rev 2 to List of Pdms Requirements & Commitments
ML20056E5921993-07-31031 July 1993
Conservative Design In-Structure Response Spectra for Resolution of USI A-46 for Tmi,Unit 1
ML20045F2721993-06-18018 June 1993
Rev 10 to TER for Interim Solid Waste Staging Facility
ML20044H3601993-05-31031 May 1993
Amend 17 to Post-Defueling Monitored Storage Sar
ML20044D1591993-05-0505 May 1993
Rev 11 to Sys Description 3526-004, Auxiliary Bldg Emergency Cleanup Sys (EPICOR-II)
ML20035H6381993-04-15015 April 1993
Nuclear Safety & Compliance Committee Semiannual Rept 18, Oct 1992-Mar 1993
ML20035C3011993-03-16016 March 1993
Rev 9 to TER for Containment Air Control Envelope (Cace)
ML20059D7351993-02-0707 February 1993
Review of Offsite Response to Site Area Emergency Incident at Three Mile Island Nuclear Station
ML20036B7551992-12-31031 December 1992
TMI-1 PRA (Level 1) Vols 1-6
ML20126D2831992-12-18018 December 1992
Criticality SAR for TMI-2 Reactor Vessel
ML20114B9631992-08-0808 August 1992
Rev 3 to Criticality Safety Evaluation of TMI Fuel Storage Facilities W/Fuel of 5% Enrichment
ML20058F6561992-07-31031 July 1992
Companion Sample Exams
ML20058F6481992-01-31031 January 1992
Metallographic & Hardness Exams of TMI-2 Lower Pressure Vessel Head Samples
ML20066K3591991-01-31031 January 1991
Rev 0 to Rept on 1990 Eddy Current Exams of TMI-1 OTSG Tubing
ML20216K1251990-10-31031 October 1990
Amend 9 to Post-Defueling Monitored Storage Sar
ML20217A4251990-09-11011 September 1990
Rev 3 to Licensing Rept for Spent Fuel Pool Mod of Pool a: TMI Unit I
ML20058M7251990-08-0101 August 1990
Rev 2 to Div Technical Evaluation Rept for Processed Water Disposal Sys
ML20056A0091990-07-26026 July 1990
TMI-1 Trust Agreements
ML20044A4131990-06-21021 June 1990
Amend 7 to Post-Defueling Monitored Storage Sar
ML20043A2341990-05-0202 May 1990
Rev 0 to TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5)
ML20055C9461990-03-31031 March 1990
Final Rept, TMI - Unit 2 Safety Advisory Board, for Mar 1981 - Dec 1989
ML20011F5391990-02-22022 February 1990
TMI Nuclear Station Unit 2 Defueling Completion Rept
ML19354E8201990-01-18018 January 1990
Rev 3 to Defueling Completion Rept
ML19327B4271989-10-17017 October 1989
Errata to Section 2.1, Prerequisites, of Removal of Metallurgical Samples from TMI-2 Reactor Vessel
ML19325D6301989-09-25025 September 1989
Rev 1 to Div Technical Evaluation Rept for Processed Water Disposal Sys
1999-08-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1001999-10-14014 October 1999
Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage
ML20217K4701999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for TMI-1.With
ML20216F9231999-09-22022 September 1999
Safety Evaluation Supporting Amend 216 to License DPR-50
05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
- on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.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
ML20211E8731999-08-24024 August 1999
Safety Evaluation Supporting Amend 215 to License DPR-50
ML20211B1931999-08-19019 August 1999
Safety Evaluation Supporting Amend 214 to License DPR-50
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
05000289/LER-1999-009, :on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced1999-07-22022 July 1999
- on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced
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
ML20196J5941999-07-0101 July 1999
Safety Evaluation Supporting Amend 213 to License DPR-50
ML20209H1421999-06-30030 June 1999
Monthly Operating Rept for June 1999 for TMI-1.With
ML20212H9101999-06-21021 June 1999
Safety Evaluation Supporting Amend 212 to License DPR-50
05000289/LER-1999-007, :on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed1999-06-18018 June 1999
- on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed
ML20195J9401999-06-15015 June 1999
Safety Evaluation Supporting Amend 211 to License DPR-50
05000289/LER-1999-005, :on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With1999-06-14014 June 1999
- on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With
ML20195H0751999-06-0808 June 1999
Drill 9904, 1999 Biennial Exercise for Three Mile Island
ML20209G0351999-05-31031 May 1999
TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo)
ML20195H9261999-05-31031 May 1999
Monthly Operating Rept for May 1999 for TMI-1.With
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
05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open1999-05-0707 May 1999
- on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
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
ML20205Q6111999-04-15015 April 1999
Safety Evaluation Supporting Amend 210 to License DPR-50
ML20205Q5981999-04-13013 April 1999
Safety Evaluation Supporting Amend 209 to License DPR-50
ML20206P2841999-04-12012 April 1999
SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90
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
05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With1999-03-14014 March 1999
- on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.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
05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys1999-02-19019 February 1999
- on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
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
05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With1999-01-11011 January 1999
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
ML20196G4661998-12-31031 December 1998
British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl
ML20207A9291998-12-31031 December 1998
1998 Annual Rept for TMI-1 & TMI-2
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
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20195C6921998-11-12012 November 1998
Safety Evaluation Supporting Amend 52 to License DPR-73
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
05000289/LER-1998-013, :on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance1998-10-15015 October 1998
- on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance
05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued1998-10-0909 October 1998
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
ML20154L5541998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for TMI Unit 1.With
1999-09-30
[Table view] |
Text
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i 42105-R-002 Revision 1 Sept.19,1995 Page 3 of 84 i
TABLE OF REVISIONS Revision Descriotion of Revision Date Acoroved 0
Original issue May 11,1995 1
Revised last paragraph Sept.19,1995 of Section 2.2.3 Part 1, per GPUN Letter No.
C311-95-2361 l
9510020236 950927 PDR ADOCK 0500o289 P
PDR
42105-R-002
- a. * '
Revision 1 Sept.19,1995 Page 30 of 84 i-MU-P-1B is normally operating to provide make-up and seal injection. The i
make-up pump (s) will initially take suction from the make-up tank. Suction will be switched to the borated water storage tank for additional water I
inventory as the make-up tank inventory is depleted. If make-up pump MU-P-l 1C is the only pump available, make-up without relying on local operator actions is from the borated water storage tank.
In addition to providing inventory control, the make-up system supplies water for seal injection, the preferred method of protecting reactor coolant pump (RCP) seals. If seal injection is not available from the make-up system, another acceptable method of maintaining seal integrity is by providing pump thermal barrier cooling from the intermediate cooling system which is l
identified as a supporting system needed to achieve the safe shutdown i
functions. Seal injection or thermal barrier cooling is required when RCS temperature is > 190 F, whether or not the RCPs are running, to prevent excessive leakage of reactor coolant from the seals.
The make-up pumps require a minimum recirculation flow to protect the pumps from overheating. The required minimum flow is normally provided by the motor operated recirculation valves MU V-36 and MU-V-37. These valves must be open when make-up pumps are operating. Flow from make-up pump MU-P-1C is not normally directed through seal injection of the normal make-up
- path, Recirculation flow is returned to the make-up tank. For the case where the d
BWST is used as a water source, the make-up tank will eventually fill from the recirculation flow. Sufficient time is available to prevent overfilling by l
manually returning pump suction to the make-up tank.
i l
- 2. Letdown for Inventory control The letdown capability will greatly simplify reactor inventory control. Manual j
control of enough components is possible to achieve and control letdown flow.
1 Sufficient time is available to line up the necessary components. The letdown d
.
