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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:OPERATIONAL LOG-PLANT SYSTEMS
MONTHYEARML20062J7041980-10-31031 October 1980 Form 1616.1,Revision 3, Insp of Emergency Respiratory Equipment ML20136C2191979-09-13013 September 1979 Strip Chart RB Pressure Data (Enhanced Trace).Radiological Ref 95 ML20136C2591979-09-12012 September 1979 Chronology of Incident on 790329 by H Mcgovern (Control Room Operator), ML19209B6751979-06-0909 June 1979 Surveillance of Feedwater Pump Turbines Required by Tech Specs,As of 790609 ML20136B8681979-05-22022 May 1979 Computer Listing of Monitored Variables ML19269E4211979-05-18018 May 1979 TMI-1 Work List.Items Listed in Priority Order ML17317B5611979-05-18018 May 1979 Reactor Coolant Pump Vibration & Loose Parts Monitor Data Delogged ML20136C0141979-05-0101 May 1979 Plant Status Readings for 790510,11,31 & 0601 ML20136A8731979-04-23023 April 1979 Incident Message Forms C-185 Through C-196 ML20136C2321979-04-19019 April 1979 Operations Records.Radiological Ref 150 ML20126K5301979-04-11011 April 1979 Plant Sys Operation Log ML20136A8711979-04-10010 April 1979 Incident Message Forms R-262 Through R-282 ML20136C2091979-04-0101 April 1979 TMI-2 Reactor Coolant Analysis Sheets.Radiological Analysis of Samples.Radiological Ref 131 ML20136C2221979-03-30030 March 1979 MU-T-1 Tank Level Data.Radiological Ref 121 ML20136C7261979-03-28028 March 1979 Plant Sys Readings for TMI-2 ML20136C6471979-03-28028 March 1979 Strip Charts for Polisher 4 Recorder 82,Polisher 3 Recorder 81 & Polisher 2 Recorder 80 on 790328-29 ML20136C1131979-03-28028 March 1979 TMI-2 Chemical Log for 790325-28 ML20136C2431979-03-28028 March 1979 Environ Control Survey Log for 790328-30.Radiological Ref 169 ML20136C6521979-03-28028 March 1979 Generator & Reactor Readings for TMI-2 on 790328 ML20136C6601979-03-28028 March 1979 TMI Strip Chart of Boric Acid Mix Tank Level ML20136C6861979-03-28028 March 1979 TMI Strip Chart for Recorder 51,monitoring Condenser Hotwell & Reactor Coolant Loop B Inlet Temps ML20136B8671979-03-19019 March 1979 Computer Listing of Performance Data ML20136C2171979-02-0707 February 1979 Surveillance 1302-2.11 Performance Form & Data Sheets. Quarterly Instrument Calibr.Radiological Ref 39 ML20136C2391978-12-14014 December 1978 Surveillance Procedure 1302-3.1A Data Sheets Re Rms Quarterly Survey.Radiological Ref 37 ML20136C2361978-12-11011 December 1978 Engineering Change Memo Re Isokinetic Nozzles for HP-R-221A, 221B,222A,222B,222C,222D,228D,228A & 228B.Radiological Ref 45 ML20136C7151978-11-0303 November 1978 Log of Test Results from Test Procedure TP-800-21 Administered to Reactor Trip ML20125B4851978-05-12012 May 1978 Pages from chemistry-polisher Status Log Book Re 780512 Condensate Trip.Includes Statement That Air Fluff Valves Were Left Open ML20125D8851977-09-24024 September 1977 Data on RCS Pressure Transient for Electromagnetic Pressurizer Relief Valve That Stuck Open,Causing Small Break in RCS Piping ML20136C1891975-07-0202 July 1975 Calibr Data Sheets for 750522-0702,calibr Procedure Peculiarities & Factory Point Source Calibr.Vendor Tech Specs,Test Data Sheets & Drawings Encl 1980-10-31
[Table view] |
Text
.. . OPEPAT! Oils SURVEILLA!!CE Ob-I/O /
ve*1" ff/A Pl/a Saturdav 7-3 Frequency Montn Week Day Snift TITLE: Feedwater Pumo Turbines
~
SURVEILL A'lCE (Accentance)
- 1. CR0 punch out following conputer points and attach printout to this data sheet and return to Ops. Engineer:
Pararr'ter "A" F.W.P.T. "B" F.U.P.T.
Printout this Printout this Ranaes column first column 2nd Expected Como. PT.# Como. PT.# Value Max. Min.
Main Turo. Gen. Load 98 880!t4 50fte 320 321 5800 0 Feed Pno Turb. Soeed Feed Pac Turo. Exhaust Pressure 28 29 28" 30" 25" Feed Pmo Disch. Pressure 30 31 Pac Feed Water Flow 21 22 H.P. Steam Inlet Temo. 41 43 535 570 530 L.P. Steam Inlet Ten.o. 42 44 370 390 360 H.P. Steam Vlv. Temo. 93 94 480 560 450 F.P. Inboard Bearina tietal Temo. 244 247 1gR 170 130 F.P. Outcoard Bearina tietal Temo. 245 248 14R 170 130 F.P. Inrust Bearing tietal Temo. 246 249 130 160 125 Turb. Active Thrust Bra. tietal Temo. 292 298 135 145 125 Turb. Inactive Thrust Bro. lietal Temo. 293 299 125 135 l?O Turb. Outboard Bro. Metal Temp. 294 300 170 180 160 Turb. Inboard Grg. Metal Temp. 295 301 170 180 160 Turb. Outboard 011 Orain Temo. 296 302 130 140 120 Oil Teno. Out of tne Cooler 297 303 120 130 120 Turb. H.P. Brg. Vibration 306 308 4 5 0 Turb. L.P. Bro. Vibration 307 309 4 5 0 Pao Inboard Bro. Vibration 310 312 <1 5 0 Pmo Outboard Bra. Vibration 311 313 <1 5 0 Indicate Turb. Vlv. Position A B Ifrom PLF) <
- 2. Perfom AUTO START of Aux. Oil Pump per attached procedure. A Pump (/ OK)
B Pump (/ OK)
- 3. Perfom AUTO START of D. C. Emergency 011 Pung per attached procedure.
A Pump (/ OK)
B Pump (/ OK)
- 4. Perfom Thrust Bearing Wear Test per attached procedure. A Turbine (/ Ors)
B Turbine (/ OK)
- 5. Perfom the Oil Reservoir Hi/Lo level arm test per attached procedure.
' ~~
A Reservoir (/ OK)
D Reservoir (/ CK)~
Foward to Ops. Engineer / Supervisor of Ops._after approval signature.
- . Supervisor of Operations: . ,
Approval: W/ 7 Perfomed By:
Date: 9!'79 Approved By:
Da-
. 7910100 h / '
OPS Form #0PS-5101 (continued)
AUTOMATIC START TEST OF AUXILIARY OIL PU!!P CAUTION:
The Feed Pumo Turbine must be operating above 3000 RPit and both the auxiliary oil pump and the D. C. energency bearing oil pump control switches should be in " normal af ter stop" position before performing this test.
Stimulate low pressure at the auxiliary oil pump automatic (INITIAL) 1.
A B start pressure switch by pressing the auxiliary _ oil _ oumo test _
oushbutton located to the left of the electrical console on the lef t side of the turbine oil tank.
- 2. The auxiliary oil pump should start and come to full speed.
Let pump run for one-half hour.
- 3. Af ter completing step 2, have Control Room Operator stop pump and leave control switch in " normal after stop" position.
- 4. Record any comments.
Performed by:
Date
!l3b 220
Ops. Forn .0PS-S con .
AUT0"ATIC START OF D.C. Ef1ERGENCY BEARI]G OIL PUMP f:
CAbTIO.l: (A) The Feed Pump Turbine must be operating above 3000 RPM and both the auxiliary oil pump and the D.C. energency bearing oil pumo control switches should be in " normal after stop" cosition.
OR (B) If turbine is operating below 3000 RPM, the auxiliary oil pump must be running and the control switch for the D.C. emergency oil pump should be in " normal after stop" position before perforning this test.
(INITIAL)
_ t[, B
- 1. Sinulate low pressure at the emergency oil pump automatic start pressure switch by pressing the turning gear oil pump test pushbutton located to tne lef t of the electrical console on the left side of the turbine oil tank.
- 2. The pump should start and come to full speed. Let pump run for one-half hour.
- 3. Af ter completing step 2, have Control Room Operator stop pump and leave control switch in " normal af ter stop" position.
- 4. Record any comments:
Performed By:
Date:
L i13S 221 e
4 Ops. Form OPS-5101 cont'd.
THRUST BEARING WEAR TRIP TEST CAUTION: The turbine is not protected against thrust I
I bearing failure during this test. Notify Control Room Operator before starting test and when test is completed.
(Initial)B A
- 1. The key switches for performing this test are located at the feed pump turbine front standard control panfl.
- 2. Turn the key in the thrust bearing wear test keyswitch to the pretest position and remove. This action disables the trip function by removing the trip contacts on pressure switches PS2 and PS12 from the trip circuits.and activates the test light circuits. Verify that the active and inactive
' thrust wear test complete lights come on and that the control room receives the "FPT Thrust Bearing Wear Trip Locked Out" alarm.
- 3. Insert' key in active thrust wear test switch and turn to test position. The active thrust wear test complete light will 3 0 out.
Return switch to normal positior. The test complete light will rame on again, and must remain on steady. Any light indications different from those specified indicate a malfunction in the test circuits or an actual thrust wear problem and must be reported.
Remove key.
4 Repeat step 3 for the inactive thrust wear test switch.
CAUTION: Proceed with step 5 only if both inactive and active test complete lights are on steady. The turbine will trip if the thrust bearing wear test key switch is rotated to the normal position when one of the lights is off or blinking.
1135 222
OPS Form #0PS-101 cont'd
. A 8
~
'I 5. Insert key back into thrust bearing wear test keyswitch and rotate to nomal position. This action enables the tr.p function by putting the trip contacts of pressure switches PS2 and PS12 back in the trip circuits and The two test complete lights deactives the test circuit.
will go out and the control room alarm will clear.
- 6. Record any coments:
Performed By:
Date:
' i135 223
- r. ,
TEST OF OIL RESERVOIR HI/LO LEVEL ALAR?t (I!!ITIAL)
A B
- 1. The handle for the oil reservoir Hi/Lo level alarm test is located on the ight side of the electrical junction box mounted on the lef t side of the turbine oil tank.
- 2. Push test handle to High level position. Control room should receive "FP/TURB A/B oil level Hi-Lo" alarm.
- 3. Release test handle. The control room alarm will clear.
- 4. Push the test handle to the low level position. The control room should again receive the alarm.
- 5. Release the test handle. The control room alarm should clear.
- 6. Record any comments:
' Performed by:
Date 113b 2.2:'4 O
OPEPATI0ftS SURVE?LLAf!CE Monthly N/A 2nd Sat. 7-3 Frequency Itontn Week ;ay Shift TITLE: EXERCISE THE FEEDPUMP TURBINE EMERGENrY GOVEPNOR (OIL TRIP TEST)
SURVEILLA?;CE (Acceotance)
CAUTION: Make sure green normal and reset lights are on before starting test.
Notify Control Room Operator before starting test.
Should require two operators in case the reset light will not stay on for communications. A B FPT FPT Thh test is performed at the turbine front standard control N 1.
- 2. Turn lockout control switch to lockout position. The green normal light will go out and the red lockout light comes on.
(Initial)
CAUTION: Do not release lockout control handle until completion of testing. Do not continue testing if lockout light does not come on.
- 3. While holding lockout control in lockout position, push the overspeed trip test pushbutton. The red trip exercised light will come on and the green reset light will go off.
- -; (Initial)
- 4. Push the reset pushbutton. The reset light will again come on and the trip exercised light will go off. (Initial)
CAUTION: The reset light must be on steady before releasing the lockout switch. The turbine may trip if the lockout switch is returned to normal and the reset light is not on steady.
- 5. When the reset light stays on, release the lockout control switch.. The lockout light will go out and green normal light will come on. (Initial)
- 6. Record any comments:
Forward to 9ps. Engineer / Supervisor of Ops, after approval signature.
Supervisor of Operations:3h '2 2 C Approval : [ P-u Perforned By:
Date: b /
Approved By:
._}}