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Category:APPLICATION
MONTHYEARML19350D1611981-03-19019 March 1981 Reapplication by Wa Fraser for Operator License ML19350D1601981-03-19019 March 1981 Reapplication by Re Boyer for Senior Operator License ML19350D1591981-03-19019 March 1981 Reapplication by Nj Monson for Operator License ML20129H1651979-01-31031 January 1979 Partially Withheld Application for M Kending for Reactor Operators License Examination ML20128F5071979-01-31031 January 1979 Partiallt Withheld Application by C Mell for Reactor Operators License Examination ML20128F5331979-01-31031 January 1979 Partially Withheld Application for J Brummer for Senior Operator License Examination ML20128F5561979-01-31031 January 1979 Partially Withheld Application by J Garrison for Senior Operator License Examination ML20129H1461979-01-31031 January 1979 Partially Withheld Application by J Herman for Operator License ML20129H1881979-01-31031 January 1979 Partially Withheld Application for D Smith for Reactor Operator License Examination ML20129H2011979-01-31031 January 1979 Partially Withheld Application by D Mayhue for Reactor Operator License Examination ML20129H1281979-01-24024 January 1979 Partially Withheld Application for Amendment to Senior Operator License for R Hutchinson ML20129G6381978-11-0909 November 1978 Partially Withheld Application for Renewal of Senior Operator Licesne Number SOP-2866-1 by J Seelinger ML20129G4601978-09-14014 September 1978 Partially Withheld Application for Reactor Operator License for E Hemmilia ML20129G4311978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for Hb Shipman ML20129F5161978-09-14014 September 1978 Partially Withheld Application for Senior Operator for R Zechman ML20129F4871978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for C Hartman ML20129F4741978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for J Logan ML20024B7591977-07-0505 July 1977 Application by Wh Zewe for Senior Reactor Operator License ML20024B7581975-07-10010 July 1975 Application by Wh Zewe for Senior Reactor Operator License ML20024B7571974-05-20020 May 1974 Application by Wh Zewe for Hot Reactor Operator License.Prof Qualifications Encl ML19270H5331973-12-19019 December 1973 Amend 2 to Application for SNM License Re Higher Strength Source to 1,300 Ci of Americium ML19270H5311973-10-15015 October 1973 Amend 1 to Application for SNM License ML19270H5291972-06-0808 June 1972 Application for SNM License for Storage Only of Fuel Elements & Byproduct Matl 1981-03-19
[Table view] Category:SENIOR OPERATOR LICENSE
MONTHYEARML19350D1601981-03-19019 March 1981 Reapplication by Re Boyer for Senior Operator License ML20128F5561979-01-31031 January 1979 Partially Withheld Application by J Garrison for Senior Operator License Examination ML20128F5331979-01-31031 January 1979 Partially Withheld Application for J Brummer for Senior Operator License Examination ML20129H1281979-01-24024 January 1979 Partially Withheld Application for Amendment to Senior Operator License for R Hutchinson ML20129G6381978-11-0909 November 1978 Partially Withheld Application for Renewal of Senior Operator Licesne Number SOP-2866-1 by J Seelinger ML20129G4311978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for Hb Shipman ML20129F5161978-09-14014 September 1978 Partially Withheld Application for Senior Operator for R Zechman ML20129F4871978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for C Hartman ML20129F4741978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for J Logan ML20024B7591977-07-0505 July 1977 Application by Wh Zewe for Senior Reactor Operator License ML20024B7581975-07-10010 July 1975 Application by Wh Zewe for Senior Reactor Operator License 1981-03-19
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARRC-99-0201, Suppl 2 to 990819 Application for Amend to License NPF-12 (TSP 980009),revising Heatup & Cooldown Curves in TS 3/4.4.9 RCS Pressure/Temp Limits & TS B 3/4.4.9.Rev 2 to WCAP-15102 Encl1999-10-0808 October 1999 Suppl 2 to 990819 Application for Amend to License NPF-12 (TSP 980009),revising Heatup & Cooldown Curves in TS 3/4.4.9 RCS Pressure/Temp Limits & TS B 3/4.4.9.Rev 2 to WCAP-15102 Encl ML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev RC-99-0154, Application for Amend to License NPF-12,revising Heatup & Cooldown Curves Located in TS Section 3/4.4.9.Requests Supersedes 990218 Application for Amend in Entirety.Rev 1 to WCAP-15102 Encl1999-08-19019 August 1999 Application for Amend to License NPF-12,revising Heatup & Cooldown Curves Located in TS Section 3/4.4.9.Requests Supersedes 990218 Application for Amend in Entirety.Rev 1 to WCAP-15102 Encl ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld RC-99-0100, Application for Amend to License NPF-12,revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water,Per TS Section 3.7.1.3, CST - Lco1999-05-17017 May 1999 Application for Amend to License NPF-12,revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water,Per TS Section 3.7.1.3, CST - Lco ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems RC-98-0214, Application for Amend to License NPF-12,revising Testing Methodology Utilized by Vsns to Determine Operability of Charcoal Adsorbers in ESF Air Handling Units1998-12-0404 December 1998 Application for Amend to License NPF-12,revising Testing Methodology Utilized by Vsns to Determine Operability of Charcoal Adsorbers in ESF Air Handling Units ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20153C3871998-09-18018 September 1998 Application for Amend to License NPF-12,revising TS 3.1.3.1, 3.2.2,3.2.3 & 6.9.1.11 by Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys at VC Summer When Thermal Power Is Greater than 25% RTP RC-98-0126, Application for Amend to License NPF-12,revising TS 4.7.7.e to Remove Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months1998-07-0101 July 1998 Application for Amend to License NPF-12,revising TS 4.7.7.e to Remove Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC RC-98-0016, Application for Amend to License NPF-12,requesting Removal of Table 4.8-1, Diesel Generator Test Schedule1998-02-0909 February 1998 Application for Amend to License NPF-12,requesting Removal of Table 4.8-1, Diesel Generator Test Schedule ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 RC-97-0108, Application for Amend to License NPF-12,revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Engineering Safeguards Features Air Handling Units1997-05-21021 May 1997 Application for Amend to License NPF-12,revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Engineering Safeguards Features Air Handling Units ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems RC-97-0065, TS Change Request - TSP 97-04,to License NPF-12,adding Footnote to TS 3.8.1.1, AC Sources - Operating, to Allow One Time Extension of Allowed Outage Time from 72 H to 7 Days to Perform on-line Maint on EDG B During Cycle 111997-03-26026 March 1997 TS Change Request - TSP 97-04,to License NPF-12,adding Footnote to TS 3.8.1.1, AC Sources - Operating, to Allow One Time Extension of Allowed Outage Time from 72 H to 7 Days to Perform on-line Maint on EDG B During Cycle 11 RC-97-0063, TS Change Request - TSP 97-02 to License NPF-12,charging mini-flow Header Isolation Motor Operated Valves1997-03-26026 March 1997 TS Change Request - TSP 97-02 to License NPF-12,charging mini-flow Header Isolation Motor Operated Valves RC-97-0064, TS Change Request - TSP 97-03 to License NPF-12,deleting Conservative from Definition of Core Alterations1997-03-26026 March 1997 TS Change Request - TSP 97-03 to License NPF-12,deleting Conservative from Definition of Core Alterations ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20128G2891996-10-0202 October 1996 Amend 135 to License NPF-12,changing TS for Plant Unit 1,in Response to 960416 Application,As Suppl by ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a RC-96-0109, TS Change TSP 950011 to License NPF-12,revising TS 3/4.6, Containment Sys Bases 3/4.6 & TS 6.8, Administrative Controls - Programs & Procedures, to Adopt Implementation Requirements of 10CFR50,App J,Option B1996-04-16016 April 1996 TS Change TSP 950011 to License NPF-12,revising TS 3/4.6, Containment Sys Bases 3/4.6 & TS 6.8, Administrative Controls - Programs & Procedures, to Adopt Implementation Requirements of 10CFR50,App J,Option B ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application 1999-08-20
[Table view] |
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METROPOLITAN EDISON COMPANY m. - :" ci.m.<: '.. uc m, mu mumw' r / - --
TELEPHONE 717 944 4041 POST OFFICE DOX 480 MIDDLETOWN.PENNSYLV ANIA 17057 January 31, 1979 j Mr. Paul F. Collins U.S. Nuclear Regulatory Comission Office of fluclcar Reactor Regulation liashington, D.C. 20555
Dear Mr. Collins:
Please consider this application for a Senior Reactor Operator's 1.icense exanination. In accordance with Section 55.10 of 10CFR55, the following infomation is submitted: I 4
- 1. flame Jn Allen Brumer -
h Age: r Present Employment: Metropolitan Edison Company, Three Mile Island Itucicar Station, Unit II
- 2. a) Education:
- 1. Annville Cleona High School Graduated - Annville, Pa.
- 2. Tennessee Technilogical Univeristy Electrical Engineering - Graduated, okevill Tenn.
l b) Experience:
ical University f, 1. Tennessee Ter.hnilok11e, Tenn.
Caretaker - Cookev . formation m. this record was de Of Informatic Tennessee Technilogical University t exe pt on 2.
Proctor - Cookeville, Tenn. f0lA. - c77/ _
l 3. Engineer Jr. (3/74 - 6/75) - lictropolitan Edison Company Three fille Island flucicar Station, Middictown, Pa.
- 4. Engineer I (7/75 - 12/76) fletropolitan Edison Company.
Three !!ile Island Ifucicar Station, lliddletown, Pa. p' 9610000113 960924 PDR FOIA DEKOK96-207 PDR
s January 31, 1979 l
. tir. Paul F. Collins f
S. Engineer II (1/77 - present) - tictropolitan Edison company, 1 Three title Island Nuclear Station, fliddletown, Pa.
i As an Engineer II, I have been involved with the Unit II PORC which has approved the Operatirg Procedures, which are associated i itith the nuc1 car safety of the Unit, Surveillance Procedures and Unit Energency and Abnornal Procedures. l Ilhile holding this position I have also been responsibic for writing ,
and reviewing some of the Operating and Survie11ance Procedures ase.ociated with Instrumentation and Control dealing with such systems l
a', the Reactor Protection System, fluclear Instrumentation System, i flon-fluclear Instrumentation System, Radiation Monitoring System, and Engineered Safety Features System to mention a few. 1 l
During the startup and test phases of Unit II, I was responsible for !
performing the Test Procedures associated with the Radiation 11onitoring System. In addition, during the Power Escalation Phase I was the !
ICS Tuning Coordinator responsible for tuning associated with the Unit II Integrated Control Systen, which required constant interface j
with the Control Room.
Previous Opeartor's License flumber - flone. l 3.
- 4. License is requested to operate a pressurized water reactor; fietropolitan Edison Conpany Three Mile Island fluclcar Station, Unit II.
- 5. See attached letter.
- 6. See Enclosure 1.
- 7. liedical exanination will be forwarded under separate cover.
Sincerely yours,
$. buw i ^~
John A. Brummer JAD/dra Enclosure 4
,9~222
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',6 ErlCLOSURE I TRAlfilflG PROGRAff RECEIVED BY:
John A. Drumer
The general outline of Mr. Drummer's training follows:
- 1. License Trainin Program (minimum 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />)(1/2/79present)
Reactor Theory 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />)
Health Physics 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />) l ICS (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)
Reactor Operations (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)
Systems (flSS and BOP) (200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />)
Procedures (50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />)
Tech. Specs. (20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />)
- 2. PWR Simulator Training at Babcock and Wilcox Corporation with Startup (Startup Certification will be forwarded by Babcock Certification (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />)(2/26/79 - 3/2/79 and 3/5/79 - 3/9/79) and tillcox Corporation)
- 3. OntheJobTraining(Minimum 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />)
Participated in, simulated or discussed the following:
Procedures Operation
- 1. llrote several Operating Procedures for Unit #2 g,uch as EHC, RPS, R!tS.
- 2. Attended PORC as PORC member and primary reviewer for Instrumentation and Control Procedures. ,
Surveillance
- 1. Idrote numerous Surveillance Procedures for Unit #2 for such systems as the following: Radiation lionitoring System,' Reactor Protection System, ilon-fluclear Instrumentaton, Engineered Safety Freatures Systens.
- 2. Provide technical supervisor for performance of Instrunentation and Control Surveillance Procedures.
PORC
- 1. Reviewed procedures as mentioned above.
- 2. Served as Instrumentation and Control reviewer during Tech. Spec. review of BfAl generic Tech. Specs. to develop Standard Tech. Specs. for Unit #2.
Control Room
- 1. Reactor Criticality - Performed calculation of estimated critical rod position.
- 2. Discussed rod withdrawal, chenical shim and the necessary rod index for power escalation and steady state conditions.
- 3. Power Operations
- 1. Performed Heat Balance Calculatinns
- 2. Perforned Reactor Coolant Total Flow Calculations
- 3. Olscussed and participated in Feed and Bleed Operations.
- 4. Discussed and perfor'med ICS Tuning at power to maintain steady-state
-)
lj operations. ~& 'gg
- -- .--.--..____-,_,^^*"*'""'^wme- - n.a__g.__ _
PAGE 2
.EpciosureI Transients i
- 1. Supervised transient test during power excalation program per TP800/23 such as follows:
i
- 1. Feedpump trip from 90% F.P. and recovery.
- 2. Step changes of 10% in magnitude using ULD, steam generator / reactor i demand station and turbine station.
- 3. Reactor coolant pump trip.
- 4. Load change from 95% F.P. to 50"..F.P. and recovery to 95%.
Balance-of-Plant _
- 1. Performed post-core load fuel verification.
- 2. Participated in reactor building fuel handling operations during core load.
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