|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 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 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 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 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 ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 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 ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,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 ML20210Q9991997-08-28028 August 1997 Safety Evaluation Concluding That Since 25th Tendon Surveillance on Few Yrs Away,Adequacy of Remaining Prestressing Force Will Be Critical to Verify ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20138H6671996-12-19019 December 1996 Safety Evaluation Accepting Util IPE Submittal in Response to GL 88-20 ML20134D7811996-10-24024 October 1996 Safety Evaluation Supporting Amend 51 to License DPR-73 ML20128L6741996-10-11011 October 1996 Safety Evaluation Accepting Third ten-year Interval for Pump & Valve Inservice Testing Program for Facility ML20128K1981996-10-0808 October 1996 Safety Evaluation Supporting Amend 50 to License DPR-73 ML20059D1771993-12-28028 December 1993 Safety Evaluation Supporting Amend 48 to License DPR-73 ML20062K1041993-12-0606 December 1993 Safety Evaluation Supporting Amend 47 to License DPR-73 ML20058F0311993-11-16016 November 1993 SE Informing That Changes to Pdms Requirements & Commitments List of 930115,does Not Constitute Unreviewed Safety Question,Nor Do They Involve Significant Hazard or an Environmental Impact ML20059K3001993-11-0808 November 1993 Safety Evaluation Supporting Amend 46 to License DPR-73 ML20057A3641993-09-0101 September 1993 SER Denying Licensee 930216 & 0416 Requests for Relief from Certain Requirements of ISI Program ML20056F0171993-08-0505 August 1993 Safety Evaluation Accepting Proposed Changes to Pdms Requirements & Commitments List of 930115 ML20128P7321993-02-19019 February 1993 Safety Evaluation Supporting Amend 171 to License DPR-50 ML20126M2861993-01-0505 January 1993 Safety Evaluation Granting Relief from ISI Post Repair Hydrostatic Schedule Requirements ML20058G1331990-11-0606 November 1990 Safety Evaluation Supporting Amend 39 to License DPR-73 ML20058P4681990-08-0909 August 1990 Safety Evaluation Accepting Changes to Table 4.3-3 of Recovery Operations Plan ML20247L0681989-09-11011 September 1989 Safety Evaluation Supporting Amend 35 to License DPR-73 ML20245J4411989-06-23023 June 1989 Safety Evaluation Supporting Util 850823 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability - On-Line Functional Testing of Reactor Trip Sys ML20247E8141989-05-18018 May 1989 Safety Evaluation Accepting Proposed Changes to Recovery Operations Plan ML20247G4131989-05-15015 May 1989 Safety Evaluation Supporting Amend 34 to License DPR-73 ML20245J1201989-04-27027 April 1989 Safety Evaluation Supporting Amend 149 to License DPR-50 ML20245A6521989-04-12012 April 1989 Safety Evaluation Supporting Amend 33 to License DPR-73 ML20196B3071988-12-0101 December 1988 Safety Evaluation Supporting Approval of Lower Core Support Assembly & Lower Head Defueling ML20153E6861988-08-31031 August 1988 Safety Evaluation Accepting Request for Exemption from Lecture Requirements of 10CFR55.59(c)(2) & for Exceptions to Control Manipulations Required by 10CFR55.59(c)(3)(i), Subsections (a) to (AA) ML20153E8471988-08-30030 August 1988 Safety Evaluation Approving Request for Mod of Recovery Operations Plan Table 4.3.3 ML20195B6991988-05-27027 May 1988 Safety Evaluation Supporting Amend 30 to License DPR-73 ML20155B3151988-05-25025 May 1988 Safety Evaluation Supporting Amend 30 to License DPR-73 ML20151D5611988-03-31031 March 1988 Sser of Util 870917 & 1103 Justifications for Proposals & & Relief Requests Re Pump & Valve Inservice Testing Program Denied in 870319 Ser.Exclusion of Stated Valves Accepted ML20150D5101988-03-18018 March 1988 Safety Evaluation Supporting Util 871027 Submittal Re Reconfiguring Main Steam Line Rupture Detection Sys Bypass Indicating Lamp During Cycle 8 Refueling Outage ML20147D9721988-02-26026 February 1988 Supplemental Safety Evaluation Supporting Util Use of Rochester Instrument Sys Model SC-1302 Isolation Devices,Per NUREG-0737,Suppl 1 ML20147E2491988-01-0808 January 1988 Safety Evaluation Supporting Util 871203 & 28 Requests to Use Core Bore Machine to Dismantle Lower Core Suport Assembly ML20237B1501987-12-10010 December 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components) ML20236T5611987-11-18018 November 1987 SER Accepting Util 831108,850805 & 870529 Responses to Generic Ltr 83-28,Item 2.2.1, Equipment Classification Programs for All Safety-Related Components ML20236M9221987-11-0505 November 1987 Safety Evaluation Supporting Util Proposal Re Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis ML20235S3241987-10-0101 October 1987 Safety Evaluation Approving Util 870724 Request for Staging of Two Radwaste Solidification Liners in Waste Handling & Packaging facility.TMI-2 Svc List Encl ML20237G5301987-08-12012 August 1987 Safety Evaluation of Util Response to Item 2.1 (Part 1) of Generic Ltr 83-28, Equipment Classification (Reactor Trip Sys Components) TMI-1. Util Response Acceptable ML20234B9701987-06-25025 June 1987 Safety Evaluation Supporting Amend 28 to License DPR-73 ML20212Q7341987-04-17017 April 1987 Safety Evaluation Supporting Amend 27 to License DPR-73 ML20206B4131987-04-0303 April 1987 Safety Evaluation Supporting Util 850416 Request for Deletion of Constraint of 20-ft Square Modified Penetrations Between Reactor & Auxiliary/Fuel Handling Bldgs.Expanding of Limit to 40-ft Square Acceptable ML20205C6161987-03-20020 March 1987 Safety Evaluation Re Util 860820 & 1020 Requests for Relief from ASME Code Section XI Requirements for Class 1,2 & 3 Components.Relief Should Be Granted Except for Requests 4 & 7.Insufficient Info Provided for Request 7 1999-07-09
[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
4 SAFETY EVALUATION B.Y-Tile OFFICE OF NUCLEAR REACTOR REGULATION FOR RECOVERY OPERATIONS PLAN CHANGE REQUEST 35 INTRODUCTION By letter dated December 16, 1985, the licensee requested approval for modifications to the T!!I-2 Recovery Operations Plan (ROP). This request was supplemented in a discussion with the licensee's staff held on Iiarch 27, 1986.
These changes involve revisions to Tables 4.3-1 and 4.3-7 of the R0P, as discussed below.
EVALUATI0ti The licensee proposes to make several changes to Table 4.3-1, to correct administrative errors arising from NRC R0P Change flo. 31, issued October 21, 19P;5 (GPUllC R0P Change Request flo. 29). In ROP Change No. 31, the neutron monitoring instrumentation surveillance requirements were listed solely in Table 4.3-1; previously, some requirements were also specified in Table 4.3-7.
Consolidating the requirements resulted in some administrative errors,to Table 4.3-1. The current request corrects these errors by making the following changes to Table 4.3-1:
- 1) The addition of a note which states " Intermediate and Source Range and Rate is not required at Cabinet 217."
- 2) Changing the frequency of channel checks frcm once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to monthly for Cabinet 217, with a note to that effect. The channel check frequency will remain once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the control room readout channels.
8607080383 860626 PDR ADOCK 05000320 P PDR mCE ) .. .. .. .. .. . .. .. .. .. .. . . .
WRNAMQ ,,, ,, , , . , ,, .. ,. . . .. ,. ., , . , . , ,,,,
^"> ... ... ... . . . . .. . .. . .. .. .. . . .. . .. . . . ...
NRC FORM 318 (10 80) NRCM 024 OFFICIR RECORD COPY
a .
.\
1
~
ll 2 The first change is necessary because prior to R0P Change flo. 31. Table 4.3-7 specified the surveillance reqTirements for the Intermediate anyource Range Neutron Flux level monitors, including the readout locations in the control i <
room and at Cabinet 217. Table 4.3-1 also specified surveillance requirements
! i for the neutron flux level monitors, and, additionally, the neutron flux rate
, monitors; however, this table did not identify readout locations. In R0P Change No. 31, Table 4.3-1 was revised to include the neutron flux level monitor readout locations previously listed in Table 4.3-7, however, the l neutron flux rate monitors were incorrectly identified as having readout capability at Cabinet 217. This oversight will be corrected by the proposed change.
The second correction to Table 4.3-1 is related to the first. Prior to R0P Change Ho. 31, Table 4.3-7 required monthly channel checks for the neutron flux level monitors at the control room and Cabinet 217 readout locations.
Table 4.3-1 required channel checks every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the neutron flux level and rate monitors at the control room readout locations only. The proposed I change will restore the monthly channel check frequency for the neutron flux level monitoring instrumentation in Cabinet 217. This frequency is consistent with the original intent of the requirement and will minimize the wear and tear on the equipment in Cabinet 217. The channel check frequency will remain at once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the neutron monitoring instrumentation control room J
readout locations. These two changes are administrative in nature and will correct discrepancies found in an earlier revision to the R0P, therefore the staff finds them acceptable.
'**C'> . . . ......... ............. ............. .............. ...... ...... ............. .............
'u= > ............ ............. ............. .............. ............. ............. ............
une ronu :ns oasoi nacu o2" OFFICIAL RECORD COPY
The licensee also proposes to modify Table 4.3-7 by adding an alternate readout location for Reactor Building Water Level indication. The licensee has installed this alternate level indication, consisting of a probe and level indicating transmitter with readout in the Hot Instrument Shop. The proposed change will improve Reactor Building Water Level monitoring reliability by providing an additional capability for surveillance, thus allowing greater operational flexibility.
The staff concludes that the proposed changes to the R0P do not pose a significant risk to the health and safety of the public and that the proposed changes are within the scope of activities and events analyzed in the PEIS. We therefore approve the proposed changes to the THI-2 Recovery Operations Plan as discussed herein. Our approval of GPU R0P Change Request flo. 35 is flRC R0P Change Approval No. 32.
OF FICE ) , , , ,,,,, ,,,, ,,,,, , ,,, , ,, , ,, ,,,,, , , , ,,
sun"* > ........... . .. . . ... ... . . ... . .. .. . .. ... .
- ^"> .... ..... .. .. .. . ....... . . ..... .. ....... .. . ... . . .........
. une sonu ais no so> sncu o24 OFFICIAL RECORD COPY
Enclosure FACILITY OPERATING LICENSE N0. DPR-73 DOCKET f!0. 50-320 Replace the following pages of the Ti1I-2 Recovery Operations Plan with the enclosed pages as indicated:
4.3-2 .
4.3-10 OD F ICE ) ...... .... .... ........ .. ........ ..... ..... . .... .... ......... ... ......... ...
SURNAMEb r .... ....... ...... ...... .............
- ^> ............ ............. .......... .. ..... . ...... ............ . .........- .... -
NRC FORM 318 (10 80) NRCM 0240 OFFICIAL RECORD COPY
m 55 l;
TABLE 4.3-1 f>3 E5 NEUTRON MONITORING INSTRUMENTATION
, Si Z
m.
CHANNEL MINIMUM CHANNEL CHANNEL FUNCTIONAL TOTAL N0. CHANNELS CHANNELS READ OUT FUNCTIONAL UNIT CHECK CALIBRATION TEST OF CHANNELS TO TRIP OPERABLE LOCATIONS
- i. ,
- 1. Intermediate' Range, Neutron S/M(4) R(1) M 2 0 1 Cab 217 +(2&3)
Flux Rate Control Room
- 2. Source Range, Neutron Flux S/M(4) R(1) M 2 0 2 Cab 217 +(2&3) f=
ja and Rate Control Room m
NOTES
- 1) Neutron detectors and all channel components located inside containment may be excluded from CHANNEL CALI-BRATION.
- 2) Only one readout required at Cabinet 217.
- 3) Intermediate and Source Range is not required at Cabinet 217.
- 4) Monthly channel check applies only to Cabinet 217.
EE AA no "
~
I 1
- jl TABLE 4.3-7 m
2 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3:
m IA g
4
- MINIMUM l gj CHANNEL CHANNEL (1) READOUT OPERABLE INSTRUMENT CHECK CALIBRATION LOCATION (S) CHANNELS
- ~Si El 1. Reactor Building Pressure S R Control Room 2 SA Control Room (2) 2(2)
- 2. Reactor Vessel Water Level S/W(2)
- 3. Incore Thermocouples/RCS S R Control Room or 2(3)
Temperature Detectors Cable Room
- 4. Reactor Building Water Level NA SA Control Bldg. 1
- - Area West or Hot i) Instrument Shop "o
- 5. Borated Water Storage Tank S R Control Room 1 i Level
- 6. Steam Generator Level NA NA NA 1/ Generator
- 7. Spent Fuel Storage Pool S/W(2) SA Control Room (2) 2(2)
"A" Water Level or Fuel Handling
- Bldg.
- c. so 8. Fuel Transfer Canal S/W(2) SA Control Room 2(2) g 53 (deep end) Water Level or Reactor Bldg.
mn g( [ (See following page for notes)
, . o
' 3 u>
8*
TMI-2 SERVICE LIST Dr. Thomes Murley Willis 'Staly. Site Matager Regional Administrator. Region i U.S. Department of inergy U.S. nuclear Regulatory Comission P.O. Boa 88 631 Park Avenue Middletown. PA 17057-0311 L King of Prussia. PA 19406 (
David J. McGoff John F. Wolfe. Esq.. Chairman. Division of Three Mile Island Programs Administrative Judge NC-23 3409 Shepherd St. U.S. Department of Energy Chevy Chase. MD. 20015 Washington. D.C. 20545 Dr. Oscar H. Paris William tochstet Administrative Judge 104 Davey Laboratory AtomlC Safety and Licensing Pennsylvania State University University Park. PA 16802.
Board Panel U.S. Nuclear Regulatory Comission Washington D.C. 20555 Randy Myers. Editorial The Pa triot
- Administrative Dr. Frederick H.Judge Shon
Harrisburg PA 17105 Atomic Safety and Licensing Board Panet Robert B. Borsum U.S. NvClear Regulatory Comission Babcock & Wi1Cox Washington. D.C. 20555 Nuclear Power Generation Division Suite 220 Karin W. Carter 7910 Woodmoant Ave.
Assistant Attorney General Bethesda. MD. 20814 505 [secutive House P.O. Bom 2357 Michael Churchhill Esq.
Harrisburg PA 17120 FILCOP 1315 Walnut St.. Suite 1632 Dr. Judith H. Johnsrud Philadelphia, PA 19107 Environmental Coalition on Nuclear Power Linda W. Little 433 Orlando Ave. 5000 Hermitage DR.
State College, PA 16801 Ral,ei gh.NC 27617 George F. Trowbridge. Esq. Marvin I. Lewis Shaw. Pittman. Potts and 6504 Bradford Terrace Trowbridge Philadelphia. PA 19149 1800 M. St.. WW.
Washington, D.C. 20036 Jane Lee 183 valley Rd.
Atomic Safety and Licensing Board racel Etters.PA 1731g U.S. Nuclear Regulatory Comission Washington D.C. 20555 Bishop. Lieberman & Cook ATTN: J. Lieberman. Esquire Atomic Safety and Licensing Appeal Panel 1155 Avenue of the Americas U.S. Nuclear Regulatory Comission New York. New York 10036 Washington. D.C. 20555-Walter W. Cohen. Consumer Ad.ocate Secretary Department of Justice U.$. Nuclear Regulatory Comission Strawberry Square.14th Floor ATTN: Chief. DOCheticq & Service Branch Harrisburg. PA 17127 Washington. D.C. 20555 Edward O. Swartz far. Larry HoChendoner Board of Supervisors Dauphin County Comissioner Londonderry Township P.O. Box 1295 RFD #1 Geyers Church Rd.
Harrisburg *PA 17108-1295 Middletown. PA 17C57 Fred Rice. Chairperson Robert L. Knupp. Ltquire Dauphin County Board of Cocunissioners Assistant Solicitor Dauphin County Courthouse Knupp and Andrews front and Market Streets P.O. Bom P Harrisburg, PA 17101 407 N. Front St.
Harrisburg. PA Ul08 D,auphin County Of fice of Emergency Preparednes s John tevin. Esquire Court House. Room 7 Pennsylvania PubllC Utilities Conv4 Front & Market Streets P.O. Box 3265 Harrisburg. PA 17101 Marrisburg PA 17120 U.S. Environmental Protection Agency Region 111 Of fice ATTN: (j$ (oordinator Curtis Building (51sth floor) 6th & Walnut Streets Mr. Edwin tintner Philadelphia. PA 19106
[secutive vice Prestdent Thomas M. Gerusky. Director General Public Uttlities NvClear Corp.
100 gr.terpace Part.ay Bureau of Radiation Protection Persip;,any. NJ 07054 Department of Environraental Resources P.O. 6am 2063 rarrisburg. PA 17120 Ad Crable
- Dan Kennedy Lancaster New Era 8 West King Street Office of Environmental Plannin9 Lancaster PA 17601 Department of Environmental Resources P. O. Box 2063 Harrisburg. PA 17120
.