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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs 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 Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,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 ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program ML20084N3541995-03-24024 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20137B5371995-03-22022 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20081C1281995-03-0808 March 1995 Svc Water Sys Operational Performance Insp Self-Assessment Plan ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20059M2301993-11-12012 November 1993 Rev 7 to 6610-PLN-4200.01, Odcm ML20057B3781993-09-0202 September 1993 Rev 6 of Solid Waste Staging Facility Sys Description ML20127A2181992-10-15015 October 1992 Rev 1 to 6615-PLN-4520.01, REMP - Plan ML20127A2301992-08-11011 August 1992 Rev 30 to Emergency Procedure 1202-32, Flood ML20090D4031991-10-0404 October 1991 Rev 16 to Waste Solidification Process Control Program ML20082M2991991-08-29029 August 1991 Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20127A1511991-07-0808 July 1991 Rev 4 to 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20082M2951991-06-27027 June 1991 Rev 14 to Operating Procedure 1104-28I, Waste Sodification Process Control Program ML20198B9741991-06-17017 June 1991 Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070L3331991-03-15015 March 1991 Rev 1 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070U9241991-03-0404 March 1991 Rev 0 to 6610-PLN-4200.01, Odcm ML20059H9031990-09-0707 September 1990 Rev 0 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20059C7931990-08-23023 August 1990 Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility ML19351A4371989-11-30030 November 1989 Rev 9 to 9110.PLN-4200.02, Emergency Dose Calculation Manual. ML20248D4071989-09-27027 September 1989 Rev 8 to 9100-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20245K1211989-08-0202 August 1989 Rev 4 to SD 3184-007, Div Sys Description for Solid Waste Staging Facility ML20244C2961989-06-30030 June 1989 Rev 1 to Sys Description SD 3510-013, Div Sys Description for Reactor Bldg Sump Recirculation Sys ML20246M7931989-03-0909 March 1989 Rev 11 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154C7191988-06-0303 June 1988 Rev 10 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154Q6771988-05-27027 May 1988 Recovery Operations Plan ML20236M1621987-11-0909 November 1987 Radiological Environ Monitoring Program for TMI-1 ML20236M4281987-10-19019 October 1987 Vols 1 & 2 of 1987 TMI Annual Exercise Scenario ML20147F9331987-08-25025 August 1987 Rev 3 to Procedure 1000-ADM-1291.01, Procedure for Nuclear Safety & Environ Impact Review & Approval of Documents ML20238C6391987-08-21021 August 1987 Rev 2 to Design Criteria 3255-86-0004, TMI-2 Design Criteria for Pressurizer Defueling Sys. W/One Oversize Figure ML20236K9601987-07-24024 July 1987 Rev 3 to 3184-007, Solid Waste Staging Facility Sys Description ML20215M3261987-06-19019 June 1987 Rev 16 to Organization Plan ML20215H0301987-06-15015 June 1987 Revised Emergency Plan Implementing Procedures,Including Rev 2 to 6415-IMP-1300.06. Addl Assistance & Notification & Rev 1 to 6415-IMP-1300.16, Contaminated Injuries. Updated Table of Contents Encl ML20215M1291987-03-20020 March 1987 Corrected NCRP Commentary 4, Guidelines for Release of Waste - Water from Nuclear Facilities W/Special Ref to Public Health Significance of Proposed Release of Treated Waste Waters at Tmi ML20214S4481986-12-31031 December 1986 TMI-2 Cleanup Program,Post-Defueling Monitoring Storage ML20212N6711986-12-17017 December 1986 Rev 2 to Test Procedure SC-1302-323 Isolator - Fault Testing. Test Results Encl ML20212H7821986-10-10010 October 1986 Rev 7 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20206U7611986-09-26026 September 1986 Rev 1 to SD 3520-010, Div Sys Description for Processed Water Storage & Recycled Sys ML20205E7891986-08-0707 August 1986 Rev 0-03 to Corporate Procedure 1000-ADM-1291.01, Safety Review & Approval Procedure ML20211Q8251986-06-0202 June 1986 Rev 4 to SDD-TI-614, Div I Sys Design Description for TMI-1 Remote Shutdown Sys ML20203N1761986-04-29029 April 1986 Rev 4 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) 1999-08-12
[Table view] |
Text
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1670.6 '- -
Revision 2 1/16/78 THREE MILE ISLAND NUCLEAR STATION q- 3 STATION HEALTH PHYSICS PROCEDURE 1670.6
~
YOLUME I EMERGENCY PLANS AND PROCEDURES. Q' ~ 3 pn U' l~ A UU~ gL )\/
OFF-SITE RADIOLOGICA!. MONITORING "
l Table of Einective Pages -
hv 0V.
- Page Date Revision Pace Date Revision JO NOL Pace Date Reymon.
1.0 1/16/78 2 26.0 51.0 2.0 1/16/78 2 27.0 52.0 3.0 1/16/78 2 28.0 '
53.0 -
4.0 1/16/78 2 29.0 54.0 5.0 30.0 -
55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 .
13.0 38,0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 3, 18.0 -
43.0 68.0
/ 19.0 ' 44.0
45.0 70.0 21.0 46.0 71.0 ,
22.0 47.0 72.0 23.0 , '48.0 73.0 24.0 49.0 74.0 25.0 50.0 . }bl7 337 75.0 .~
Unit 1 Staff Recommends A val Unit 2 Staff Recommgnds val
- Approval ! Date Approval Date - -
Cognirap OS/HAad Cogniq/d Qehd Unit 1 PORC Recommenos Approval Unit 2 PORC Recommends Approval W DateY"N ~l? G5SE V/'thdtplan of PORC Date N ?
p Chairmanof PORC ,, ,
PORC comments of included PORC comments of -
induded (datej (data)
Date By If - Date -
D.By (M ,1 Approval Date
~
fY Appr I r _s//L s Date $ )),~ 7 8 Date 7-//-ve igt.,0 pe ional -
' 'E m 350 'W p'q'"
~.. 1670.5
- . Revision 2 1/16/78 ,
g THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHY, SICS PROCEDURE 1670.6 0FF-SITE RADIOLOGICAL MONITORING 4
1.0 OISCUSSION 3 During a Radiation Emergency (Site or General) where an accidental 1
release of radioactive material, an off-site monitoring team will provide radiological assessment data and in' formation. Conditions
'I at' the time of an occurrence will dictate specific areas where radiological efforts will be required. Since emergency situations are expected to produce high radiation le7els for a relatively short period of time, initial radiological assessment data is, required as soon as possible.
2.0 RADIOLOGICAL MONITORING I
2.1 Off-Site Radiation Monitoring Team - Airborne Release
]
2.1.1 An Off-Site Radiation Monitoring Team (RMT) shall be assigned at the Emergency Control Station and dispatched to the security
- search facility by the Radiation Protection Supervisor to obtain emergency monitoring equipment. ,
2.1.2 vCommunications will be established via walkie-talkie with the Emergency Control Station (ECS).
2.1.3 The RMT shall have the emergency mnitoring kits, air sampler, powerverter and walkie-talkie and proceed to location as, directed by the ECS. (Refer to monitoring map.) ,
2.1.4 At the location designated, perfom a dose rate survey of the -
general area. Record and relay data information to the Radiation-Protection Supervisor et the ECS. Wait for further instructions from the ECS. s g 33g 7
1.0
- *- 1670.6 Revision 2 1/16/78 2.1.5 If directed by the ECS to collect an air tample and detemine -
a radioiodine airborne activity concentration continue with the following:
2.1.6 Install the powerverter (DC/AC Converter) by connecting the positive (+) and negative (-) teminals to their respective-posts on the vehicles 12V DC battery.
2.1.7 Set the main circuit breaker switch and the selector switch to "on". (Red Neon Pilot Light indicates proper operation set-up).
2.1.8 Using the Radeco High Volume Air Sampler with a radiciodine sampler cartridge, connect to the powerverter.
2.1.9 Set selector switch to " variable" and adjust flow to indicate '
Sft 3/ minute and sample for 3 minutes to yield 15 ft3or 5x10 5 cc sampled air. (If S ft / 3minute cannot be obtained adjust
}
flow as high as possible and sample air long enough to yield 3
15 ft ). Record sample time and contact ECS for location outside of plume for sample counting.
2.1.10 The Eberline SAM-2/RD-19 Detector System (Dual-Single Channel Analyzer) will be used for counting the cartridge.
2.1.11 The SAM-2 will be powered by use of the battery pack which connects to the rear pane 1. Adjacent to this connection is the power switch and stabilizer switch to "on". BATT OK Light on front panel should be ON. If the light flickers or does not light, the AC power cord will be substituted for the -
battery pack.- The instrument is then connectr4 to the pcwerverter for AC power.
3 1817,339 2.0 s
. .,. 1670.6
. Revision 2
~
1/16/78 2.1.12 Control Circuitry should be set as follows:
- a. Ratemeter switch to " CHI" and selector switch to appropriate range. ('.e.X1,X10,etc).
t
- b. Scaler display switch to "0N" with count mode switches at 5, X1, timed. ,
,1
- c. The windows, thresholds, and HV ac(just controls should be i
checked for correct settings as indicated on the calibration sticker. I
- d. Threshold switches to "IN", window switches CHI "+", CH2 "Off".
- e. With the detector probe connected to front panel, push count reset - start switch for counting sequence.
2.1.13 Radiofodine Airborne Activity Concentration is calculated by:
i
._,}-
' , Net Counts / Minute pCi/cc = .
6 (Eff) (Volume) (2.2x10 )
EfficiencyispostedontheSAN-2 Analyzer.
2.1.14 : The cencentration data should be relayed to the ECS as spon as ,
possible, and wait for further instructions. ;
2.1.15 v The ECS may direct the monitoring team to do the following: .-
- a. If a continuous air monitor is located in the designated area, replace charcoal and particulate filters with clean filters and make gross radioactivity determinations, from
~
dirty filters. Retain dirty filters for precise laboratory analysis. -
- b. If TLD station is nearby, collect TLD and return it to the ECS for evaluation. Replace it with a new TLD.
1817 340 3.0 s
..",,, 1670.6
. .- Revision 2
- 'f 1/16/78
- c. Report results to Radiation Protection Supervisor.
- d. Place sufficient T1.D's at either the continuous air monitor or at a convenient, representative locaticn in the designated area to permit reading TLD's every four .
hours during the emergency.
Collect additional samples as specifically directed.
e.
2.2 Off-Site Radiation Monitoring Team - Liouid Release 5
24.1 When a reading of 6.8x10-3 pCi/ml (4.8x10 CPM)isindicated, a radiation monitoring team will be dispatched by the Radiation Protection Supervisor.
2.2.2 Water samples will be obtaired at the following locations:
- a. Discharge Monitoring Point
- b. York Haven Dam
~
g c. , City of Columbia
- d. Other points as designated by the Radiation Protection Supervisor 2.2.3 Samples will be analyzed to determine activity concentration. .
2.3 Washdown Area Monitor _
2.3.1 Decontamination of vehicles will be supervised by a Rad / Chem Technician at each of the washdown areas. (NorthWashdown Area -two miles north of the North Gate on Route 441 (Kiwanis Field adjacent to Swatara Creek). South Washdown Area - 3 miles south on Route 441 (Collins Substation).
2.3.2 Vehicles will be monitored prior to and following the washdown.
The vehicle will be released if the radiation level is less than 0.5 mR/hr. , .
. 4.0
January 18, 1980 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )
)
METROPOLITAN EDISON COMPANY ) Docket No. 50-289
) (Restart)
(Three Mile Island Nuclear )
Station, Unit No. 1) )
CERTIFICATE OF SERVICE I hereby certify that copies of " Licensee's First Set of Interrogatories to Intervenor Steven C. Sholly", were served upon those persons on the attached Service List by deposit in the United States mail, postage prepaid, this 18th day of January, 1980.
1 L
Robert y. Zahlsr Dated: January 18, 1980 1817 342
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )
)
METROPOLITAN EDISON COMPANY ) Docket No. 50-289
) (Restart)
(Three Mile Island Nuclear )
Station, Unit No. 1) )
SERVICE LIST Ivan W. Smith, sEsh John A. Ievin, Escuire Qiairman Assistant Counsel Atomic Safety and Licensing Pennsylvania Public Utility Cam'n Board Panel Post Office Box 3265*
U.S. Nuclear Pegulatory remnission Harrisburg, Pennsylvania 17120 Washington, D.C. 20555 Karin W. Carter, Esquire Dr. Walter H. Jordan Assistant Attorney General Atomic Safety and Licensing 505 Execative House Board Panel Post Office Box 2357 881 West Outer Drive Harrisburg, Pennsylvania 17120 Oak Ridge, 'Ibnnessw 37830 Febert L. Knupp, Esquire Dr. Linda W. Little Assistant Solicitor Atomic Safety and Licensing County of Dauphin Board Panel Post Office Box P 5000 Hermitage Drive 407 North Front Street Paleigh, North Carolina 27612 Harrisburg, Pennsylvania 17108 James R. Tourtellotte, Esquire John E. Mirnich Office of the Executive Iagal Director Omi m n, Dauphin County Board U. S. Nuclear Regulatory cerrmission of Ccrmissioners Washington, D.C. 20555 Dauphin County Courthouse Front and Market Streets Docketing and Service Section Harrisburg, Pennsylvania 17101 Office of the Secretary U. S. Nuclear Regulatory Ccnmission Walter W. Cbhen, Esquire Washington, D.C. 20555 Consumr Advocate Office of Censumer Advocate 14th Floor, Strawberry Square Harrisburg, Pennsylvania 17127 1817 343
Jordan D. Cunningham, Esquire Pobert Q. Pollard Attorney for Newberry 'Ibwnship Chesapeake Energy Alliance T.M.I. Steering Coninittee 609 Mcntpelier Street 2320 North Second Street Baltincre, Maryland 21218 Harrisburg, Pennsylvania 17110 Chauncey Kepford Theodore A. Adler, Esquire Jtriith H. Johnsrud Widoff Peager Selkowitz & Adler Environmental Coalition on Nuclear Post Office Box 1547 Power Harrisburg, Pennsylvania 17105 433 Orlando Avenue State College, Pennsylvania 16801 Ellyn R. Weiss, Esquire Attorney for the Union of concerned Marvin I. Iewis Scientists 6504 Bradford Terrace Sheldon, Harnen & Weiss Philadelphia, Pennsylvania 19149 1725 Eye Street, N.W., Suite 506 Washington, D.C. 20006 Marjorie M. Aanedt R. D. 5 Steven C. Sholly Cbatesville, Pennsylvania 19320 304 South Market Street Machanicsburg, Pennsylvania 17055 Gail Bradford Holly S. Keck Iegislation Chainran Anti-Nuclear Group Pepresenting York 245 West Philadelphia Street York, Pennsylvania 17404 Karin P. Sheldon, Esquire Attorney for People Against Nuclear Energy Sheldon, Harnon & Weiss 1725 Eye Street, N.W., Suite 506 Washington, D.C. 20006 s
1817 344