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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17352A3821993-12-28028 December 1993 Third Ten-Yr ISI Interval IST Program for Pumps & Valves. ML17353A7621992-12-28028 December 1992 Pre-fire Plan Guidelines & Safe Shutdown Manual Actions. ML17349A7491992-12-0808 December 1992 Revised Odcm. ML17349A3711992-05-21021 May 1992 Rev 10 to Procedure PT-51-WS, Solidification Process Control Procedure. ML17349A2511992-03-27027 March 1992 Rev 0 to Pc/M 91-128, 480 Volt Undervoltage Protection Scheme Mod for Unit 3 ML17348B4121991-10-22022 October 1991 Health Physics Procedure 0-HPS-042.8, Dewatering Controls for Radwaste Liners. ML17348A2801990-05-31031 May 1990 Rev 1 to Emergency Power Sys Enhancement Project Testing Rept. ML17348A5381990-02-13013 February 1990 Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17347B4891989-12-18018 December 1989 Administrative Procedure AP 11550.92,Health Physics Procedure HP-92, Emergency Radiation Team Response - Offsite. W/891218 Ltr ML17347B3681989-10-0202 October 1989 Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves, Rev 2 ML17347B2851989-08-17017 August 1989 Change a to Rev 1 to JNS-PTN-200, Second Ten-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17347B2951989-03-21021 March 1989 Procedure 3-EOP-ECA-0.1, Turkey Point Nuclear Plant Unit 3 Loss of All AC Power. ML17348B4131988-03-10010 March 1988 Rev 8 to Procedure PT-51, Solidification Process Control Procedure. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17342A9971987-10-26026 October 1987 Procedure 0-ADM-019, Mgt on Shift. ML17342B0191987-10-24024 October 1987 Procedure 0-ADM-019, Mgt on Shift (Mos), Weekly Summary Rept for Wk Starting 871024 ML17342A8141987-07-24024 July 1987 Draft Revs to Procedures Generation Package. ML20076H2831987-05-31031 May 1987 Rev 0 to Technical Note 51187, Procedures for Repairing Prefabricated Panel & Preshaped Conduit Section Fire Barriers Installed at Plant ML17347A3081987-01-26026 January 1987 Emergency Procedure EP 20109, Criteria for & Conduct of Local Evacuations. ML17347A3071987-01-26026 January 1987 Emergency Procedure EP 20107, Fire/Explosion Emergencies. ML17347A2241986-12-22022 December 1986 Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr ML17342A9111986-11-18018 November 1986 Off-Normal Operating Procedure 3208.1, Malfunction of RHR Sys. ML20215L8241986-09-23023 September 1986 RCS Pressure Boundary Check Valves 4-874A & B Leak Test, for Unit 4 ML20215L7031986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-3-750 &/Or MOV-3-751 Leak Test, for Unit 3 ML20215L7881986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 3 ML20215L7791986-09-23023 September 1986 RCS Pressure Boundary Valves MOV-4-750 &/Or MOV-4-751 Leak Test, for Unit 4 ML20215L8001986-09-23023 September 1986 RCS Pressure Boundary Check Valves Leak Test, for Unit 4 ML20215L8191986-09-23023 September 1986 RCS Pressure Boundary Check Valves 3-874A & B Leak Test, for Unit 3 ML20076H4411985-11-0606 November 1985 Rev 4 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4491985-10-11011 October 1985 Rev 3 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Precedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4531985-09-20020 September 1985 Rev 2 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20199E4531985-08-23023 August 1985 Off-Normal Operating Procedure 9408.2, Energizing 4 Kv Buses Using Cranking Diesels Bus Tie Lines or Startup Transformer from Opposite Unit ML20199E4611985-08-23023 August 1985 Off-Normal Operating Procedure 7308.1, Malfunction of Auxiliary Feedwater Sys ML20199E4111985-08-22022 August 1985 Operating Procedure 7201.1, Standby Steam Generator Feedwater Sys - Operating Instructions. Related Info Encl ML20199E4321985-08-22022 August 1985 Off-Normal Operating Procedure 9408.3, Loss of Voltage to 'C' 4,160 Volt Bus ML20076H4611985-03-28028 March 1985 Rev 1 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Power Corp,Turkey Point Npp ML20076H4721985-03-15015 March 1985 Rev 0 to Technical Note 20684-TP, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Nuclear Plant Applications Prepared for Bechtel Powecorp,Turkey Point Npp ML17346A8291985-02-0404 February 1985 Procedures Generation Package. ML17346A6701984-12-31031 December 1984 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents. ML17346A5621984-09-26026 September 1984 Revised Emergency Operating Procedures,Including O-ADM-110 Re Verification Guideline for Emergency Operating procedures,O-ADM-111 Re Emergency Procedure Validation Plan & Procedures Generation package.W/841001 Ltr ML17346A5391984-09-0101 September 1984 Emergency Plan Implementing Procedure 1107, Duties of Emergency Planning Supervisor,Offsite Emergency Organization. ML17346A5401984-09-0101 September 1984 Emergency Plan Implementing Procedure 1211, Activation & Use of Emergency News Ctr (Turkey Point),Offsite Emergency Organization. 1998-08-27
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Text
FLORIDA POWER ANO LIGHT COMPANY TURKEY POINT UNITS 3 ANO 4 EMERGENCY PROCEDURE 20125 SEPTEMBER 8 1983 1.0 Tit1 e:
ON-S ITE EMERGENCY ORGANIZATION 2.0 Ao royal and List of Effective Pa es:
2.1 ~Ap roval:
Change dated 9/8/83 Reviewed by PNSC Seotember 8 1983 Approved by Plant Mgr-Nuclear, M>> 19<89 Approved by Vice President of Nuclear Energy HZ'3&
2.2 List of Effective Pa es:
Pa<ac Date ~Pa e Date ~Pa e Date ~Pa e Date 1 9/8/83 2 9/8/83 3 9/8/83 4 9/8/83
3.0 Scone
3.1 ~Pur oae:
This procedure describes the members and duties of the On-Site Emergency Or gani tati on. JOELETEOI 3.2 Di scussi on:
During the period immediately following the declaration of an emergency,.the shift operating staff constitutes the irrmediate response organization, i.ee e the Interim Emergency Teams. Emergency requirements take immediate precedence over normal operating responsibilities (as determined by Emergency Procedures or at the direction of the Emergency Coordinator) .
Subsequent to the iomediate response actions and notifications, other plant staff will begin arriving to form the Primary Emergency Teams and to staff the Technical Support Center. The On-Site Emergency Organization reports to and supports the Emergency Coordinator.
3.3 ~Author it Turkey Point Plant IRadiolooical Emergency Plan 83ii2i0074 83iii0 PDR ADQCK 05000250 '
PDR
! 0 il f 9/8/83 EMERGENCY PROCEDURE 20125, PAGE 2 ON-SITE EMERGENCY ORGANIZATION
3.4 Definitions
3.4. 1 Emer enc Coordinator:
Responsible for notifying off-site authorities, both inside and outside the Company and has full authority and responsibility for on-site emergency response actions. This function is performed by the JP'lant Supervisor - ~Nuclear . A member of the plant management staff may assume thi s function at their discretion. (See Emergency Procedure 20101, Duties of Emergency Coordinator).
3.4.2 Interim Emer enc Teams:
The Interim Emergency Teams are composed of members chosen from plant shift personnel. All are qualified in procedures and practices required for the performances of their duties as team leaders or members.
3.4.3 Primar Emeroenc Teams:
The Primary Emergency Teams are composed of first line management personnel and others who normally work on the regular day work schedule, which is also exclusive of weekends and holidays.
3.4.4 Technical Su port Center Su ervisor:
The person designated by the Emergency Coordinator to supervise the personnel and manage the technical support activities in the Technical Support Center. This function is performed by one of the following:
Operations Superintendent - Nuclear Operations Supervisor - Nuclear Technical Department Supervisor Other department supervisors (if necessary)
4.0 Precautions
- 4. 1 The Interim Teams should take action regardless of the fact that the Primary Emergency team members may be present.
Members of an Interim Emergency Team may consider themselves relieved ~onl upon the specific instructions of a recognized superior or the Primary Emergency Team Leader. Merely knowing that a superior or a Primary Emergency Team Leader is present does not constitute a release from emergency duties and responsibilities.
4.2 At their own option, and with the knowledge of the Emergency Coordinator, line management members of that team may relieve their counterpart on the Interim Emergency Teams.
J 9/8/83 EMERGENCY PROCEDURE 20125, PAGE 3 ON-S ITE EMERGENCY ORGAN IZATION 5.0 Res pons ibi i ties:
1 5.l Emer enc Direction and Control:
The Emergency Coordinator shall be responsible for direction and control, as described in Emergency Procedure 20101, Duties of Emergency Coordinator.
5.2 Notification and Communication:
The Emergency Coordinator shal 1 be responsibl e for noti fication and communications as described in Emergency Procedure 20101, Duties of Emergency Coordinator.
5.3 Radiation Team:
The Health Physics Supervisor shall be the Radiation Team Leader. He shall direct the actions of the Health Physics technicians under the orders of the Emergency Coordinator. Tne Interim Radiation Team Leader is designated as the Health Physics Technician on shift with the Nuclear lÃatch Engineer as his alternate.
5.4 Plant S stem En ineerina:
The Shift Technical Advisor shall provide the initial technical support necessary for repair or corrective actions.
5.5 Fire Team:
h The Nuclear Match Engineer ~l(NWE I shall be the Fire Team Leader. igther designated Nuclear Operators, nho are leader qualified, may also act as Fire Team Leader if the NME is not availablel.
This position is manned continuously but i he is not available the Nuclear Turbine Operator shall act as his alternate.
5.6 First Aid/Decontamination Team:
The Plant Radiochemist shall be the Primary Team Leader with the Chemistry Supervisor as his alternate. A Nuclear Operator, trained in first aid and personnel decontamination, shall be the Interim Team Leader. I no Chemistry Department personnel are availablel, any trained employee could act as a First Aid/Decontamination Team member until primary team members can be called in.
5.7 Securit Team:
The Security Supervisor shall be the Primary Security Team Leader with the Assistant Plant Security Supervisor as his alternate. The Security Shift Supervisor shall act as the Interim Security Team Leader. Personnel control and accountability are the responsibility of the Security Team. The Security Team Leader shall be responsible sor notifying the Emergency Coordinator of unaccounted aor personnel. Notification of occupants in the Owner Controlled Area shall take place during the security search.
~'
9/8/83 EMERGENCY PROCEDURE 20125, PAGE 4 ON-S ITE EMERGENCY ORGANIZATION 5.8 Rescue Team:
Rescue Operations shall involve the First Aid/Decontamination Team and the Radiation Team as necessary. Under the control of the Radiation Team Leader, entry to potentially hazardous areas shall be made by the First Aid/Decontamination Team with assistance from the Radiation Team. Upon notification of the injury, both teams shall respond per the Emergency Coordinator's instructions.
5.9 Recover and Restoration Team:
The Operations Superintendent - Nucl ear shal 1 be the Team Leader. The Technical Department Supervi sor i s the al ternate. Team members shal 1 be assigned from available plant staff.
5.10 ~Re Ent-r Re-entry teams shall be formed as necessary in accordance with Emergency Procedure 20111, Re-Entry.
6.0
References:
6.1 Turkey Point Plant Emergency Plant 6.2 Emergency Procedure 20101, Duties of an Emergency Coordinator
- 7. 0 Records:
The Emergency Coordinator shal 1 maintain records as described in Emergency Procedure 20101, Duties of the Emergency Coordinator.
8.0 Instructions
8.1 Upon declaration of an emergency, the Interim Team Leaders shall contact the Emergency Coordinator to determine the inmediate response teams needed.
Be 2 The Shi ft Technical Advisor shall assist the Emergency Coordinator in evaluating the emergency.
8.3 The Emergency Coordinator shal 1 ini ti ate the noti ficati ons described in Emergency Procedure 20101 to inform necessary plant management and Emergency Team Leaders.
8.4 The Technical Department Supervisor shall report to the Technical Support Center and act as the TSC Supervisor. The personnel in the TSC shal 1 provide plant management support to allow the Iplant Supervisor - ~lluclear to concentrate on reactor control.
8.5 The Emergency Coordinator shall provide watch relief as conditions require changes.
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October 28, 1983 L-83-540 Mr. James P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street NM, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Emer enc Plan Im lementin Procedures In accordance with 10 CFR 50, Appendix E, enclosed is one copy of Emergency Plan Implementing Procedure:
Number Title 20125 On-Site'mergency Organization.
Two copies of this procedure have been forwarded to the Document Control Desk by copy of this correspondence.
Very truly yours,
<),',/pl/:Wu ur
/
J. M. Williams, Jr.
Vice President Nuclear Energy Department JWW/RDM/js Attachment cc: Document Control Desk (2 copies of enclosure)
Harold 'F. Rei s, Esquire PNS-EP-83-82
REGULATUll4f OITRATI;ON DISTRISUTIORi +TEIL (lrIDS)
ACCESSION NbH;~~~~ OUC ~ DATE:
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SUBJECT:
Central Files version of Emergency Pllan Implementing Pr oceaure 20!12Sg "Or>si te Emerqency Organi zat ion" w/831026 ltd DISTRIBUTION CODE:, XOO'&S COPIES RECEIVED:LTH , Ei CL . SIZE:
Emerg Plan (CF avail)
II'ITLE:
NOTES:
PEG IP IENT IES
'ECIPIENT Id GOOK/lAIAME COPIES I TlR ENCL ID CODh/i'vAr E COP LTTR ENCL NRH OHbl SC 0 McD0!'~ALD.O V1 1 1 INTERIATAI llS 1 1 FERA TECH HAZ09 1 1 IE/DEPER/KPB 03 2 'I E./CE PER /IRAN 1 1 NRR/DS I/AE6 1 1 NHR/IDSI/RAt3 1 0 HEr'ILES 07 1 1 TOTAL I'IVIES'fiER OF COPIES HErjU jRE;"); LTTR 10 ENCL