Similar Documents at Hatch |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20106A6521992-02-29029 February 1992 Proposed Rev 3 to Ei Hatch Nuclear Plant Solid Radwaste PCP, Per GL 89-01 ML20106A6501992-02-0707 February 1992 Rev 7 to Ei Hatch Nuclear Plant ODCM, Reflecting Proposed Changes,Per GL 89-01 ML20056B3031990-08-0101 August 1990 Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval ML20149N1141988-01-0404 January 1988 Revised Second 10-Yr Interval Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20211H5491987-02-20020 February 1987 IGSCC-Susceptible Primary Pressure Boundary Stainless Steel Piping & Components Insp/Mitigation Program, 1987 Maint/Refueling Outage ML20245B8301986-12-10010 December 1986 Rev 0 to SO-OPS-05-1286, Spent Fuel Pool Transfer Canal Gates ML20245B8171986-12-0505 December 1986 Rev 0 to SO-OPS-02-1286, Processing of Water from Yard Drains ML20245B8201986-12-0505 December 1986 Rev 0 to SO-OPS-01-1286, Radwaste Discharges. Supporting Documentation Encl ML20203L9291986-08-0101 August 1986 Rev 0 to Training Procedure 72TR-TRN-002-0S, License Requalification Training Program ML20137V9031985-12-0505 December 1985 Rev 1 to Emergency Implementing Procedure 62RP-RAD-009-05, Airborne Radioactivity Concentration Determination ML20076J1871985-11-0808 November 1985 Rev 2 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp for Georgia Power Co ML20076J1911985-11-0404 November 1985 Rev 1 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20076J1961985-10-23023 October 1985 Rev 0 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20135F3161985-08-26026 August 1985 Rev 1 to Emergency Operating Procedures Implementation Plan for Emergency Response Capability Project ML20132E5471985-08-23023 August 1985 Rev 0 to Engineering Svc Procedure 42EN-ENG-011-OS, Scram/ Transient Reporting ML20209F2391985-07-0101 July 1985 Recirculation,Rhr & Reactor Water Cleanup Sys Piping Weld Joint Insp/Mitigation Program for 1985 Maint/ Refueling Outage ML20128A0561985-06-25025 June 1985 Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20126E8331985-06-11011 June 1985 Emergency Plan Implementing Procedures & Deleted Title Sheets,Including Procedures HNP-8007 Re Decontamination of Clothing & Hats & HNP-8004 Re Dosimetry Issuance & Tracking ML20116D4401985-04-23023 April 1985 Revised Emergency Procedures HNP-8109 Re Continuous Air Monitors Models AM-3D & AM-33-1,HNP-8122 Re Radiation Monitor Model RM-16 & HNP-8146 Re Rascal Portable Rate Meter-Scaler/Model PRS-1 Operation & Calibr ML20245B7911985-04-17017 April 1985 Rev 0 to 10AC-MGR-04-0, Deficiency Control Sys. Supporting Documentation Encl ML20107G1421985-02-15015 February 1985 Revised Emergency Implementing Procedures,Including Rev 3 to HNP-8161 Re Eberline Model PCM-1 Portable Monitor Operation & Calibr & Rev 2 to HNP-8036 Re Waste Classification & Manifest Reporting Resin Shipments ML20215F7371984-12-26026 December 1984 Rev 1 to Administrative Control Procedure 40AC-FPX01-0, Fire Protection Program. Portions of Procedures 34AB-OPS-056-1S & 34AB-OPS-056-2S Encl ML20101B0551984-12-17017 December 1984 Rev 5 to Emergency Plan Implementing Procedure HNP-8134, Whole Body Counter Sys ML20108E0921984-11-29029 November 1984 Rev 10 to Procedure Data Package HNP-1-3980-1, Kinemetrics SMA-3 ML20107H5701984-10-31031 October 1984 Detailed Control Room Design Review Program Plan ML20155C8961984-09-30030 September 1984 Rev 1 to Offsite Dose Calculation Manual ML20155C8841984-09-30030 September 1984 Rev 1 to Solid Radwaste Process Control Program ML20098G3401984-09-30030 September 1984 Offsite Dose Calculation Manual ML20098G3381984-09-30030 September 1984 Solid Radwaste Process Control Program ML20108E0741984-06-13013 June 1984 Rev 10 to Procedure HNP-1-3980-M, Seismic Instrumentation Functional Test & Calibr ML20084H4971984-05-0101 May 1984 Rev 0 to Procedures Generation Package for Emergency Operating Procedures,Including plant-specific Technical Guidelines for Units 1 & 2,plant-specific Writers Guide & Implementation Plan for Emergency Response Project ML20086U4131984-02-29029 February 1984 Vendor Equipment Technical Info Program, Per Generic Ltr 83-28,Section 2.2.2,final Draft ML20087N9101984-01-26026 January 1984 Public Version of Transmittal & Title Page to Deleted Emergency Plan Implementing Procedures,Including Procedure HNP-8031 Re Determination of Specific Activity of Spent Resin & Curie Contents of Liner & 840322 Memo ML20087M7911984-01-25025 January 1984 Public Version of Transmittal & Title Pages of Deleted Emergency Plan Implementing Procedures HNP-8019, Insp of Steel Radwaste Shipping Drums & HNP-8422, Handling & Loading of Chem-Nuclear Cask & 840322 Memo ML20087M9321984-01-20020 January 1984 Public Version of Rev 7 to Emergency Plan Implementing Procedure HNP-8101, Teletector Model 6112B/D Operation & Calibr & Jm Felton 840322 Release Memo ML20081B6731984-01-18018 January 1984 Public Version of Rev 0 to Emergency Plan Implementing Procedure HNP-8161, Eberline Model PCM-1 Portal Monitor & Rev 17 to HNP-8008, Radiation Work Permit & Jm Felton 830307 Release Memo ML20087P0191984-01-13013 January 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8038 Re Waste Classification & Manifest Reporting & HNP-8042 Re Radiological Work Practices & 840326 Memo ML20079H9011983-12-0707 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8035 Re Pulmonary Function Screening Program & HNP-8016 Re Shipment of Radioactive Matl ML20093D4881983-10-31031 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including HNP-4858, Naturally Occurring Phenomenon & HNP-8108, Pocket Dosimeter Use & Performance Test. W/831031 & 840709 Release Memo ML20108E0491983-10-28028 October 1983 Rev 4 to Procedure HNP-4858, Naturally Occurring Phenomenon ML20080L0651983-10-12012 October 1983 Rev 1 to Procedure HNP-4848, Determination of Extent of Core Damage Under Accident Conditions ML20081L9461983-10-12012 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4827 Re Offsite Radiological Environ Monitoring During Emergencies & HNP-4852 Re Offsite Dose Estimation 1998-04-30
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PROCEDURE Actions for All Personnel in Site' Area Fmergener PROCEDURE TITLE HNP-4621 PROCEDURE NUMBER .
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APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 2 Pages 1, 2&3 Deletion on Page 1 Page 5 deleted j
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- Georgia Power n ..o ~o See Title Paqe 1 of 4 ACTIONS _FOR ALL PERSONNEL IN SITE AREA EMERCENCY NOTE ,
This procedure supercedes HNP-4600 Revisibn 8 dated 8-1-80.
A. CONDITIONS Events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary.
B. REFERENCE HNP-4620.
- C. ACTION
- 1. Persons discovering an emergency condition shall immediately
_ notify the control room by the most expeditious means available.
- 2. Control room operators shall announce the nature of the emergency on the public address system and specify that personnel initiate site area emergency procedures.
- 3. Control room operators shall place the plant in a safe condition as the emergency warrants. ,
- 4. If possible, person (s) in immediate area take appropriate rapid action to limit the extent of the inciifent with available means, and then retreat to the rally point. ,
S. Persons involved in the incident report to Health Physics at the Emergency Operations Facility as soon as possible after decontamination for further evaluation of dose received.
I
- 6. Persons called in from offsite should report to the Emergency Operations Facility unless specifically directed otherwise.
- 7. Staffing of the Emergency Operations Facility (EOF) shall begin immediately. The normal EOF is the Visitor's Center; the alternate EOF is the Appling County Sheriff's office in the courthouse.
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- 8. If the emergency occurs during a regular day shift, members of the plant operating organization on site will report as follows:
- a. Control Room .
Operations Supervisor - All oh shift operators, Shift Foreman, Shift Supervisor and Shift Technical Advisor.
- b. Emergency Operations Facility The following persons will report to the E.O.F. after checking through the rally point.
Assistant Manager, H.P. Superintendent, Administrative Superintendent, RET members, 4 communicators.
Three RET members will be dispatched immediately by the OSC Manager to report to the EOF.
One or more RET members will be dispatched immediately to Gate 1 by the Rally Point Leader to frisk workers who are outside the primary protected area.
- c. Technical Support Center (T.S.C.)
The following persons will report directly to the T.S.C. following notification of a Site Area Emergency.
Assistant Manager, Superintendent of Engineering Services, Superintendent of Maintenance, Superintendent of Operations, Reactor Engineer, Engineering Supervisors, Laboratory Supervisor (Health Physics), 4' communicators.
~
- d. Operations Support Center (O.S.C.)
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, The following persons will report directly to the j O.S.C. following notification of a Site Area Emergency.
1 Maintenance Supervisor, 1 crew instrument technicans w/ foreman (pre-designated), 1 crew electricians w/ foreman (pre-designated), 1 crew mechanics w/ foreman (pre-designated), all R.E.T. members and four laborers
! with foreman (predesignated).
. 9. All personnel who have not been assigned to the control room, TSC, O.S.C. or E.O.F. will evacuate the site per step 12 or 13.
- 10. Members of the plant organization will comply with applicable procedures to effect orderly coordinated actions in the emergency.
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- 11. Members of the Radiological Emergency Team report to the OSC immediately if on site when the emergency begins. If team
. members are called in, they report to the EOF for -
assignments. .
- 12. Evacuation _grocedure for personnel-inside the primary protected area:
- a. Proceed to the area just inside the fence at the exit designated by the announcement over the Public Address System. .
- b. Proceed to drop off all identification badges at the Security post and continue to the Environmental Building or the Skills Training Building as directed by the Rally Point Leader. All personnel that were involved in the accident or are wearing PC's will not leave the protected area.
. c. Frisking and decontamination will take place at either of these locations as directed by the Rally Point Leader. Once this is completed, the RET will direct personnel to leave the plant site.
- d. Personnel should leave the site vicinity in personal vehicles using US 1. Direction of travel (north, south, either direction) will be announced by the Control Room and will be based on wind direction.
. e. If required, company vehicles will be used to supplement transportation needs. .
- 13. Evacuation procedure for personnel outsiUetheprimary protected area:
- a. Proceed to the Rally Point indicated by Control Room
( personnel over the Public Address Systems.
NOTE If the rally point must be moved because of high background radiation, follow instructions of the R.E.T.
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- b. Get checked for- contamination by GPC Radiological Emergency Team personnel at Gate 1.
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- c. If contaminated, go to area designated by surveyor and await decontamination.
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- d. Personnel in Section C.8.b report to E.O.F. ,
- e. Personnel will leave the site vicinity using U.S. 1.
Direction of travel (north, south or either) will be announced by the control room and,will be based on wind direction. .
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