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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20035F2071993-02-15015 February 1993 Rev 0 to HS-EP-02850, Hazardous Chemical & Oil Spills ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint 1998-08-28
[Table view] |
Text
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r THE. TOLEDO EDISON COMPAhT DAVIS-BESSE NUCLEAR POWER STATION IMERGENCT PLAN h 6 G PROCEDURES REVISION INDEI 1
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PAGE REVISION PROCEDURES REVISION TEMPORARY MODIFICAT*.'NS j
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EI 1300.00 2
3 EI 1300.01
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EI 1300.02 2
EI 1300.03 EI 1300.04 2
2 EI 1300.05 EI 1300.06 2
EI 1300.07 2
EI 1300.08 3
EI 1300.09 1
EI 1300.11 1
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EI 1300.12 1
T-5850, T-5918 i
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August, 1982 Y'
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8209160097 820826 PDR ADOCK 05000346 F
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EI 1300,11.0 Davis-Besse Nuclear Power Station j
i Unit No. 1 Emergency Plan Implementing Procedure EI 1300.11 Recovery e
Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date A
Submitted by C.
E. Wells 6/13/80 Section Head Date Recommended by MI/M 6/3b 3
SRB Chairman
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bate QA Approved 4 /M Quality' Assurance Manager Date Approved by N
'8b Stat' ion Superintendent []
Date Revision SRE QA Sta. Supt.
No.
Recommendation Date Approved Date Approved Date j G y.< w *5n &
7l1sltLNA Y
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1 EI 1300.11.1 1.
PURPOSE
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To outline the course of action for placing the plant in an antici-1 pated recovery condition following a plant event which required activation of the Station Emergency Plan.
2.
SCOPE Describes the actions and responsibilities of Davis-Besse and of fsito support groups in activitics after the Station Operations Manager and Emergency Duty Officer have jointly declared that the emergency situation is stable and the Station is ready to enter recovery phase activities.
2.1 The actual magnitude of event recovery will dictate the extent of personnel involvement in the recovery operation.
t 2
2.1.1 For events of a minor nature, the normal on-shift organization should be adequate to perform
. j necessary recovery actions (i.e. for Unusual J
Event classifications).
1 2.1.2 For events involving significant damage to plant systems required to maintain operation of the plant, the on-site emergency organization should ho adequato Lo coordinato the nucussary recovery
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.i actions (i.e. for Alert classifications.)
1 2.1.3 For events involving damage to plant systems
~l required to maintain safe shutdown of the reactor the off-site emergency organization should be adequate to manage the necessary recover actions
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(L.u. for Sitn or General Emergency classifica-Lions).
2.2 The Station Operations Manager, under the direction of thu Operations Director, shall be responsible at the site for authorizing the start of reentry, recovery, and rustoration activities; and the return to normal operations, r
3.
ljEFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 4
DEFINITION 4.1 Recovery Actions - Those actions taken after an emergency to restorn Lhn Station as nearly as possihiu Lo pru-umurgency conditions.
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2 EI 1300.11.1
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5.
RECOVERY PROCESS i
5.1 Initial Conditions j
5.1.1 Plant conditions are abnormal, but appear stabilized following an event requiring activation of the l
Emergency Plan.
- a. The plant is in a shutdown condition with
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adequate core cooling.
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- b. In plant radiation levels are stable and decreasing with time.
- c. The release of radioactive material to the environment is controlled and there is no significant potential for additional uncontrolled releases.
- d. Fire, flooding, or similar emergencies are under control.
5.2 Recovery Requirements 5.2.1 Hoontry activities have been completed as s,
required by the Reentry Procedure, EI 1300.10.
LJ 5.2.2 Plant and TECo personnel have been assigned activities under the direction of the Emergency
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Duty Officer through approval of the Recovery Director and Operations Director.
5.2.3 Special team members are NOT designated prior to the initiation of this procedure but should be
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selected from available personnel based on cxperionen and training.
5.3 Recovery Considerations 5.3.1 Particular attention shall be dire'cted towards isolating components and systems as required to control or minimize the hazards.
5.3.2 A systematic investigation shall be conducted to
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dnterminn thn equipment that has bocn damagnd and the extent of the damago.
lJ 5.3.3 A detailed investigation of the accident causes 1
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3 EI 1300.11.1
.q
'S-and consequences both to the plant and the environment shall be conducted.
s 5.3.4 Determinations shall be made as to the repair work required to perform necessary modifications to plant equipment and/or operating procedures.
5.3.5 Repair work and approved modifications shall be carried out as required by existing or prepared procedurcs.
5.4 Radiological Considerations 5.4.1 Normal Itmits of occupational exposure shall be applied during recovery since no emergency is considered to exist.
5.4.2 Compliance with the limits shall be the res-ponsibility of the Recovery Director through the Chemist and Health Physicist.
5.4.3 Recovery operations that may result in the release of radioactive materials shall be ovaluated by the Recovery Director and his staf f as far in advance as possible.
5.5 Procedura 5.5.1 The Shift Supervisor shall direct any necessary recovery actions that are minor in nature (i.e.,
through normal maintenance work requests),
- n. Ropair work and approved procedure modifications shall be carried out as required by' existing procedures.
1 4
- b. Reports on the cause and reparation of the event shall be made as required by existing station or regulatory procedures (i.e.,
licensee event report or deviat' ion report, etc.)
5.5.2 If the event involves significant damage to plant systems, the responsibility for recovery nctions should be shif tml to the TSC.
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- a. The Station Superintendent, Outage Management becomes the Recovery Manager and recovery actions involving significant plant repair, including:
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4
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i 1
4 EI 1300.11.1 1.
Re-entry into affected areas of the plant
~~'f as per EI 1300.10.
_/_,
I 2.
Modifying plant equipment and/or operating i
procedures.
3.
Initiating appropriate system tests to verify the plant's capability to return to service.
I
- b. All emergency procedures shall be closed out or have an individual assigned to them for completion and closure.
- c. All activated emergency response or support organizations shall be notified in recovery situation and subsequently of its termination.
5.5.3 If the eve.t involves damage to plant systems impairing the ability to maintain safe shutdown for protection of the public, recovery responsibility
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should be shifted to the EOF.
1
- a. The Recovery Manager under the authority of the Engincaring Support Director, shall develop, coordinato, and expedite plans and f"3 R schedules for recovery operation, k;>_j
- b. A long-term recovery organization shall be established to coordinate all recovery operations.
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- c. A detailed investigation of the accident cause and consequences both of the plant and the I) onvironment will be conducted.
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- d. Any discharges will be controlled as per plant
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or regulatory limits.
- c. Special procedures for decontamination and
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repair, installation and operation of backup systems, inspections and tests necessary to
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assure plant integrity and the adequate repairs, waste handling and processing, and
.)
ALARA considerations will be developed and J
implemented.
NOTE:
As necessary, a technical review group will be identified in the development of the recovery organization, as well as the individual (s) having J
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5 EI 1300.11.1 1
final signature authority on all procedures.
- f. Process and administer any additional support services for personnel, legal counseling, and special funding requirements.
I
- g. Any procedural waivers granted during the emergency phase shall be either terminated or documented through appropriate procedural modifications,
- h. To the extent possible, applicable limiting conditions for operation and surveillance requirements of the plant Technical Specifications shall be complied with.
NOTE:
For those conditions and surveillances in which compliance is Lnpractical, the NRC shall be informed and consulted with regarding safety implications of continued operation in that mode.
- i. Applicablo off-sita agencies shall be notified
.,)
of recovery organization and activity changes and subsequently of its. termination.
- j. Any necessary restoration activities shall be implemented to prepare for resumption of full
.m power operating, including:
1 1.
Disposal of all waste generated during the emergency.and recovery phases.
m 2.
Elimination of potential effects of the emergency on future plant operations.
0 3.
Training of plant operations, Shift Technical Advisors, and other applicable individuals on changes that occurred to the plant ouring the emergency outage.
4.
Replenishment of any emergency equipment or consumabic materials.
- k. If recovery and restoration efforts cannot restore the plant to an operable status, a
-d O
6 EI 1300.11.1 decommissioning organization shall be established PJ to shutdown the plant to a safe long-term
.h condition.
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5.6 Final Conditions 5.6.1 A recovery organization has restored the plant to its pre-emergency status, to a modified pre-emer-gency status capable of power operations, or to a decommissioning status.
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END
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