Public Version of Facility Emergency Implementation Procedure, Recovery - EofML19343B038 |
Person / Time |
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Site: |
Farley |
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Issue date: |
11/06/1980 |
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From: |
Harriston W ALABAMA POWER CO. |
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To: |
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Shared Package |
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ML19343A898 |
List: |
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References |
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FNP--EIP-20-1, FNP-0-EIP-20-01, NUDOCS 8011240515 |
Download: ML19343B038 (7) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205S9641999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20205A3101999-02-28028 February 1999 Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20196F6261998-12-0101 December 1998 Proposed Tech Specs Pages Re Amend to Licenses NPF-2 & NPF-8.Proposed TS Changes Include Revisions to SG Level Setpoints,Rcs Operational Leakage & Specific Activity Limits & SG Tube Insp Program ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20151V6991998-09-11011 September 1998 Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20212B1791997-10-31031 October 1997 1 SG ARC Analyses in Support of Full Cycle Operation ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20198T4921997-03-31031 March 1997 Small Bobbin Probe (0.640) Qualification Test Rept ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems 1999-06-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20138A3661996-04-25025 April 1996 Rev 15 to Procedure FNP-O-M-011, Offsite Dose Calculation Manual ML20071P9561994-06-15015 June 1994 Rev 1 to FNP-0-ETP-4338, Svc Water Storage Pond Sounding Survey ML20071Q2831994-03-0808 March 1994 Rev 1 to FNP-0-ETP-4381, Svc Water Storage Pond Piezometer Well Readings ML20071Q3151994-03-0808 March 1994 Rev 1 to FNP-0-ETP-4389, Svc Water Storage Pond Dam Biennial Insp ML20063H7681994-01-0101 January 1994 Rev 13 to Odcm ML20071Q3551993-10-18018 October 1993 Rev 7 to FNP-0-ARP-8, Svc Water Structure ML20071Q3661993-07-13013 July 1993 Rev 26 to FNP-1-ARP-1.1, Main Control Board Annunciator Panel a ML20071Q3751993-06-24024 June 1993 Rev 8 to FNP-0-AOP-31.0, Loss of Svc Water Pond ML20071Q3341993-01-29029 January 1993 Rev 0 to FNP-0-ETP-1035, Svc Water Dam & Structure Monthly Insp ML20071Q4031993-01-0606 January 1993 Rev 8 to FNP-0-STP-125, Svc Water Bond Seepage Test ML20126A1941992-12-0808 December 1992 Rev 2 to FNP-0-M-011, Odcm ML20071Q3051992-05-12012 May 1992 Rev 0 to FNP-0-ETP-4384, Svc Water Pond Deformation Monument Readings ML20071Q3871991-03-28028 March 1991 Rev 4 to FNP-0-STP-611.1, Spillway Channel & Structure Verification ML20071Q3601991-03-28028 March 1991 Rev 4 to FNP-0-STP-611.0, Spillway Channel Insp ML20059D8331990-08-30030 August 1990 Rev 76 to EPIP FNP-0-EIP-008 ML20059J1841990-08-24024 August 1990 Rev 10 to ODCM ML20058P6261990-08-15015 August 1990 Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Classs 1,2 & 3 Components ML20058Q1541990-08-15015 August 1990 Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20248H8811989-10-0404 October 1989 Rev 3 to FNP-1-M-042 Re Second 10-yr Interval Inservice Testing Program for ASME Code Class 1,2 & 3 Pumps & Valves ML19325C6751989-09-25025 September 1989 Rev 8 to FNP-0-M-011, Odcm ML20244B4531989-04-0303 April 1989 Rev 7 to FNP-0-M-011, Odcm ML20247C7721989-03-24024 March 1989 Rev 0 to FNP-2-M-068-1, Updated Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20151U2981988-05-31031 May 1988 Suppl 1 to EQDP-ESE-68B, ATWS Mitigating Sys Actuation Circuitry in Amco Cabinet & Wall Mounted Hoffman Relay Enclosure ML20151Y7341988-04-30030 April 1988 Westinghouse MT-SME-186, Background & Technical Basis for Handbook on Flaw Evaluation for Jm Farley Nuclear Plant, Units 1 & 2 Reactor Vessel Beltline & Nozzle to Shell Welds ML20151R3301988-04-14014 April 1988 Rev 5 to General Ofc Emergency Implementing Procedure GOP-EIP-116, Emergency Operations Facility Shift Turnover ML20151S0141988-04-12012 April 1988 Rev 4 to Offsite Dose Calculation Manual ML20236T2641987-11-23023 November 1987 Draft Rev 0 to FNP-1-M-043, Second 10-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20150C2271987-09-18018 September 1987 Rev 4 to FNP-0-M-011, Offsite Dose Calculation Manual ML20150C2201987-08-0505 August 1987 Rev 3 to FNP-0-M-011, Offsite Dose Calculation Manual ML20214P4381987-05-27027 May 1987 Rev 0 to FNP-1-M-042, Second 10-Yr Pump & Valve Inservice Testing Program ML20213H0721987-05-12012 May 1987 Rev 1 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification ML20213H1011987-05-12012 May 1987 Rev 2 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification ML20213A1771986-12-31031 December 1986 Rev 1 to Incident Investigation Manual ML20214K4911986-07-11011 July 1986 Rev 2 to Offsite Dose Calculation Manual ML20154C8681986-02-21021 February 1986 Revised Emergency Plan Implementing Procedures,Including Rev 40 to FNP-0-EIP-8, Emergency Communications & Rev 13 to FNP-0-EIP-26, Offsite Notification ML20133H1181985-10-11011 October 1985 Attachment to Procedure FNP-85-1072 Re on-call Schedules Concerning Both Plant & Nuclear Generation Personnel. Schedules Effective 851001 ML20132E9211985-07-23023 July 1985 Corrected Rev 15 to Emergency Plan Implementing Procedure FNP-0-EIP-4, Chemistry & Environ & Health Physics Support to Emergency Plan ML20133G9431985-05-21021 May 1985 Rev 1 to FNP-0-M-011, Offsite Dose Calculation Manual ML20100H4071985-02-26026 February 1985 Public Version of Revised Attachments a & B to Procedure FNP-0-EIP-8 Re on-call Schedule for Plant Personnel for 1985 & on-call Schedule for Nuclear Generation Personnel for First Quarter 1985 ML20101L5421984-12-27027 December 1984 Rev 5 to General Ofc Emergency Implementing Procedure GO-EIP-131, Emergency Operations Ctr - Flintridge Emergency Equipment & Supplies ML20101L5121984-12-27027 December 1984 Rev 9 to General Ofc Emergency Implementing Procedure GO-EIP-111, Corporate Activation & Notification Procedures ML20101E6061984-12-14014 December 1984 Rev 1 to Emergency Implementing Procedure FNP-0-EIP-30, Post-Accident Core Damage Assessment ML20198D3081984-09-24024 September 1984 Rev 3 to STD-P-05-003, Process Control Program for In-Container Solidification of 4 to 20 Weight Percent Boric Acid ML20095D4101984-08-17017 August 1984 Revised Emergency Plan Implementing Procedures,Including GO-EIP-101 Re Corporate Emergency organization,GO-EIP-135 Re Emergency Plan Review & Rev & GO-EIP-120 Re Ref Guidance for Recovery Manager ML20198D3171984-08-0606 August 1984 Rev 5 to STD-P-05-004, Progress Control Program for In-Container Solidification of Bead Resin ML20093G4051984-07-17017 July 1984 Public Version of Rev 5 to Emergency Plan Implementing Procedure GO-EIP-111, Corporate Activation & Notification Procedures. W/Jm Felton 840717 Release Memo ML20093G3561984-07-17017 July 1984 Public Version of Rev 29A to Emergency Plan Implementing Procedure FNP-0-EIP-8, Notification Roster 1998-04-19
[Table view] |
Text
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(f)P - O ' l 'f-VOL. 14 FNP-0-EIP-20 November 3, 1980 Revision 1 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP-20 S
A F
E T
Y RECOVERY - EOF R
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A PERsonaLpa:.73c7yg DOCUMENT CONTROL
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DELETID IN Accoa:Anchbyf(('".,
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dMCM OF IncurIos Acr DO NOT REPRODUCE COPX NO.,'039 Approved:
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Plant Manager j
Date Issued:
I t fo l
Date of Implementation:
11-17-80 List-of-Effective-Page Page Rev. #
l-6 Rev. 1 Disk EIP-4 8011+40s2s'
FOL. 14 FNP-0-EIP-20 RECOVERY - EOF 1.0 Purpose This procedure delineates the actions to be taken to restore the plant and site to its preemergency status as a result of an emergency requiring the activation I
of the EOF.
2.0 References 2.1 Joseph M. Farley Nuclear Plant Emergency Plan 2.2 Title 10, Code of Federal Regulations, Part 20 3.0 General 3.1 Due to the unforeseeable conditions that would exist in an emergency condition, specific recovery criteria and procedures will be developed when required, considering maximum protection for plant personnel and the general public consistent with reasonable efforts to restore the affected unit and continuing operation of the unaffected unit.
3.2 Personnel exposure to radiation should be kept within 10CFR20 limits.
3.3 All recovery operations will be directed by the Recovery Manager from the Emergency Operations Facility for emergencies requiring EOF activation.
4.0 Procedure 4.1 The Recovery Manager shall have the general responsibilities as described below:
The Recovery Manager shall supervise the operation of the EOF and direct the overall recovery effort.
He has the full authority and responsibility to make decisions regarding acc2 dent mitigation and plant recovery.
He will provide corporate management with timely information on recovery operations through the Senior Vice President.
The line of succession for the Recovery Manager position is as follows:
(1)
Vice President - Nuclear Generation (2)
General Manager - Nuclear Generation (3)
Manager - Nuclear Engineering and Technical Support 1
Rev. 1
VOL. 14 FNP-0-EIP-20 4.2 The Recovery Support Director / Emergency Coordinator shall have the general responsibilities as described below:
The Emergency Coordinator is the general office contact for notification of emergency conditions.
He is responsible for activating the offsite recovery organization.
The Emergency Coordinator will be either:
(1)
General Manager - Nuclear Generation, or (2)
Vice President - Nuclear Generation, or (3)
Manager - Nuclear Engineering and Technical Support, or (4)
Designated alternate of one of the above.
The Recovery Support Director is responsible for overall emergency, planning activities. His responsibilities include the following:
(1)
Coordinate activities with off-site organizations in direct support of operations to establish safe plant conditions and minimize offsite and onsite exposure.
(2)
Maintain lines of communication.with the Alabama Division of Radiological Health, NRC, and other local, state and federal agencies.
(3)
Provide timely and accurate information to the Public Information Manager for release to the media.
(4)
Requests assistance from the Savannah River Operations Office through the State of Alabama or INPO as required.
(5)
Direct administrative support activities in the areas of logistics and manpower.
This position is filled by the General Manager -
Nuclear Generation or his designed alternate.
2 Rev. 1
VOL. 14 FNP-0-EIP-20 4.3 The Technical Support Director shall have the general responsibilities as described below:
The Technical Support Director shall manage the offsite technical resources as necessary to support the Recovery Support Director in recovery efforts.
His responsibilities shall include the 1
following:
(1)
Manage and coordinate offsite organizations with respect to design and construction (APCo, Bechtel, Southern Company Service Incorporated, Westinghouse, etc.) in support of the Recovery Support Director.
(2)
Direct the activities of the Technical Support staff.
4.4 The Public Information Manager shall have the general responsibilities as described below:
1 i
The Public Information Manager communicates with the Recovery Manager and Recovery Support Director concerning the gathering of accurate information regarding plant status, sequence of accident progression, and plans for recoverf. This information will be passed on to the press in a timely manner.
Coordinated news releases are planned in order to minimize the possibility of rumors during an emergency.
He will report to the EOF as directed by the Recovery Manager.
4.5 The Recovery Support Staff shall have the general responsibilities as described below:
4 (1)
Coordinate activities of offsite groups
~
to directly support operatons (e.g.
specialists in the areas of core performance, degraded acde operation, transient analysis, etc.).
(2)
Policies communications into and out of the EOF to keep them organized and efficient.
(3)
Provides information to the Recovery Support Director for his dissemination to state health officials, NRC, upper management, Public Information Manager, etc.
(4)
Provide logistic support as directed by the Recovery Support Director from 4
within the Company and from outside vendors as required.
3 Rev. 1 1
i
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VOL. 14 FNP-0-EIP-20 (5)
Provide manpower support using Company personnel, and outside organizations.
Scheduling shift manning will be coordinated with the Recovery Support Director.
(6)
Coordinate contractural agreements with outside organizations in support of recovery.
(7)
Coordinate environmental monitoring activites and arrange for additional radiological monitoring support.
(8)
Provide information to the Recovery Support Director concerning offsite exposure monitoring for relay to State Health Officials.
4.6 The Technical Support staff shall have the general responsibilities as described below:
(1)
Coordinates design change review and implementation.
(2)
Coordinates licensing issues.
(3)
Communicate with the Health Physics Manager as directed by the Emergency Director on radiological monitoring and assessment.
(4)
Advise Health Physics Manager concerning decontamination, sampling and chemistry control.
4.7 Methodology The decision to relax protective measures will be based upon a comprehensive review of plant system parameters.
These shall include but not be limited to the following:
1.
Stability of the reactor shutdown condition i.e., successful movement toward a cold shutdown condition.
2.
Integrity of the reactor containment building.
3.
Operability of radioactive waste systems and decontamination facilities.
4.
The availability and operability of a heat sink.
4 Rev. 1
~
.. _ = _.
I 1
VOL. 14 EWP-0-EIP-20 1
5.
The integrity of power supplies and electrical equipment.
i 6.
The operability and integrity of instrumentatio:
including radiation monitoring equipment.
I In the latter instance this shall include portable equipment assigned to the 4
emergency.
i 7.
Availability of trained personnel and support services.
The Recovery Manager will analyze the input from his advisors in the areas listed above to determine if plant restoration efforts can begin.
The l
following criterial shall be considered appropriate for the consideration of relaxation of protective measures:
+
l 1.
Plant parameters of operation no longer i
indicates a potential or actual emergency exists.
t i
2.
The releases of radioactivity from the plant is controllable and no longer exceeds permissible levels and no danger to the public from this source is credible.
3.
The plant is capable of sustaining i
itself in a long term shut-down condition.
t r
4.
Plant entry and clean-up is possible without workers receiving in excess of their permissible exposures.
l 4.8 Notification The Recovery Manager shall notify the Plant Manager and company management that a decision i
has been reached to initiate a recovery operation.
I He shall then notify onsite agencies' representatives ensuring the NRC, and State and Local authorities are provided with the same information.
He shall also inform these agencies if any change in the structure of the recovery organization is to occur.
4.9 Population Exposure Total population doses shall be periodically estimated in the affected sectors by utilizing distribution maps and actual census numbers available from the State / Local agencies.
The Recovery Support Manager will work with the 5
Rev. 1 l - -. -.
- L
^
- c..
VOL.-14 FNP-0-EIP-20 State / Local agency representatives to determine both whole body exposure resulting from noble gas / particulate activity (immersion and ingestion doses) and thyroid exposure resulting from the inhalation of radiciodines.
J
.i I
6 Rev. 1
_. _ _ _.,