Public Version of Facility Emergency Implementation Procedures, Re-entry Procedures.| ML19343B021 |
| Person / Time |
|---|
| Site: |
Farley  |
|---|
| Issue date: |
11/06/1980 |
|---|
| From: |
Harriston W
ALABAMA POWER CO. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML19343A898 |
List: |
|---|
| References |
|---|
| FNP--EIP-14-1, FNP-0-EIP-14-01, NUDOCS 8011240482 |
| Download: ML19343B021 (4) |
|
|
|---|
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
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
ML20202G1311998-02-12012 February 1998
Proposed Tech Specs Re Pressure Temp Limits Rept
ML20202F1121998-02-12012 February 1998
Revised Proposed Changes to TS Page 6-19a for Power Uprate
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
ML20135C8641997-02-14014 February 1997
Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power
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
I h VOL. 14 FNP-0-EIP-14 October 31, 1980 Revision 2 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTICN PROCEDURE FNP-0-EIP-14 S
A F
E T
Y RE-ENTRY PROCEDURES R
E L
A T
E D
PERSONAI. FEI7ACY INFORMATION DC:D IN ACCCDA3CE WIIn itig FF"02 07 IyygpMATION ACT Approved:
c.). W Plant Manager
.n.
. Date Issued: // TO Date of Implementation: 11-17-80 Disk EIP-4 i List of Effective Paces Page Rev.
1 0 DOCUMENT CONTROL 2 2 CONTROLLED COPY 3 2 DO NOT REPRODUCE COPY NO. OM BAL)by0 %L 0 .. -
VOL. 14 FNP-0-EIP-14 4
RE-ENTRY PCCCEDURES 1.0 Purcose
. This procedure provides the guidelines for re-encry into plant or site areas which have been evacuated as a result of an emergency.
2.0 References Joseph M. Farley Nuclear Plant Emergency Plan.
3.0 General 3.1 Re-entry shall be made to:
3.1.1 Ascertain personnel evacuation and search for. missing personnel.
3.1.2 Rescue trapped or injured personnel.
3.1.3 Determine the extent of damage.
l 3.1.4 Perform actions which are required to i eliminate a source or potential source that represents a hazard to the general public or to prevent a substantial loss in property. .
3.1.5 Assess radiological and/or other hazardous conditions in order to establish more definite personnel exclusion areas boundaries.
3.2 A fire emergency shall be considered a special re-entry and procedures for re-entry during this type of emergency are addressed in FNP-0-EIP-13, Fire Emergen:les.
3.3 Radiological monitoring shall be required during all re-entries.
3.4 Re-entry into an evacuated' area shall be made
, only upon the direction of the Emergency Director or Shift Supervisor in the absence of the Emergency Director.
3.5 Although emergency situacions may transcend the normal requirement of maintaining personnel exposures below 10 CFR 20 limits, emergency ,
exposures shall be minimized to every degree practicable and'shall not exceed the following
. limits for Farley Nuclear Plant personnel who have completed the casite radiation protection training:
Rev. O s 1
, VOL. 14 FNP-0-EIP-14 3.5.1 25 rem - when emergency onsite action is required to eliminate a source or potential source that represents a hazard to the general public or to prevent a substantial lose in property.
3.5.2 75 rem - for lifesaving operations such l as rescue or search for known missing persons.
4 10 CFR 20 exposure limits shall not be
- exceeded without the approval of the Emergency Director.
3.6 Personnel assigned for re-entry shall be given explicit instructions by the Emergency Director, and other members of the emergency organization, as appropriate, concerning their actions in the emergency area.
3.7 Personnel assigned for re-entry shall wear emergency personnel dosimetry devices, protective clothing, respiratory protection devices and other protective devices as deemed necessary by health physics personnel.
3.8 Re-entry personnel shall not deviate from a planned route unless unanticipated conditions such as rescue, performing an operation which would minimize the emergency condition, etc. ,
require such a deviation.
3.9 If emergency dose rates encountered during re-entry exceed the limits established by the Emergency Director, re-entry personnel shall return to a safe area and contact the Emergency Director for further instructions.
3.10 A Radiation Monitoring Team or Emergency Repair Party which functions as a re-entry team shall consist of at least two persons.
4.0 Procedure 4.1 The Emergency Director shall:
4.1.1 Be responsible for selecting and authorizing qualified personnel for re-entry.
4.1.2 Assign a member of the re-entry team to
, be the team leader.
4.1.3 Plan, with the aid of the emergency
-staff, the activities of re-entry personnel.
Rev. 2 2
s VOL. 14 FNP-0-EIP-14 4.1.4 Thoroughly brief the re-entry personnel concerning the nature of the emergency, the possible hazards and their duties in the emergency area.
4.1.5 Establish exposure limits with the aid of health physics personnel and be responsible for authorizing exceeding any 10 CFR 20 exposure limit.
4.1.6 Thoroughly debrief re-entry, personnel as to their actions in and their assessment of the emergency area.
4.2 Re-entry personnel shall:
4.2.1 Perform assigned duties in the emergency area as quickly and safely as possible.
4.2.2 Advise the Emergency Director of any unexpected conditions which may seriously affect their assigned duties.
4.2.3 Without delaying the mission or causing unnecessary exposures, monitor the dose rate along the route followed to obtain as much radiological information as possible.
4.2.4 Freguently observe their personnel dosimeters and withdraw to a safe area prior to reaching an established dose limit.
4.2.5 Upon exiting, follow established self-monitoring and personnel decontamination procedures, as necessary, under the supervision of the individual charged with health physics monitoring.
4.2.6 Record and report to the Emelgency Director the radiological conditions and damage assessments in the emergency' area.
i Rev. 2 i
l 3
i i
. . . . _ _ _ _ _ , .- ,__ _._. __ _ _ _ _ - - - _ - ,