Public Version of Facility Emergency Implementation Procedure, Notification of Unusual Event.| ML19343B029 |
| 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 |
|---|
| FNP--EIP-17-1, FNP-0-EIP-17-01, NUDOCS 8011240497 |
| Download: ML19343B029 (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
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
,.4 VOLUME 14 FNP-0-EIP-17 October 31, 1980 Revision 3 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP-17 S
A F
E T
Y NOTIFICATION OF UNUSUAL EVENT R
E L
A msonAL HI7ACT I:iFcEMATION DELZID IN ACC0rAN05if1TH TH3 g rszcc:a or INFCEMATION ACT D Approved:
H . d. 14 &w Plant Manager Date Issued: /l-4-FD Date of Implementation: 11-17-80 Diskette #EIP-1 List of Effective Pages DOCUMENT CONTROL Page Rev- CONTROLLED COPY 1-4 3 DO NOT REPRODUCE l Checklist pg. 1 3 Fig. 1 3 COPY NO. D39 i l
l 80ll ayo yq 7
s VOLUME 14 FNP-0-EIP-17 NOTIFICATION OF UNUSUAL EVENT 1.0 Purpose This procedure defines the criteria for classifying an emergency as a Notification of Unusual Event, delineates l personnel and organizations who may be notified and lists actions which may be taken to mitigate the effects of the emergency.
'2. 0 References 2.1 Joseph M. Farley Nuclear Plant Emergency Plan.
2.2 FNP-0-EIP-8, Notification Roster 2.3 FNP-0-EIP-13, Fire Emergencies 2.4 FNP-0-EIP-11, Handling of Injured Personnel 2.5 FNP-0-EIP-26, Offsite Notification 3.0 General 3.1 Description The classification of Notification of Unusual Event applies to situations in which events are in process or have occurred which could indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occur.
3.2 Criteria A NOTIFICATION OF UNUSUAL EVENT would be required for any plant condition that warrants increased awareness on the part of state and/or local offsite authorities or involve other-than-normal plant shutdown or any of the following items:
3.2.1 Initiation of safety injection either automatically or manually as a result of plant parameters approaching or reaching their setpoint.
3.2.2 Radiological effluent technical specification limits being exceeded.
3.2.3 Any of the following technical specification limited conditions for operation are exceeded:
Rev. 3 1
. VOLUME 14 FNP-0-EIP-17 3.2.3 Any of the following technical specification limited conditions for operation are exceeded:
(a) Reactor coolant activity, (b) Containment integrity requiring shutdown to HOT SEUTDOWN.
3.2.4 Indicated subcooling (margin to saturation) decreased below 100F.
3.2.5 Failure of any of the following valves to c1cse:
(a) Pressurizer safety valve, (b) Pressurizer power operated relief valve and its remote motor operated isolation valve.
J (c) A steam generator safety valve, (d) A steam generator power operated relief valve.
3.2.6 Loss of both trains of offsite power OR--
loss of all onsite emergency, power (diesel generators and auxillaries).
3.2.7 Attempted unauthorized entry into a vital area or attempted sabotage of vital equipment.
3.2.8 Loss of control room indication or annunciation to an extent requiring shutdown.
3.2.9 Natural phenomena being~ experienced or projected to affect the plant site as follows:
(a) Any earthquake, (b) Unusual river water level caused by flood, low water or hurricane surge, (c) Any tornado onsite, (d) Any threatening hurricane.
1 Rev. 3 l l
2
i VOLUME 14 FNP-0-EIP-17 3.2.10 Hazards experienced onsite or within one mile of the site boundary which could affect plant operations, such as:
(a) Aircraft crash, (b) Explosion or fire, (c) Release of toxic gas, (d) Release of flammable gas.
3.2.11 Transportation of contaminated injured individual to an offsite facility.
3.2.12 Loss of secondary coolant outside containment concurrent with ECCS activation.
3.2.13 Complete loss of forced RCS flow as indicated by RCS flow indicators on all three RCS loops. I 3.2.14 Inadvertent loading of a fuel assembly into an improper position which causes ,
Fq to be greater than the technical specification limit.
4.0 Procedure 4.1 A plant operator shall notify the Emergency Director of any emergency if the Shift Supervisor is indisposed.
4.2 The Shif t Supervisor will perform the following:
4.2.1 Announce the condition over the plant public address system and evacuate affected areas of the plant as applicable.
4.2.2 Notify the individuals or authorities as delineated in EIP-26 (Figure 1).
4.2.3 The Shift Supervisor shall perform the duties of the Emergency Director until his arrival or as otherwise instructed by the Emergency Director.
4.3 The Emergency Director will perform the following:
4.3.1 Notify the offsite authorities delineated
- in EIP-26. (Figure 1)
Rev. 3 i
3 i
4 VOLUME 14 FNP-0-EIP-17 4.3.2 Activate that portion of the plant emergency organization necessary to respond to the incident by,providing instructions for the Administrative Aide (refer to EIP-8) and natify the Emergency Coordinator.
4.3.3 Ensure personnel accountability if an evacuation was initiated (EIP-10).
4.3.4 Plan and initiate re-entries (EIP-14) .
4.3.5 Continually reassess the emergency condition to ensure a higher classification does not exist.
4.3.6 Close out with verbal notification to notified agencies followed by a written report as required by technical specifications or escalate to a more severe class.
't Rev. 3 4
FNP-0-EIP-17A NOTIFICATION OF UNUSUAL EVENT CHECKLIST Initials I. Shift Supervisor A. Announce condition and initiate evacuation if required.
B. Notify individuals / agencies per EIP -26 II. Emergency Director A. Provide instructions for the -
Administrative Aide to notify essential members of the plant staff and the Emergency Coordinator.
B. Notify offsite authorities per EIP-26 C. Activate plant emergency organization D. Ensure personnel accountability (EIP-10)
E. Plan and initiate re-entry (EIP-14)
F. Reassess conditions for possible upgrade to a higher emergency classification G. Close out or escalate to a more severe class 1 Rev. 3 J
/
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