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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] |
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GO-EIP-136 ALABAMA POWER COMPANY NUCLEAR GENERATION DEPARTMENT GO-EIP-136 NOAA WEATHER ALERT RADIO DISTRIBUTION AND MAINTENANCE APPROVED:
Gener Manager, Nuclear Generation
- a liar ' gb-Nuc 'ea '~ ~ ~ ee7 & Te6hnTEa f~ Support b
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A Aa 1 v _ _
& Engineering Review L D AJ/
Vice Pr. is ent- O e r Generation COPY NO. 38 Vic ~~ ~~tdent-Pdblic Information DO NOT REPRODUCE Date Issued lo 2'l !32_
hbR OCK O 8 Effective Date __Q M JJ.
F PDR List of Effective Pages:
Page No. Revision No.
1-5 0 Figures 1-5 0 Rev. O
t GO-EIp-136 NOAA WEATIIER ALERT RADIO DISTRIBUTION AND MAINTENANCE 1.0 Purpose This procedure defines the responsibilities of the Public Information Department regarding Weather A]ert Radio dis-tribution and maintenance.
2.0 Reference Management Procedure No. 401-003
~3.0 General ,
3.1 Copies of this procedure will be kept at the Parley
- Visitors Center (FVC), Public Information Department, and Farley Nuclear Plant (FNP) Document Control.
Copies will be distributed to the Nuclear Generation Department, General Office Telecommunications Depart-ment, and S.E. Division Telecommunications Group.
3.2 The FVC staf f in conjunction with Nuclear Generation will be responsible for updating procedural information on an annual basis.
3.3 The Nuclear Generation Section will be responsible for 1
procedure issuance and control.
4.0 Procedure 4.1 Electric Cooperatives, Georgia Power Company and APCo Ashford Local Office -
The PVC staff will establish and maintain contact with the electric cooperatives, Georgia Power and APCo local office managers that serve customers within a ten (10)
Rev. O
V GO-EIP-136 mile radius of the nuclear plant regarding the weather alert radios.
4.1.1 Based on written agreement, each electric co-operative, Georgia Power local office and APCo Ashford local office will provide the FVC staff with a monthly listing of residential and busi-ness electrical connects and disconnects. The local offices will also serve as a collection point for residents returning radios when elec-trical service is disconnected due to moving.
4.2 Electrical Connects The FVC staff will coordinate distributing weather alert radios to new residents.
4.2.1 After reviewing the monthly electrical connects and disconnects listings, the FVC staff will ensure that a siren information and emergency preparedness brochure is distributed to new residents in the Gordon, Ashford and Columbia siren zones.
4.2.2 After reviewing the monthly electrical connects and disconnects listings, the FVC staff will mail letters to new residents in areas covered by NOAA radio distribution, requesting that the resident come by a distribution point (APCo f
local office or FVC) to receive a NOAA radio and emergency preparedness brochure. If the new Rev. O
1 GO-EIP-136 resident does not obtain a radio within 90 days, a FVC staff member will contact the resident and if necessary deliver a radio and brochure.
4.3 Electrical Disconnects The FVC staff is responsible for obtaining radios from residents moving out of the 10-mile radius.
4.3.1 Based on written agreement, the electric cooper-ative offices, Georgia Power local office and APCo Ashford local office will serve as a collection point for weather alert radios.
Each resident will be informed by the local office to bring his weather alert radio to the local office or to return it to the FVC.
4.3.2 The FVC staff will collect weather alert radios from the local offices on a monthly basis.
4.4 Radio Malfunctions FVC staff is responsible for handling incoming tele-phone calls and visitors who have problems with the weather alert radios.
4.4.1 The FVC staff will keep a log (Figure 1) of in-coming telephone calls and see that problems are resolved in a timely manner. The FVC staff will systematically try to determine the cause of a radio problem (Figure 2). If the problem cannot t
be resolved over the telephone, the resident will be asked to come by the most convenient Rev. O
GO-EIP-136 distribution point and exchange the malfunction-ing radio for an operable one. The APCo Ashford local office and FVC will serve as distribution points.
In the event that the resident cannot or will not come by a distribution point, an appointment will be made for a staff member to deliver an exchange radio within the next month.
4.5 Weather Alert Radio Repair FVC staff is responsible for coordinating weather alert radio repair.
4.5.1 Based on information provided by the resident, the FVC staff will fill out a deficiency tag (Figure 3) and attach it to the malfunctioning radio before giving the radio to the S.E. Divi-sion Telecommunications group.
4.6 Weather Alert Radio Inventory The FVC staff is responsible for keeping an adequate supply of weather alert radios and batteries for distribution and exchanges.
4.6.1 The FVC staff will keep a quantitative inventory record of all spare weather alert radios--radios in storage, radios at the FVC, and radios being l repaired by S. E. Division Telecommunications group.
4.6.2 FVC staf f will notify the Nuclear Generation
(
l Rev. 0 l
V GO-EIP-136 Department when the inventory level drops to a pre-established minimum level. The Nuclear Generation Department is responsible for ordering weather alert radios.
4.6.3 The FNP storeroom will order batteries based on a pre-established miniumum-maximum stock level.
4.7 Records Management The FVC staff is responsible for keeping a thorough, timely records management program for the weather alert radio distribution and repair.
4.7.1 The FVC will record and keep the following in-formation:
a) Telephone Log of incoming calls regarding the weather alert radios b) Radio deficiency tags 4.7.2 The FVC will be provided the following information:
a) Daily trouble sheet (by S. E. Division Tele-communications group) b) Radio distribution print-out (by FNP Document Control upon request) 4.7.3 FVC staff will provide the following information to PNP Document Control for inputing into the computer:
a) Record of Delivery forms (Figure 4) b) Record of Return or Exchange forms (Figure 5)
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i GO~EIP-135 TROUBLE SYMPTOMS:
I. Radio will not receive transmission Yes/No A. Is unit plugged in? /
B. Is " monitor switch" down and " volume control" fully clockwise /
C. Is antenna installed and fully extended? /
D. Is power switch on? (See pg. 4 of owners manual for location) - -/
If all answers are yes, exchange the radio.
If answer to A is "no" and radio works after being plugged in, replace the battery.
II. Radio will work in " monitor" mode but does not activate during the weekly test Yes/No A. Is unit plugged in? /
B. Is antenna installed & fully extended? /
C. Verify Reset switch is not stuck in " Reset" position. /
D. Does the " Alert" light come on during each test? -f If answers to A and B are yes and reset switch is not stuck, exchange the radio.
If answer to A is "no" and radio works after being plugged in, replace the battery.
l FIGURE 2. NOAA Radio Check List Rev.0
GO-EIP-136 g
O RADIO DEFICIENCY Date Returned:
SN:
Resident Name s,
Malfunction:
b Won' t Receive in Monitor O won't Activate in Alert O spuriously Activates in Alert Other Repaired & Tested by Date FIGURE 3. Radio Deficiency Card Rev. O
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j FORM I GO-EIP-136 4
NATIONAL WEATHER SERVICE RADIO RECORD OF DELIVERY
.J DATE:
OFFERED / DELIVERED TO:
Mr./Mrs.:
Address:
Phone:
'I Evacuation Zone:
i
\ACKNOWLEDGEMENT OF RECEIPT NWS RADIO SERIAL NO.
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i FIGURE 4. Record of Delivery Form (Side 1)
Rev. O t
E GO-EIP-136 FORM II NATIONAL WEATHER SERVICE RADIO RECORD OF DELIVERY DATE:
OFFERED / DELIVERED TO:
Mr./Mrs.:
Address:
Phone:
Evacuation Zone:
VERIFICATION OF DELIVERY (If resident does not wish to sign Form I) OF NWS RADIO SERIAL NO.
APCo Representative RESIDENT INDICATED ABOVE REFUSED TO ACCEPT NWS RADIO APCo Representative RESIDENT NOT AT HOME b) Day 1
] Day 2 F ATTEMPT-TO-DELIVER Notice Attached To Door FIGURE 4. Record of Delivery Form (Side 2)
Rev. 0
V GO-EIP-136 NATIONAL WEATHER SERVICE RADIO RECORD OF RETURN OR EXCHANGE DATE:
RETURNED / EXCHANGED BY:
Mr./Mrs.:
Address:
Phone:
Evacuation Zone:
Serial Number of Radio Returned:
Serial Number of Radio Issued:
Resident Signature f
Date Transmitted to Document Control: By:
FIGURE 5. Record of Return or Exchange Form Rev. O
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GO-EIP-137 ALABAMA POWER COMPANY NUCLEAR GENERATION DEPARTMENT GO-EIP-137 PNS SIREt1 SYSTEM TESTING AND MAINTENANCE APPROVED:
^
Genera ~ianager, Nuclear Gen 6Tition
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r7N uclear,. i ering & Techniddf Support
- 00 Ml M hager-Safetp hudit & E Qfneering Review
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Vice PreslifenFNuclear Generation CONTROLLED COPY
, pygg '3 g DO NOT REPRODUCE Vi(p'Predft . t-Sout t Divisi3 (o/,23hn Date Issued Effective Date _$ h d %J,_
List of Effective Pages:
Page No. Revision No.
1& 2 0 Table 1 0 Figure 1 0 Rev. 0
b ,
GO-EID-137 PNS SIREN SYSTEM TESTING '
AND MAINTENANCE 10 Purpose The purpose of this procedure is to delineate the program ~to be utilized for ensuring Farley Nuclear Plant (FNP) prompt notification system (PNS) sirens,are maintained in an operable condition. -
2.0 Scope This procedure applies to Southeast Division Telecommunica-tions personnel.
3.0 References 3.1 Whelen Model WS-3000 Electronic Siren Warning System Instruction Manual 4.0 General -
4.1 Operational Testing of each PNS siren wil1 be conducted quarterly on the dates shown in Table 1 and.coordina'thd' -s with the Houston County Department of Civil Defense.
I 4.2 Prior to each scheduled test, the APCo Public Information Department will arrange for eppropri ate notice to be provided to the public affected by the test.
4.3 Test results will be documented utilizing Figure 1.
5.0 Procedures _
5.1 Petform a visual inspection of the speaker cluster, speaker cable, siren case assembly and antenna. ,
5.2 Inspect batteries and verify bau.ery " eyes" are green..
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- GO-EIP-137 e'
Hearing Protection must be worn for the following steps 5.3 Contact Houston County Civil Defense at 1-794-9720 or 1-793-1114, Ext. 240 and request that the siren system being checked be activated in the "PA" node followed by the "Hi/Lo" mode.
5.4 While the siren system is activated (operating), verify illumination of the 16 LEDs and the clipping indicator located on the siren amplifier panel.
5.5 Verify that the siren is audible in the "PA" mode and that the correct tones pattern is generated with adequate volume in the "Hi/Lo" mode (NOTE: This is not meant to require that the volume be measured).
5.6 Document any corrective maintenance performed and retest as required.
5.7 Notify Houston County Civil Defense of successful test completion.
Rev. 0
O GO-E IP-13 7 TABLE 1 PNS SIREN TEST SCHEDULE t
. 1982 2nd Quarter Thursday May 20 3rd Quarter Thursday July 1 4th Quarter Thursday October 7 1983 1st Quarter Thursday January 6 2nd Quarter Thursday April 7 3rd Quarter Thursday July 7 4 th Quarter Thursday October 6 1984 1st Quarter Thursday January 5 2nd Quarter Thursday A'pril 5 3rd Quarter Thursday-July 5 4th Quarter Thursday October 4
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