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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
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GO-EIP-112 ALABAMA POWER COWANY NUCLEAR GENERATION DEPARTENT EERGENCY MDBILE C0fMJNICATIONS GO-EIP-112 T CONTROL DOC go coPT copy NO.
033 APPROVED: - .
Manamo'-Nd lear Operations & Administration Date/
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. Date 29 b
'Ffanagbf-Nuclear E 1 r *& echnical Support / '/
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ager-Safety Audit &lEngineering Review Date
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__Vice President-Nuclear Generation.A i
Data Issued
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Rev. 3 8401260185 840118 PDR ADOCK 05000348 l
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/~5 GO-EIP-112 k-IlSEX OF EFFECTIVE PAGES REVISION NO.
- Page No. 0 1 2 3 4 5 6 I 7 8 9 10 1 X 2 X
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h._s; GO-EIP-112 EERGENCY MD81LE COMUNICATIONS 1.0 Purpose This procedure provides instructions for establishing communications between emergency support personnel in transit to the FNP site ar.J personnel located at company facilities. -
2.0 General 2.1 This procedure covers communications with [nobile units enroute between FNP and company. offices in Birmingham.
2.2 The Southeast Division Control Center is unmanned during acs-working hours and a call out will be required (see Table 2).
2.3 An annual update will be performed on all call signs, base-station f phone numbers and PAX extensions by the Superintendent-Regulatory and Procedural Control.
i 3.0 Procedse 3.1 Fns company facilities to mobile units 3.1.1 Determine approximate location using map (Figure 1) and
, dgarture time of person you wish to communicate with.
3J.2 Determine the base station nearest to the mobile unit using M le 2.
NOTE
. It is important TliiaY you stay on the -
line with the base station until they have contacted the mobile unit.
3 ~2 'Sudle Units to Company Centers
.s 33 2.I Using Table 2, detennine the nearest base station. ,
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O ,- GO-EIP-112 V [:
3.2.2 Select the proper Pl. and channel numbers on your UHF mobile
( unit or your proper frequency on your Low Band Unit.
3.2.3 Make the following transmission: "This is call # _ to (base station)".
3.2.4 If no reply. is received following several attempts then using .
Table 2 find the next base station in the direction you are traveling and repeat Steps 3.2.2 and 3.2.3.
3.2.5 Following a reply from a base station acknowledging your transmission give the message you wish to send and the com-pany center you wish to send it to.
NOTE
, If trouble exists with too many com-nunications on that frequency, then
(
the statement "This is a priority message" should be made.
l - ,
3.3 From Aircraft to Company Facilities l
3.3.1 Have pilot contact the nearest Flight Service Station (FSS) and inform Specialist of message to ce relayed.
3.3.2 Request Specialist to repeat message to insure accuracy.
l L 3.3.3 Give Specialist phone number of company facility you wish to send message to and request that he relay the message by placing a collect call on a commercial phone.
3.4 From Company Facilities to Aircraft 1
L 3.4.1 Obtain "N" number of aircraft by calling the Aircraft Coordi-f nator (592-4039)
! 3.4.2 Contact Birmingham Flight Service Station (FSS) at the n .
UTO following: 254-1387 or 254-1388.
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- GO-EIP-112 i 3.4.3 Give Birmingham (FSS) the "N" number of the aircraft and re-
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quest that a " priority message" be transmitted. .
3.4.4 Give the message to the FSS and request they repeat it to insure accuracy.
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TABLE 1 GENERAL OFFICE 80 BILE RADIO UNIT CALL IWpBERS
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AS OF 8-22-83 CALL # OPERATOR CLASSIFICATION-LOCATION 9923 Hairston, G. Manager-Farley Nuclear Plant 933 Kingsley, O. Manager-Nuclear Eng. & Tech. Support 993 Mcdonald, R. Vice President-Nuclear Generation 9935 Morey, D. Operations Superintendent-FNP 978 Thrash H. Manager-Nuclear Operations &
Administration 9924 Woodard, J. Assistant Plant Manager-FhP 9925 Farley Nuclear Plant Ambulance' 9926 C & HP Farley Nuclear Plant -
9967 Masters Security-Faricy huclear Plant 9927 Security Farley Nuclear Plant 9928 Security Farley Nuclear Plant 940 Weaver, Tyre Corporate Security-SE Division Rev. 3
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TABLE 2 - .
MOBILE IMDIO pantsrus EUR GINTilDI. FOIIK AIZESS Control Podet Hsurs of Operetion RAF-PL.f. Ch. # Aggrostlaste a - - Aresse (7 days / week unless speciflod)
{ el.0 Shades Cohabe Service Dept. Monday-Friday IklF-PL.1, Ch. I General Of fice to Jemison Exit
- 823-4480 or PAX 81-88-71, 0800-1700 on 1-65 at Exit Number 219 4 81- 8 8- 72 , 81- 8 8- 73
- l.1 B'hom Div. Customer Monday-Friday IMF-PL.1, Ch. I Service Center (Radio Room) 1700-0800 251-7378; 251-3500 or PAX 24 hrs. Sat. & Sun.
4,-
81-465,81-446 82.0 Clanton Office 83-5430; Monday-Friday UHF-PL.3, Ch. 8 Jemison Exit Number 219 to alle 85-5435; 85-5445; 755-0570 0800 - 1700 marker 193 on 1-65 j h
e2.1 Southern Div. Customer Monday-Friday (MF-PL.3, Ch. 8 . !
I Service Conter 2 63- 6244, 1700-0800 M' 2 8-E4 6' or PAX 5-3 71, 24 hrs. Sat. & Sun.
- 83-3 78, 83-3 79 e3.0 SD(X: 0000 - 2400 UHF-PL.3, Ch. 6 Mlle Marker 193 on 1-65 to 262-4390, 263-9050 Troy PAX 83-260,83-258, 83-257 t
84.0 SED (X: Monday-Friday UHF-PL.6, Ch.16 Troy to Ozark vn U.S. 231 687-3521 or PAX 86-273, 0800-l 'iOO 86-274,86-276 >
l
' 5.0 FNP, Central Alarm 0000 - 2400 , UHF-PL.8, Ch.10 Ozark to TNP ;
y J Station - PAX 76-305
- All Control Points should be notified that an emergency condition exists and monitoring of their mobile redlo channeks may be of I
vitel importance to personnel enroute to or from Farley Nuclear Plant.
to
." **The placement c the radio antenna If possible should be on the roof of the vehicle, and if possible communications should be ;
w attempted at higher altitude positions. Both of these two measures enhance the clarity of the comununication links. [c -
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MOTE: All PAX extensions are listed as it calling from General Of fice. [
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. Alabama Power Company 600 North 18th Street
! Post Office Box 2641 Birmingham, Alabama 35291
. Telephone 205 250-1000 O\
AlabamaPower the southem s;ectrc system December 15, 1983 Docket No. 50-348 Docket No. 50-364 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Sir:
Erclosed in accordance with 10CFR50, Appendix E requirements are two copies of Emergency Implementing Procedure GO-EIP-112, Rev. 3. Also enclosed is a Document Transmittal Acknowledgement Form which we request that you sign and return so that we may verify your receipt of these documents in accordance with our document control procedures. If you hr.vc any questions, please advise.
Yours very truly, NhMu: !
C. H. Mudd, Jr.
CHMJr/KWM:sm l Enc 16sures: G0-EIP-112 (2) l ReceiptAcknowledgement(1) xc: Mr. K. W. McCracken Mr. C. H. Mudd, Jr.
File A-27.9.1 1:i I4 l; fV
! M >
_ . . ~ _ _ . _ . _ _ . . . _ _ . _ _ . . . . . . .
REGULATORY INFORMAKION DISTRIBUTION SYSTEM (RIDS)
ACCESSIGN N6 RID 9*ee99tSB DUC.DATE: 83/12/15 NOTARIZED: NO DOCKET #
FACIL 50-348 Joseph M. Farley Nuclear Plant, Unit 1, Alabama Power 05000348
~
50-364 Joseph M. Farley Nuclear Plant, Unit 2, Alabama Power 05000364 AUTH.NAME AUTHUR AFFILIATION MUDD,C.H. Alanama Power Co. ,
RECIP.NAME RECIPIENT AFFILIATION NRC = No Detailed Affiliation Given
SUBJECT:
Central Files version of Rev 3 Emergency Plan Implementing Procedure G0=EIP=112, " Emergency Mobile Communications."
W/831215 Itr.
DISTRIBUTION CODE: XOOSS COPIES RECEIVED LTH _{. ENCL $[ SIZES ... .
l TITLE: Emerg Plan (CF Avail) l L
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODS /NAME LTTR Ef:CL ID CODE /NAME LTTR ENCL NRR ORB 1 BC 1 0 REEVES,E. 01 1 1 ,
l f INTERNA 02 1 1 FEVA TECH HAZO9 1 1 l At/DEPER/EPB 03 2 2 IE/DEPER/IR6 1 1
! 14RR /D SI / AEB 1 1 NRR/DSI/RA8 1 0
! REG FILES 07 1 1 l
I I:
l 10 ENCL 8 TOTAL NUMBER OF COPIES HEuUIRLO: LTTR
. ._ . . _ . _