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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291B1621995-03-0606 March 1995 Rev 9 to Procedure Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii. ML17291A1341994-06-16016 June 1994 Pages 9 & 10 to Rev 11 to PPM 13.12.15,inadvertently Omitted from Original Submittal ML17291A6661994-04-30030 April 1994 WNP-2 Odcm. ML17290A9951993-12-31031 December 1993 Amend 16 to Odcm. ML17290A3771993-05-27027 May 1993 Amend 1 to Inservice Insp Program Plan,First Insp Interval. New Relief Request Will Be Submitted to Define Areas of Limited Exam of RPV nozzle-to-shell Welds ML17272B0141993-04-28028 April 1993 Amend 1 to Vols 1-3 of ISI Program Plan. ML17289B2621993-02-22022 February 1993 Rev 1 to LTI7.4, Operations Liaison Responsibilities. ML17289B1931993-01-31031 January 1993 Offsite Dose Calculation Manual. ML17289A7811992-07-31031 July 1992 Revised Plant Procedures Manual Including Rev 10 to 13.8.2, Backup Emergency Dose Projection Sys Operations & Rev 7 to 13.11.1, Recovery Manager Duties. ML20097H7511992-04-23023 April 1992 Plant Procedure 10.25.89, One Hour - Three Hour Fire Barrier Installation ML17289A5031992-04-0101 April 1992 Washington Nuclear Plant - 2 Licensed Operator Requalification Program Corrective Action Plan Resolution Documentation. ML17286B1791991-11-21021 November 1991 Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2. ML17286A9051991-06-28028 June 1991 Odcm. ML17286A7381991-04-30030 April 1991 Revised Plant Procedures Manual Including,Procedures 13.7.7, 12.7.8,13.8.1 & 13.11.15 ML17286A4971990-12-0505 December 1990 Revised Epips,Including Rev 8 to 13.8.2,Rev 10 to 13.10.9, Rev 8 to 13.11.13,Rev 8 to 13.14.1,Rev 6 to 13.14.3,Rev 10 to 13.14.4 & Rev 7 to 13.14.9 ML17285B0621990-02-26026 February 1990 Amend 7 to Odcm. ML17285B0501990-02-22022 February 1990 Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr ML20066K0451989-03-28028 March 1989 Rev 5 to Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii ML17285A2621988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML17285A2511988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML20090M2951987-11-17017 November 1987 Rev 4 to FATE-84-100, Vipre Code Maint Procedures Manual ML20236N3071987-11-0606 November 1987 Corrected Page 16 of Rev 7 to Procedure 13.14.2, Process for Determining Protective Action Recommendations & Protective Action Decisions ML17279A5931987-10-0808 October 1987 Rev 3b to Pump & Valve Inservice Test Program Plan. ML17284A3901987-06-30030 June 1987 Draft A-3453-87-6, Washington Nuclear Plant 2 Generic PRA- Based Insp Plan. ML17278B1221986-11-17017 November 1986 Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency). ML20215B7551986-07-24024 July 1986 Rev 3 to NDE & I Instruction Qci 6-4, Ultrasonic Exam BWR Nozzle Inner Radius ML20215B7631986-03-20020 March 1986 Rev 3 to NDE & I Instruction Qci 6-13, Ultrasonic Exam of Piping Welds (Manual) ML17278A5681986-01-0606 January 1986 Rev 5 to Emergency Plan Implementing Procedure 13.14.7, Emergency Training. ML17278A5341985-12-20020 December 1985 Rev 3a to Pump & Valve Inservice Test Program Plan. ML17278A4731985-11-0101 November 1985 Revised Emergency Procedures,Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions, Rev 0 to Procedure 5.0.1, Emergency Operating Procedure Flow Chart & Rev 1 to Procedure 5.1.3, Reactor Power Control. ML17278A5491985-09-24024 September 1985 Rev 0 to Procedure Tp 8.6.6, Special Test Procedure for Tdas Class 1E Isolators. ML20133N3611985-09-0909 September 1985 WPPSS-2 Emergency Preparedness Exercise Manual for 850909-13 ML20129B5491985-05-0606 May 1985 Vol 1 of Rev 0 to Inservice Insp Program Plan ML17278A4291985-03-20020 March 1985 Rev 1 to Operating & Engineering Test Procedure 8.2.92, UHS Performance. ML17277B6461985-03-0505 March 1985 Amend 4 to 85-01, Preservice Insp Program Plan, Vols 1-4 ML17277B3101984-02-29029 February 1984 Control Room Design Review Program Plan. ML17277B3091984-02-17017 February 1984 Function & Task Analysis of Emergency Operating Procedures. ML17277B7331983-12-28028 December 1983 Rev 2 to 23A1900AA, RHR Sys. ML17277B0401983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.3.8, Equipment Clearance & Tagging. ML17277B0421983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.5.1, Tech Spec Surveillance Testing Program. ML17277B0361983-11-0707 November 1983 Rev 5 to Administrative Procedure 1.3.1, Standing Orders/ Night Orders. 1999-08-27
[Table view] |
Text
ACCELERATED DISTRIBUTION DEMONSTPATION SYSTEM REGULA& INFORMATION DISTRIBUTIONYSTEM (RIDE)
ACCESSiON NBR:9208120098 DOC.DATE: 92/07/31 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION
.SCHNELL,J.L. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Revised plant procedures manual including rev 10 to 13.8.2, "Backup Emergency Dose Projection Sys Operations" & rev 7 to 13.11.1, "Recovery Manager Duties." I DISTRIBUTION COP ": A045D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submi al: Emergency Preparedness Plans, Implement'g Pr cedures, C NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 PD 1 1 DEAN,W. 1 1 D
INTERNAL: AEOD/DOA/IRB 1 1 NRR PB9D 1 1 NUDOCS-ABSTRACT 1 1 EG LF~~ 01 1 1 D EXTERNAL: NRC PDR 1 1 NSIC 1 1 R
D D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED)
TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8
jl X
'A
WAS)IINGTOK PUBLIC POWB)
SUPPLV SVSTXuVr INTEROFFICE MEMORANDUM DATE: July 31, 1992 TO: Distribution FROM J. L. h, Plant Administration, WNP-2 (927A)
SUBJECT:
WNP-2 PLANT PROCEDUM~B MANUAL- VOLUME 13 PACKAGE NO.92-183 AMENDMENT
REFERENCE:
PPM *1.2.4 The editorial pages sent out with Package 92-183 were not on Controlled Copy paper.
Please replace the pages you received with the enclosed pages.
P~rcedure Rev Title ~Pa 13.8.2 10 Backup Emergency Dose Projection System Operations 3,4 of 19 13.11.1 7 Recovery Manager Duties 6of10 To verify receipt and inclusion of these Procedures, please sign, date and return this receipt to SHERYL THOMASON, 927A within TEN 1 W RKIN DAYS of the date of this IOM.
Date Signature of Manual Holder Controlled Copy Number JLS/st Attachments t'000 920812009B '))20731
'F...
PDR ADOCK 05000397
'DR'
0 V
~ ~
t ll I
Dl TRIB N- V L 1 ontinued Control
~M'1 Dro Mm Lgggiin 63 Emergency Training 1020 64 Radwaste Control Room 927A 66 Simulator, Shift Manager 1034 68 Remote Shutdown Room (13.4. 1) 927A 69 EOF Communications Center (EOFCC) 1021 73 Dept. Soc. & Health Serv.
74 Dept. Soc. & Health Serv.
75 Dept. Soc. & Health Serv.
78 Shift Technical Advisor 927A 80 Plant Records 927A 82 EOF Decision Center 1020 83 MUDAC 1020 86 Simulator, Shift Technical Advisor (STA) 1034
~87 ~Document Control Desk, NRC 90 Corporate Communications 325 92 Emergency Preparedness Program 1020 93 Radiological Programs 1020 94 Offsite Agency Center 1020 95 Security Decision Center 1020 96 Crisis Management Center 325 97 Technical Data Center 1020 98 Corporate Library 330 102 Telecommunication Services 1032 104 Emergency Preparedness Program 1020 105 NRC Emergency Response 1020 106 Emergency Preparedness Program 1020 114 EOF Decision Center 1020
'23 Planning & Scheduling 988P 126 Asst. Managing Director for Operations 1023 127-132 (6) Licensed Training 1027 133 Emergency Planning 1020 134-136 (3) >
MUDAC Field Team Kits (Sec. 9, 13. 13 .4, 13.14.4) 1020 137-140 (4) MPF Field Team Kits (13.5.4, 13.7.5, S ec. 9, 1020 13.13.4, and 13.14.4) 141 Reliability Centered Maintenance (TOC 0 nly) 142 Pacific N.W. Labs 146 FEMA RX Liason 148 Emergency Planning N/A Kathy McCullough (IOM Only) 917Y N/A Sheryl Thomason (IOM Only) 927A Plant Admin. w/o 927A Susan Legard (IOM Only) 909 Page 2 of 2
DI TRIB N - V LUME 13 Control
~o )y Lamgun ~Mu'1 D~rp 2 Control Room 927A 3 Shift Manager 927A 5 Licensed Training 1027 6 Simulator 1034 7 Technical Manager PE27 8 Operations Manager 9270 HP/Chemistry Manager
'27K 9
10 Maintenance Manager 927S ll Plant Admin. Manager 927S 12 Engineering Services PE13 17 Central Training Services (Sec. 14) 1027 20 Chemistry Supervisor 927A 21 Health Physics Supervisor 927A 25 Project Manager, Bechtel 964D 26 Region V, NRC 27 Security Programs Manager 1021 28 Region V, NRC 29 WNP-3 Technical Library 700 30 EOF Records Room 1020 31 TSC Emergency Response 927A 33 Admin. Security Specialist 953 34 HP Technicians Office 927A 35 Resident Inspector 901A 36 Emergency Preparedness Program 1020 37 Mgr. of Emerg Plann & Environ Prog 1020 42 Maintenance Training 184 46 HS&FP PE12 47 Director, Projects 580 49 Security Training/Evaluation 1021 50 Plant Emergency Director 927A 52 Division of Emergency Management 53 Division of Community Development 54 Dept. Soc. & Health Serv. (Seattle) 55 Federal Emergency Mgmt. Agency 56 Emergency Preparedness Coordinator 57 Benton County Dept of Emerg. Mgmt.
58 WNP-2 Security (SAS) 913 59 WNP-2 Security (CAS) 913 60 WNP-2 Security 913 61 Operations Support Center/Cabinet Lunchroom of 2
'age 1
~R ~Ac ion BEDPS Operator (Cont.) e. Answer the interactive questions based on your judgement and Plant conditions, uch as those that may be listed on MUDAC Calculati n Worksheet (similar to Attachment 4.1), or Control om Calculation Worksheet (similar to Attachment 4.4), provide the basis for TRS-80 EDPS calculations.
The TRS-80 does not ha e a printer capability so EDPS calculations may be list on a worksheet similar to Attachment 4.3.
N~TB: In the eve~ of BEDPS program failure from the TRS-80 Model 1 s memory, the program can be reloaded from th magnetic tape cassette stored with the TRS-80 by doin the following:
Connec the tape recorder/player to the TRS-80 using e supplied cable.
Tu on the TRS-80. Set tape recorder volume co ol to "P".
~ I sert the cassette containing the BEDPS.BA rogram and rewind. Reset tape counter to 000.
e sure that the recorder/player is set for rem te control. (Pause is set to Out)
Press PLAY key and be sure that it locks down.
Access BAS from the Main Menu of the TRS-80 (positi cursor over BASIC and press ENTER).
Type L AD BED and press ENTER.
The TRS-80 will search the tape for the BEDPS.BA program and rint the names of any files it passes over. Once EDPS.BA is loaded, the TRS-80 will print OK.
PROCEDURE NUMBER VISION PhOE 13.8.2 10 3 of19
IVIII ~Acti o BEDPS Operator (Cont.) Tpp ~AV A. 2 p p I rewind tape, remove tape and disconnect tape recorder.
I~M/I A
- a. Enter menu number for BEDPS or RASCAL selection.
- b. Ensure laser printer is on.
- c. Read and follow instructions shown on screen.
- d. Default values must be entered.
- e. If needed, a backup disk for the PS/2 is located in the
'disc storage file in the MUDAC equipment cabinet, When a full page is not produced by the laser printer, you must eject the partial page before you begin another set of calculations.
- 4. When directed, complete Attachment 4.1, Offsite Dose Calculation Worksheet. See Attachment 4.2 for instructions for completing Attachment 4.1.
- 5. Using the information on the worksheet, answer the questions as they appear on the computer screen, Always press ENTER after answering each question.
- 6. At the completion of the program, a Summary of Doses will be displayed.
- 7. RASCAL will display a dose map of effective committed doses.
- 8. Copy the results onto Attachment 4.3, Summary of EDPS Backup Calculation and attach RASCAL results when requested.
- 9. Perform calculations for 1.2, 2.0, 3.0+, 5.0 and 10 miles downwind. Perform calculations for any other distance downwind, as needed.
PROCEDURE NUMEER REVISION PAGE
/
13,8.2 10 4 of 19
A
',g I I
t
CGNTROLLED CGPY CHE KLT T F RRE VERY D Time
~~~1~ ~ni i~l N T AKE R EMER A. Contact the PEP and obtain briefing on event and actions taken to mitigate.
B. Assure the designated JIC Director has emergency event information for mahng timely and accurate releases of information to the public.
ATIN T TAK FR A. Contact the PEP and obtain briefing on event and actions taken to mitigate.
B. Assure the designated JIC Director has emergency event information for making timely and accurate releases of information to the public.
C. Direct notifications be made for partial or full EOF activation as you deem necessary.
A N T TAKEF RAL T:
A. Notify Plant Emergency Director upon your arrival at the EOF and obtain briefing on event status and mitigation activities.
B. Maintain log until secretary arrives.
C. Determine when EOF can be declared ACTIVATED, then:
- 1) Relieve PED of RM duties.
- 2) Assume responsibility for PAR notifications.
- 3) Direct CRASH-initiate and EOF PA announcements be made to inform emergency centers of RM duty transfer.
D. Inform Managing Director/Rep as required.
Attachment 4.1 Page 1 of 3 PROCBDURB NUhIBBR RBYISION PAOB 13.11.1 6of10
ft f