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| O YANKEE NUCLEAR POWER STATION i
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| i GRADED EXERCISE l MARCH 1987
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| ! EXERCISE MANUAL 1
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| O O mee. -
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| 8704130316 870331 qe \
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| PDR ADOCK 05000029 \
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| F PDR \
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE
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| -n
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| () MARCH 1987 TABLE OF CONTENTS Section Page
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| ==1.0 INTRODUCTION==
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| ......................................................- 1.0-1 1.1 Exercise Schedule............................................ 1.1-1 1.2 Participating Centers / Agencies............................... 1.2-1 1.3 List of Abbreviations........................................ 1.3-1 1.4 References................................................... 1.4-1 2.0 EXERCISE OBJECTIVES............................................... 2.0-1 2.1 Station Exercise 0bjectives.................................. 2.1-1 3.0 EXERCISE GUIDELINES AND SC0PE..................................... 3.0-1 3.1 Controller Guidelines........................................ 3.1-1 3.2 Extent of P1ay............................................... 3.2-1 3.3 Simulation List.............................................. 3.3-1 3.4 Player Instructions.......................................... 3.4-1 3.5 Exercise Termination Criteria................................ 3.5-1 4.0 CONTROLLER /0BSERVER INFORMATION................................... 4.0-1 4.1 Assignments.................................................. 4.1-1 4.2 Exercise Guidance / Evaluation Sheets.......................... 4.2-1 5.0 EXERCISE SCENARIO................................................. 5.0-1
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| , 5.1 Initial Conditions........................................... 5.1-1 5.2 Scenario 0utline............................................. 5.2-1 5.3 Narrative Summary............................................ 5.3-1 5.4 Scenario Time Line........................................... 5.4-1 5.5 Detailed Sequence of Events.................................. 5.5-1 6.0 SCENARIO DATA / EVENTS (Message Cards / Command Cards)................ 6.0-1 6.1 Scenario Event Messages...................................... 6.1-1 6.2 News Media Center Messages .................................. 6.2-1 7.0 STATION EVENT DATA................................................ 7.0-1 7.1 Events Summary............................................... 7.1-1 7.2 Event Mini-Scenarios......................................... 7.2-1 1400e
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| YANKEE NUCLEAR.PCWER STATION GRADED EXERCISE p,
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| (f MARCH 1987 TABLE OF CONTENTS (Continued)
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| Section Page 8.0 OPERATIONAL DATA.................................................. 8.0-1 9.0 RADIOLOGICAL DATA................................................. 9.0-1 9.1 Area Radiation Monitors................... .................. 9.1-1 9.2 Process Radiation Monitors................................... 9.2-1 9.3 Plant and Site Radiation Survey Maps......................... 9.3-1 9.4 Primary Vent Stack Release Data.............................. 9.4-1 9.5 Chemistry Data............................................... 9.5-1 9.5.1 Reactor Coolant Activity Concentrations............... 9.5.1-1 9.5.2 Vapor Containment Air Concentrations . . . . . . . . . . . . . . . . . . 9.5.2-1 2 9.5.3 Secondary Side Steam Concentrations................... 9.5.3-1 9.5.4 Reactor Coolant and Secondary Side (Blowdown) ,
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| Sample Dose Rates..................................... 9.5.4-1 1 9.5.5 Steam Generator No. 4 Blowdown Sample Activity Concentrations........................................ 9.5.5-1
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| ' p Q_ 9.6 Off-Site Monitoring Team Observer Instructions / Data..........
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| 9.7. On-Site Monitoring Data......................................
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| 9.6-1 9.7 ,
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| 10.0 METEOROLOGICAL DATA............................................... 10.0-1 10.1 Meteorological Data (Control Room) ......................... 10.1-1 10.2 Meteorological Data (EOF / ESC) .............................. '
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| 10.2-1 10.3 Weather Forecast ........................................... 10.3-1
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| : 10. 4 ESC Me t eo rol o g ic al Da t a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.4-1
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| -lii-1400e
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| O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987
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| ==1.0 INTRODUCTION==
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| ,_a _. a a -_. am. _ a -- _,,., ,,
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| 1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 1.1 EXERCISE SCHEDULE O .
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| O -.
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| . . . ~ _ - . . _ _ . . - .- . - - . - . - - - . - . . _
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| Rav. 1 3/21/87 e Page 1.1-1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 1.1 EXERCISE SCHEDULE Controller Briefing / Tours 1
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| Date: Monday, March 30, 1987 Time: 1:00 PM i
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| Location: Yankee Information Center l 4
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| ==Purpose:==
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| NRC Emergency Response Facility Appraisal Entrance / Emergency i Exercise Scenario Briefing
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| * Attendees: Yankee Management / Drill Coordinator /NRC Appraisal and Exercise Team Date: Monday, March 30, 1987 :
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| i .
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| Time: 2:00 PM Location: Yankee Information Center
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| ==Purpose:==
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| Pre-exercise scenario briefing Attendees: Yr,nkee Controllers / Observers, NRC Evaluators f T
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| Rev. 1 3/21/87 7-ss Page 1.1-2 1.1 EXERCISE SCHEDUI.E (Continue l)
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| Date: Monday, March 30, 1987 Time: 3:30 PM Location: Emergency Response Centers and In-Station Areas
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| ==Purpose:==
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| Familiarize Controllers with affected areas Attendees: In-plant Yankee Controllers GRADED EXERCISE Date: Tuesday, March 31, 1987 i
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| O Time: 4:45 AM
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| (
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| Location: Yankee Nuclear Power Station l Emergency Operations Facility (EOF) - Buckland News Media Center - Charlemont Engineering Support Center (ESC)
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| ==Purpose:==
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| Demonstrate the ability to adequately protect the health and f
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| safety of the public and station personnel Attendees: Yankee Emergency Response Organization 5
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| r
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| , - - - - _ , , - , - . . . . . . _ . - - , , _ _ _ . ~ . . - . _ _ - , _ . - - - - - _ _ _ _ _ _ . _ _ . - . _ . _ . .-m.-.- , - , . _ ,- . , _ - - . _ - - . _ - - ..
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| Rev. 1 3/21/87 1.1 EXERCISE SCHEDULE (Continued)
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| EXERCISE DEBRIEFINGS Date: Tuesday, March 31, 1987 Times Upon exercise termination Location: In individual emergency response facilities
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| ==Purpose:==
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| Exercise debriefings Attendees: Controllers / Observers / Players (NRC Observers welcome)
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| Date: Tuesday, March, 31, 1987 O Time: After Facility Debriefings Location: Buckland EOF
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| ==Purpose:==
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| Controller / Observer Coordinated Debriefing Attendees: Controllers / Observers, NRC welcome 1402a
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| 4 Rev. 1 l 3/21/87
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| ; Page 1.1-4 i
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| 4 Date: Wednesday, April 1, 1987 l
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| ,t f
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| j Tiime: 9:30 AM P
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| Location: Yankee Information Center i
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| 1
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| : Purposes Controller Debriefing ,
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| e Attendees: Yankee Controllers / Key Station Personnel /NRC 4
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| 1
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| !. Note: This will be followed by the NRC critique session.
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| YANKEE NUCLEAR POWER STATION i
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| : f. .
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| 1' !
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| GRADED EXERCISE I
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| : i. i.
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| 1 MARCH 1987 l 1
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| \'
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| @ 1.2 PARTICIPATING CENTERS / AGENCIES :
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| l r l Rev.'O
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| - 1/12/87 Page 1.2-1 YANKEE NUCLEAR POWER STATION
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| ; GRADED EXERCISE MARCH 1987 1.2 PARTICIPATING CENTERS .
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| YANKEE ATOMIC ELECTRIC COMPANY Emergency Operations Facility (in Buckland, MA)
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| Technical Support Center i News Media Center (in Charlemont, MA)
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| Control Room Forward Control Point Operations Support Center Security Gatehouse Engineering Support Center (Corporate) (in Framingham, MA)
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| PARTICIPATING AGENCIES Commonwealth of Massachusetts agencies and/or departments State of Vermont agencies and/or departments 4
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| a O
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 1.3 LIST OF ABBREVIATIONS O
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| ; 3 Page 1.3 + --
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| 1.3 List of Abbreviations o ARM l' - Area Radiation Monitor '
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| o 'ASDV - Atmospheric Steam Dump Valve 4
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| .o CRP -
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| Control Room Panel
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| - ),
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| .o' CTMT 4 '
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| Containment o DC0 -
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| Duty and Call Officer o DF -
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| Dilution Factor o EAL -
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| Emergency Action Level i- o- ECCS- -
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| Emergency Core Coolan't, System
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| , o. EOFC -
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| Emergency Operations, Facility Coordinator o EOF -
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| Emergency Operations Facility o ERO . - Emergency Response Organization o EPZ -
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| . Emergency Planning Zone o ESC -
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| Engineering Support Center
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| -KI Potassium Iodide o -
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| 7 o LPSI -
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| Low Pressure Safety Injection a
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| f o MCS- - ' Main Coolant System ,
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| - 3 t o MCP -
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| Main Coolant Pump F o- MCSLAPM - Main Coolant System Leak Air Particulate Monitor l- o MSL -
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| Main Steam Line t
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| o NMC -
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| News Media Center o NAS - Nuclear Alert System b
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| [ o NG -
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| Noble Cases l o- NRC -
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| Nuclear Regulatory Commission o NRV -
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| Nonreturn Valve o . NWS -
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| National Weather Service l .
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| . e i 1404e I , ,
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| '^
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| Rev. 1 3/21/87 Page 1.3-2 o OP -
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| Operating Procedure o OSC -
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| Operations Support Center o OSCC -
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| Operations Support Center Coordinator o PAB -
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| Primary Auxiliary Building 4 o PED -
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| Plant Emergency Director o POD - -
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| Pocket Dosimeter o PVS -
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| Primary Vent Stack o REA -
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| Radiological Evaluation Assistant o RM -
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| Recovery Manager o SG -
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| Steam Generator o SI -
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| Safety Injection o SIAS -
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| Safety Injection Actuation Signal o SRV -
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| Safety Relief Valve o SS -
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| Shift Supervisor o TAG -
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| Technical Administrative Guideline o TS -
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| Technical Specification o TSC -
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| Technical Support Center o TSCC -
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| TSC Coordinator o VC -
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| Vapor Container (Containment) o WSI -
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| Weather Services International
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| ; o YNPS -
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| Yankee Nuclear Power Station o YNSD -
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| Yankee Nuclear Services Division l l
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| I l
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| 1 04e l
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| N l
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| . O .
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| 4 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 i
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| O
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| ==1.4 REFERENCES==
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| Q 1e.
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| i Rev. O i 1/12/87 Page 1.4-1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987
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| ==1.4 REFERENCES==
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| : 1. Yankee Nuclear Power Station Emergency Plan
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| : 2. Yankee Nuclear Power Station Emergency Plan Implementing Procedures
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| : 3. Yankee Atomic Electric - TAG 12 Emergency Preparedness Responsibilities
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| : 4. Yankee Atomic Electric Company Final Safety Analysis Report Yankee Nuclear Power Station l
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| l I
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| l l
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| O 1ese i
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| . - - - r ,----
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| O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 ;
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| 2.0 EXERCISE OBJECTIVES 4
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| Revision 1 2/6/87 Page 2.0 'O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 2.0 EXERCISE OBJECTIVES Description and Scope 4
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| In order to demonstrate the radiological emergency response preparedness of the Yankee Nuclear Power Station, an emergency response preparedness exercise will be conducted on March 31, 1987. The excercise being conducted for a small-scale exercise which will involve the participation of Yankee station and corporate personnel. The State of Vermont, Commonwealth of Massachusetts, and the local communities within the plume exposure pathway have the opportunity to participate in the
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| () exercise, if they so desire.
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| A set of exercise objectives for the exercise were developed to evaluate -
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| and test certain elements of the Yankee emergency preparedness program.
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| The selected exercise objectives were based upon previous open items identified by the NRC and corrective actions taken in regard to follow-up action items identified by Yankee personnel. These exercice l- objectives will be used to ascertain the required input to the exercise
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| ; scenario sequence of events and to establish the evaluation criteria to be used by the exercise controllers and observers. The specific exercise objectives to be demonstrated are described in the following section.
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| O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 2.1 STATION EXERCISE OBJECTIVES O
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| . Revision 2 3/9/87
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| ,s Page 2.1-1 i \
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| .G' YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 2.1 Station Exercise Ob_iectives A. Emergency Classification and Accident Assessment
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| : 1. Demonstrate the ability of personnel to recognize emergency initiating events and properly classify the condition in accordance with pre-established Emergency Action Levels.
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| : 2. Demonstrate the capability of personnel to technically evaluate the incident conditions and recommend appropriate corrective actions,
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| -")
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| d
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| : 3. Demonstrate that adequate dose assessment procedures can be performed to determine off-site radiological consequences.
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| : 4. Demonstrate that off-site monitoring teams can be dispatched and deployed in a timely manner and that adequate controls exist for performance of contamination surveys of monitoring team vehicles returning to the EOF.
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| : 5. Demonstrate the ability to obtain appropriate chemistry samples, j using the post-accident sampling system, as necessary, in f
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| I support of accident assessment activities.
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| Revision 2 3/9/87 i Page~2.1-2 V:
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| B. Emergency Response Facilities
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| : 1. Demonstrate the ability of station personnel to activate and staff the emergency response facilities in accordance with established procedures.
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| : 2. Demonstrate and test the adequacy'and effectiveness of emergency response facilities operations and equipment.
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| : 3. Demonstrate the ability of each emergency response facility to provide adequate recordkeeping and documentation.
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| C. Notification and Communication
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| : 1. Test the adequacy and operability of communication equipment.
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| among the various emergency response facilities.
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| : 2. Demonstrate that messages between response facilities are transmitted in an accurate and timely manner.
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| : 3. Test the adequacy of the plant emergency notification methods and procedures.
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| : 4. Demonstrate the ability to communicate with in-plant and off-site monitoring teams.
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| : 5. Demonstrate the ability to communicate and coordinate information and actions taken with state emergency response representatives.
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| : 6. Demonstrate the ability to complete timely and accurate initial notifications of the emergency classifications to the States and the NRC.
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| 1221e
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| Revision 2 3/9/87 Page 2.1-3 Q.
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| D. Direction and Control
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| -1. Demonstrate the ability of key emergency response personnel to direct the emergency response organization in the-implementation of the. Emergency Plan and associated procedures.
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| : 2. Demonstrate the ability to conduct briefings regarding the emergency response status within the emergency response facilities periodically throughout the exercise.
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| E. Radiological Exposure Control
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| : 1. Demonstrate the ability to provide adequate radiation protection controls and recordkeeping for emergency response personnel, such as appropriate personnel dosimetry, personnel monitoring (frisking), contamination control, use of protective clothing,
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| '% / and decontamination techniques.
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| : 2. Demonstrate the proper use of radiological survey instruments when performing in-plant surveys under emergency conditions.
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| F. Protective Actions
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| : 1. Demonstrate the ability to implement appropriate on-site protective action measures for emergency response personnel.
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| : 2. Demonstrate the adequacy of the protective action decision making process to make appropriate recommendations.
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| G. Public Information f
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| : 1. Demonstrate the ability to provide accurate and timely
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| ( information releases to the public and the news media.
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| J
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| ! 1221e
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| Revision 2 3/9/87
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| /m- Page 2.1-4 U
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| : 2. Demonstrate the ability to provide briefings for and to interface with the public and news media.
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| : 3. Demonstrate the capability to courmicate and coordinate news l releases between the EOF and the News Media Center.
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| : 4. Demonstrate the ability to coordinate news releases with the state's public information representatives.
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| : 5. Demonstrate the ability to provide rumor control.
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| H. Parallel and Other Actions
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| : 1. Test and evaluate the adequacy of the method to establish and maintain access control and personnel accountability.
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| : 2. Demonstrate, to the extent practicable and within the imposed time constraints, the implementation of recovery planning.
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| : 3. Demonstrate the ability to perform adequate scenario training to the exercise controllers and observers.
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| : 4. Demonstrate the licensee's capability for self-critique and ability to identify areas needing improvement in order to make future appropriate plan and procedural changes.
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| 1221e
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| !7 GRADED EXERCISE i
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| f MARCH 1987-I e i f.
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| e i ,
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| l 3.0 EXERCISE GUIDELINES AND SCOPE L
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 3.1 CONTROLLER GUIDELINES O
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| e
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| 1397e
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| Rev. 1 3/21/87
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| ~ Page 3.1-1 O
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 3.1 controller Guidelines A. Purpose and Scope This document provides guidance for conducting the March 1987 YNPS Graded Exercise. It provides methods for demor.strating emergency response capability, conducting the exercise and evaluating the results. Section 3.3 summarizes the actions to be simulated by players during the exercise.
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| B. Concepts of Operations and Control of the Exercise J
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| Yankee Atomic Electric' Company will supply official Controllers for each location where an emergency response is being demonstrated.
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| Prior to the exercise, the Controllers will be provided with appropriate maps, materials and evaluation forms.
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| , Controllers will distribute information to players on message cards. Controllers will provide advice to Observers and resolve problems. For scenario purposes Lead Controllers may be required to issue command cards to direct the play of some events. The Exercise Coordinator will be in overall charge of conducting the exercise.
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| Major requests for scenario modifications or holding periods must be cleared through the Exercise Coordinator.
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| The exercise initial conditions will be provided by the Control Room Controller. The remaining exercise message cards will be provided
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| , (,_, 1397e
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| Rev. 1-3/21/87
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| / Page 3.1-2
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| (
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| by Controllers at other emergency response facilities at the times indicated by the scenario outline and sequence of events. Other message cards may be issued to players at times required by player !
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| actions during the exercise.
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| As the initiating events are provided to the plant staff, they will determine the nature of the emergency and the implementation of appropriate emergency plan implementing procedures. These procedures are expected to include a determination of the emergency classification in accordance with NUREG-0654 FEMA-REP-1, Rev. 01.
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| Notifications will be made to the appropriate federal, state and local authorities.
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| -The hypothesized emergency will continue to develop based on data and information provided to the operators located in the Control Room. Operators will complete responses as if they were actually responding to the station events. Inconsistencies in the scenario may be intentional and required to provide a basis which tests capabilities of emergency centers to the maximum extent feasible in a limited time. Controllers have the authority to resolve or explain problems that may occur with the scenario during the exercise.
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| C. General Guidance for the Conduct of the Exercise
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| : 1. Simulatina Emeraency Actions Some of the exercise objectives will be demonstrated by simulating the associated emergency response actions. Wherever possible, actions should be carried out. When an emergency response is to be simulated, the Controller will provide the players with written directions in the form of a consnand card on which actions are to be simulated.
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| O 1397e
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| Rev. 1
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| * 3/21/87' Page 3.1-3
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| : 2. Avoidina Violations of Laws Intentional violation of~1aws is not justifiable during any exercise. To implement this guideline the following actions must be taken:
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| : a. All Controllers / Observers and potential exercise participants must be specifically informed of the need to avoid intentional violation of all federal, state and local laws, regulations, ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities should be followed as would normally be the case.
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| : b. Exercise participants will not direct illegal actions being taken by other exercise participants or members of the general public.
| |
| : c. Exercise participants will not intentionally take illegal l actions when being called out to participate in an exercise. Specifically, local traffic laws such as speed laws will be observed.
| |
| : 3. Avoiding Personnel and Property Endanserment Participants and Evaluators will be instructed to avoid endangering property (public or private), other personnel '
| |
| responding to the exercise, members of the general public, animals and the environment.
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| : 4. Actions to Minimise Public Inconvenience 4 It is not the intent, nor is it desirable or feasible, to effectively train or test the public response during the conduct 1397e
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| Rev. 1 3/21/87 s Page 3.1-4 I I V'
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| of radiological emergency exercises. Public inconvenience is to be minimized.
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| The actions of federal, state and local agencies and nuclear
| |
| ]
| |
| power plant operators receive continuous public notice and scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public ,
| |
| (radio, loudspeakers, etc.) be prefaced and conclude with the words, "this is a drill; this is a drill."
| |
| D. Emergency Response Implementation and Operations
| |
| : 1. Initial Notification
| |
| '"3 Initial notification of the emergency classification will be s_ / made by station staff to the states in accordance with existing emergency plan implementing procedures.
| |
| : 2. Emergency Operations Facility (EOF) Operations The EOF emergency response organization will be activated during l
| |
| this exercise. Data will be distributed and transmitted by Controllers in the EOF, TSC, Control Room, Security and OSC.
| |
| : 3. Forward Control Point (FCP) Operations The FCP will be activated during this exercise. FCP information and direction will come from the TSC/ EOF.
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| (Os_,/ 13978
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| Rev.~1 3/21/87 Page 3.1-5 O
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| gj
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| : 4. Control Room Operations The Control Room emergency response organisation will be located at the Control Room during this exercise., Operational data will
| |
| -be provided to operators by the Control Room Controller in the form of message cards and flip charts. Radiological data will be provided to operators as necessary.
| |
| : 5. Technical Support Center (TSC) Operations The TSC emergency response organization will be activated during this exercise. TSC information and direction will come from the Control Roou Operators. TSC Controllers will also.be available to provide data which is normally accessible from the Safety Parameter Display System (SPDS).
| |
| : 6. Operations Support Center (OSC) Operations The OSC emergency response organization will be activated during this exercise. Operations Support Center responses, direction and information will be communicated with the Technical Support Center. OSC Controllers / Observers will accompany all OSC teams dispatched during the exercise and will have appropriate operational and radiological data for the players.
| |
| ~7. Off-Site Monitorina Teams Off-site monitoring teams will be fully activated and dispatched in accordance with existing procedures. Simulated data will be provided to off-site monitoring teams by Exercise Controllers / Observers.
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| 1397e j
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| I l
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| Rev. 1 3/21/87 Page 3.1-6 V
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| : 8. Media Center Operations The Media Center will be fully activated and staffed during the exercise. Press releases to the beneral public and news media will be simulated. Media Center staff will obtain all necessary information on current status of the exercise through normal communications channels with the EOF. Simulated press releases will be compiled and implemented in accordance with the Yankee Media Center Emergency Procedures.
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| : 9. Security Operations l
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| All security emergency responses appropriate to the exercise scenario will be implemented in accordance with existing procedures by an Exercise Security Force. Evacuation and
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| /~' accountability will be demonstrated.
| |
| b E. Exercise Termination The exercise will be terminated by the Exercise Coordinator when all emergency response actions have been completed in accordance with the exercise time sequence.
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| 1
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| () 1397e
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| l O ,
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 O
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| 3.2 EXTENT OF PLAY I
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| O 1224e
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| .Rev. 0 1/27/87 .,
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| Page 3.2-1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 3.2 EXTENT OF PLAY A. Emergency Classification and Extent of Play Accident Assessment
| |
| : 1. Demonstrate the ability of personnel 1. The scenario provides detailed operational to recognize emergency initiating and radiological data which allows personnel events and properly classify the to demonstrate this objective by implementing' condition in accordance with pre- all steps of OP-3300, Classification of established Emergency Action Levels. Emergencies.
| |
| : 2. Demonstrate the capability of personnel 2. The scenario will provide technical-to technically evaluate the incident information to players which will allow them conditions and recommend appropriate to analyze the conditions and propose corrective actions, corrective responses. Corrective actions will be simulated in the plant to the fullest extent possible without affecting normal plant operations.
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| 1224e
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| 4 Rev. 1 3/9/87 Page 3.2-2 Extent of Play
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| : 3. Demonstrate that adequate dose assessment 3. Players will be provided radiological data procedures can be performed to determine which will allow them to demonstrate this off-site radiological consequences. objective by implementing appropriate sections of OP-3310 (Control Room) and OP-3347 (EOF)..
| |
| : 4. Demonstrate that off-site monitoring 4. This objective will be demonstrated in teams can be dispatched and deployed in accordance with OP-3311. Monitoring teams a timely manner and perform the will be dispatched and provided scenario appropriate monitoring activities. off-site radiological conditions by exercise observers who will accompany teams in the field.
| |
| : 5. Demonstrate the ability to obtain 5. This objective will be demonstrated by the appropriate chemistry samples, using simulation of drawing chemistry samples the post-accident sampling system, as in accordance with OP-9450. Scenario data necessary, in support of post-accident will be provided by exercise observers who assessment activities. accompany OSC teams during their activities.
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| 1224e
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| O O O Rev. 0 1/27/87 Page 3.2-3 Extent of Play B. Emeraency Response Facilities
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| : 1. Demonstrate the ability of station 1. The following facilities will be fully activated personnel to activate and staff the in accordance with Emergency Procedures: CR, emergency response facilities in TSC, OSC, EOF, FCP, ESC, and News Media Center.
| |
| accordance with established procedures. Only emergency response staff will participate in this exercise. All other station operations and l
| |
| staff should not be affected.
| |
| : 2. Demonstrate and test the adequacy and 2. All facilities will be fully exercised.
| |
| effectiveness of emergency response
| |
| ; facilities operations and equipment.
| |
| : 3. Demonstrate the ability of each 3. All facilities will fully document their emergency response facility to provide activities.
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| i adequate recordkeeping and documentation.
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| l l C. Notification and Communication l
| |
| : 1. Test the adequacy and operability of 1. All Yankee communications systems will be communication equipment among the various activated except for the Public Alerting l emergency response facilities. System.
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| I 1224e i
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| l f)
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| \
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| 77 ['
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| j Rev. 1 3/9/87 l Page 3.2-4 Extent of Play
| |
| : 2. Demonstrate that messages between 2. Various communication links will be established in response facilities are transmitted order to transmit information and data. Exercise in an accurate and timely manner. controllers and observers will evaluate the quality and timeliness of messages.
| |
| : 3. Test the adequacy of the plant 3. Personnel will notify the States and NRC by utilizing emergency notification methods and the NAS telephone and the NRC red phone. The Station procedures. Public Address System will be used to inform staff of plant conditions. Activation of the evacuation alarm will occur.
| |
| : 4. Demonstrate the ability to communicate 4. All in-plant and off-site monitoring teams will with in-plant and off-site monitoring communicate with the TSC/OSC and FCP/ EOF, respectively.
| |
| l teams. using the appropriate communications system.
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| l S. Demonstrate the ability to communicate and 5. State coordination will take place at the EOF.
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| i l
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| coordinate information and actions taken with state emergency response representatives.
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| 1 l 6. Demonstrate the ability to complete timely 6. Actual emergency classification notifications and accurate initial notifications of the will be made to the State and the NRC.
| |
| l emergency classifications to the States and the NRC.
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| 1224e l
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| L _
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| i (w _.-) )
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| ! v _-
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| Rev. O l 1/27/87 Page 3.2-5 Extent of Play D. Direction and Control
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| : 1. Demonstrate the ability of key emergency 1. All emergency response facilities have response personnel to direct the emergency & dedicated coordinators who will direct response organization in the implementation 2. emergency response and conduct briefings of the Emergency Plan and associated in their respective facilities.
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| procedures.
| |
| : 2. Demonstrate the ability to conduct briefings regarding the emergency response status within the emergency response facilities periodically throughout the exercise.
| |
| E. Radiological Exposure Control
| |
| : 1. Demonstrate the ability to provide 1. Scenario provided on-site radiological adequate radiation protection controls & conditions have been estimated which for emergency response personnel, such 2. which correspond to postulated system i as: issuing and tracking appropriate activities. Station radiological conditions personnel dosimetry, performing personnel relate directly to the postulated scenario.
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| l 1224e l
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| m O O O Rev. 0 1/27/87
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| 'Page 3.2-6 Extent of Play monitoring (frisking) and contamination The resulting scenario radiological levels control, and demonstrating the use of will require players to pay close attention protective clothing and respiratory to appropriate radiation protection controls
| |
| . protection equipment, as necessary. in accordance with emergency procedures.
| |
| Players will be responsible for performing
| |
| : 2. Demonstrate the proper use of radiological habitability checks of emergency response survey instruments when performing facilities, in accordance with OP-3312, in-plant surveys under emergency projecting and controlling personnel conditions. exposures, in accordance with OP-3330.
| |
| Emergency surveys of plant areas may require use of high-range instrumentation and dosimetry (e.g., teletectors). Use of respirators, protective clothing, and contamination / exposure control techniques
| |
| .will also be warranted. Decontamination of personnel and equipment shall be SIE LATED.
| |
| Issuance of potassium iodide shall be SINLATED. Entry into actual radiation areas, such as the VC shall be SINLATED.
| |
| Collection of system and effluent samples shall be SIELATED.
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| 1224e
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| -t m.um,
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| O O O Rev. 0 1/27/87 Page 3.2-7 Extent of Play F. Protective Actions
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| : 1. Demonstrate the ability to implement 1. On-site protective action measures will appropriate on-site protective action include radiation exposure and contamination measures for emergency response personnel. control and the evacuation of nonessential personnel. The evacuation of personnel will include performing protected area accountability.
| |
| : 2. Demonstrate the adequacy of the protective 2. Protective action decision making will be action decision making process to make demonstrated in accordance with Appendix E -
| |
| appropriate recommendations. of OP-3310, Protective Action Recommendations.
| |
| G. Public Information
| |
| : 1. Demonstrate the ability to provide 1. In accordance with Emergency Procedure accurate and timely information 2. OP-3343, the News Media Center will be releases to the public and the news 3. activated at the Alert classification. Prior media. 4. to the Alert, the Public Affairs Director will
| |
| & draft an initial news release to be used on an
| |
| : 2. Demonstrate the ability to provide 5. "as needed" basis. As the Media Center is briefings and interface with the public activated, new releases will be prepared and and news media. called to AP and UPI. These calls will be simulated. Written releases will follow up 1224e
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| f f .'
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| ' N.]
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| Rev. 0 1/27/87~
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| Page 3.2-8 Extent of Play
| |
| : 3. Demonstrate the capability to communicate these initial news releases based cui and coordinate news releases between information obtained in coctdination~with the .-
| |
| * the EOF and the News Media Center. EOF and ESC. State representatives from Massachusetts and Vermont will be sent to the
| |
| : 4. Demonstrate the ability to coordinate News Media Center where they will coordiaate news releases with the state's public their activities with the Public Affairs information representatives. Director.
| |
| : 5. Demonstrate the ability to provide rumor control.
| |
| j-H. Parallel and Other Actions a
| |
| : 1. Test and evaluate the adequacy 1. Manpower Assistants, Road Barrier Teams and of the method to establish and security will fully _ exercise these methods.
| |
| maintain access control and maintain personnel accountability.
| |
| : 2. Demonstrate, to the extent practicable 2. Recovery planning will be fully exercised in and within the imposed time constraints, a table-top fashion at the EOF.
| |
| the implementation of recovery planning.
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| 1224e
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| _ - - __________ ____ - ___-_ m
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| g.
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| Rev. 0 1/27/87
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| ' Page 3.2-9 Extent of Play . s' L
| |
| : 3. Demonstrate the ability to perform 3. Scenario training will be done for all adequate scenario training to the controllers and observers at a briefing the exercise controllers and observers. day before the exercise. Experienced controllers and observers will be utilized whereever possible.'
| |
| s
| |
| : 4. Demonstrate the licensee's capability 4. Critique items will be compiled and tracked for self-critique and ability to after the exercise by the Technical Services identify areas needing improvement in. Manager at YNPS and Manager - Radiation order to make future appropriate plan Protection at YNSD. Plan and procedure and procedural changes. changes will be made as necessary.
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| . /
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| d AI r;
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| + ''
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| i w
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| l 9
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| 1224e ,
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| 4 O
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 3.3 SIMULATION LIST O .
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| l
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| / 4 1490e
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| . . _ . , . . __. ___ . ~ . .. - -. _.. _ _ . . _ _ _ _ . _
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| -t 1 <
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| v
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| ~
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| Rev. 1-3/26/87 i
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| . Page 3'3-1 .
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| {
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| ; YANKEE-NUCLEAR POWER STATION +
| |
| 4 GRADED EXERCISE I
| |
| i
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| . MARCH 1987 l' ,
| |
| 3.3 Simulation List j
| |
| {; 1. Plant specific data will not be programmed into the SPDS. _ Specific SPDS data will be issued in the Cue Card form.
| |
| l
| |
| : 2. . During the exercise,: plant evacuation and center activation will' t- occur. However, once the exercise participants have-been selected, ;
| |
| { - then those personnel unassigned will be allowed to return to normal duties (i.e., the plant can consider these-personnel'as scheduled-F emergency relief _ staff).
| |
| LO i 3. No VC entries will be allowed to perform in-plant corrective actions.
| |
| i
| |
| : 4. "The actual drawing of- post-accident samples sill be simulated.
| |
| I Results of all radiological surveys and samples will be provided on -
| |
| - Cue Cards.-
| |
| 4
| |
| : 5. Meteorological data will be simulated using Message Cards from
| |
| . Section 10.0. -
| |
| ~
| |
| ; 6. If plant areas should be considered as scenario contamination areas, ,
| |
| ~
| |
| . players will be instructed to post the areas and coordinate clean-up
| |
| ; - activities in accordance with appropriate procedures. Use of-
| |
| : protective clothing and respirators will be simulated except.for t various demonstrations as determined by the Exercise Coordinator which will be performed to satisfy.the exercise objective.
| |
| 3 I.
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| i -
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| 1490e ,
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| i 4
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| 4
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| --rw-** w t -e--* m *>-ere= n - - wee ve-e e ve. . -w irare,**-se-r---+ww.w-*-r-'m 6-w -=n- ~--v-ett e v =r +w t 4 v s-= w , e - m =re- m n '='er'wwww---==-w-er-e -a t--esm y - t- --st"9k'---
| |
| | |
| Rsv. 1 3/21/87 Page 3.3-2 .
| |
| ' p.
| |
| : 7. If exercise conditions warrant the issuance of Potassium Iodide (KI), then the decision will be recorded, but the action will be simulated.
| |
| : 8. Plant recovery will be demonstrated in a table-top type of format.
| |
| : 9. The plant organization will be instructed to discuss procedural methods associated with personnel decontamination activities, if conditions warrant such action.
| |
| : 10. Medical emergency response will not be demonstrated during the exercise.
| |
| '11. Fire protection capabilities will not be demonstrated during the exercise.
| |
| g)
| |
| ( ,
| |
| : 12. For the purpose of the exercise, smoking and drinking will be allowed at all emergency centers. Drinking and eating will not be allowed in any portion of the Radiation Control Area.
| |
| : 13. Controllers / Observers and off-site agency representatives will not be issued dosimetry unless plant access is required.
| |
| . 14. Security will be provided with a list of Exercise nonparticipants for accountability purposes.
| |
| 1490e
| |
| - ,r -. __ ~ e -r ,, -- , ,,--w,- -- --w- =*m-... ~y, ,. , ,---- ,. - - . ,w -, - , -.4,- ,.-, ,, ,_-.----. --,4-.w.. -- -- ,
| |
| | |
| A 4 X A .m .- -
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| a ._-
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| - 1 i
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| l O l l
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| 4 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 3.4 PLAYER INSTRUCTIONS O
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| l l
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| O
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| Rev. 1 3/21/87 Page 3.4-1
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| [\
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| %)
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 3.4 Player Instructions An exercise of the Yankee Nuclear Power Station Emergency Plan will be held on March 31, 1987. The successful demonstration of emergency response capabilities will depend on Player observation of the following guidelines:
| |
| : 1. Exercise participants include Players, Controllers, Observers, and an Exercise Coordinator. Controllers will provide Players with message and command cards to instigate emergency responses.
| |
| 7~,
| |
| Controller and Observers will be identified by badges and hats.
| |
| ( ,) .
| |
| They will also be evaluating Player actions.
| |
| NRC evaluators will be identified by badges.
| |
| : 2. Always identify yourself by name and function to the Controller / Observers and the NRC evaluators.
| |
| : 3. Play out all actions, as much as possible, in accordance with your Emergency Plan and Procedures as if it were a real emergency. If an action or data is to be simulated, a Controller / Observer will provide Players with appropriate direction.
| |
| : 4. Always identify and discuss your actions to the Controllers. State your data out loud as you are recording it. For your own benefit, it is recommended that you play out your actions as much as 1491e
| |
| (
| |
| | |
| 1 Rav. 1 3/21/87 Page 3.4-2~ ,
| |
| g
| |
| -possible,_as if it were a real emergency. It is to your advantage
| |
| .to exercise as many appropriate response actions as possible.
| |
| 4
| |
| .5. Periodically speak out loud, identifying your key actions and decisions to the Controller / Observers. This may seem artificial, but it will assist the evaluators and is to your benefit.
| |
| : 6. When you are assigned to complete a response action, be sure to be accompanied by an Exercise Controller / Observer at all times.
| |
| : 7. If you are in doubt about completing a response action, ask your Controller or Observer for clarification. The Controller / Observer will not prompt or coach you. Emergency response action must not place exercise participants in any potentially hazardous situations.
| |
| : 8. The Controllers / Observers will periodically issue messages or
| |
| () instructions designed to initiate response actions. You must accept these messages immediately. They are essential to your successful i performance.
| |
| : 9. If the Controller / Observer intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for a l -- good reason.- His direction may be essential to the overall success of the exercise for all participating groups.
| |
| : 10. If you disagree with your Controller / Observer, discuss your problem with him. If an agreement regarding an emergency response cannot be
| |
| +
| |
| made, contact the Exercise Coordinator. Again -do not jeopardize personal safety or. plant operations for the sake of the exercise.
| |
| : 11. Respond to questions in a timely manner.
| |
| ['') 1491e v
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| l
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| _ , . ~ - .. _ _ . _ _ _ , _ _ . . _ . _ . _ _ . . . . - . _ . . . . _ _ _ _ _ _ _ _ . _ . _ _ _ . .
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| r Rev. 1 3/21/87.
| |
| Page 3.4-3 D
| |
| I 12. You must play as if radiation levels are actually present in
| |
| ! accordance with the information you receive. This may require you to wear additional dosimeters, to observe emergency radiation protection practices, and to be aware of and minimize your radiation exposures..
| |
| : 13. Controller / Observers are exempt from simulated radiation levels and
| |
| '- other emergency conditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal station radiological practices and procedures.
| |
| : i. - :14. Utilize status boards and log books as much as possible to document i and record your actions.
| |
| 15.'Always begin and end all communications with the words, "THIS IS A DRILL,". during the exercise so that these communications are not confused with an actual emergency.
| |
| : 16. Players must not accept any messages / instructions from the NRC evaluators. You may answer questions directed to you by NRC evaluators. If you do not know the answer to a question, refer them to your Facility Coordinator or the Controller / Observer.
| |
| 4
| |
| : 17. One of the primary objectives of the exercise is our ability to 4
| |
| self-critique our deficiencies. Try to keep a list of problems which you encounter during the exercise and recommend corrective actions. Provide these to your Facility Controller at your facility debriefing.
| |
| l i
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| () 1491e
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| - - - . , . - . . . . _ - . _ _ ~ , . _ . . . . _ . , . . . _ . . _ - - . . . , _ - - . , _ _ . . . . . . . . - _ . . . . _ - , . . _ - . . . . - _ _ . _ . - _ , - , , - - - _ . _
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| O J
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| YANKEE NUCLEAR POWER STATION j
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| GRADED EXERCISE MARCH 1987 3.5 EXERCISE TERMINATION CRITERIA O
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| O "'8-
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| 1 Rev. O j 1/12/87 ;
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| Page 3.5-1 O
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| 3.5 EXERCISE TERMINATION CRITERIA The exercise may be terminated under the following circumstances:
| |
| : 1. If all emergency response actions have been completed in accordance with the exercise time sequence;
| |
| : 2. If an actual plant emergency condition develops coincident with the exercise; and
| |
| : 3. If an actual off-site emergency impacts the response actions of Yankee exercise participants.
| |
| In the event that Item 2 should occur, the following actions will be taken:
| |
| : 1. The Shif t Supervisor will inform the Control Room Controller of the plant status. The Control Room Controller will, in turn, contact the Exercise Controller and inform him of plant status;
| |
| : 2. The Exercise Coordinator will inform the TSC and EOF Coordinators i and/or the Recovery Manager;
| |
| : 3. Concurrent with the notification in Step 2, the Control Room will announce over the plant paging system the following statement:
| |
| "The emergency plan exercise has been terminated. I repeat.
| |
| The emergency plan exercise has been terminated."
| |
| This message may be immediately followed by the appropriate emergency class announcement (if appropriate).
| |
| : 4. The Exercise Coordinator would be responsible for directing the 1 actions of the Controller / Observers; and 1398e
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| Rev. 0 1/12/87
| |
| ~x Page 3.5-2
| |
| : 5. The emergency plan / procedures and notifications applicable to the event would be implemented in accordance with the nature of the emergency (if appropriate).
| |
| In the event that Item 3 should occar, the following actions should be taken:
| |
| : 1. The State Police, having been notified of the emergency, should open direct communications with the Yankee Control Room using the Nuclear Alert System; r
| |
| : 2. The Shift Supervisor will notify the Control Room Controller who, in turn, will notify the Exercise Coordinator.
| |
| 1
| |
| : 3. A coordinated decision would be made in conjunction with the Recovery Manager and/or the TSC and EOF Coordinators concerning the s- / completion of the exercise;
| |
| : 4. The Exercise Coordinator would be responsible for temporarily halting the exercise until such time a decision could be made;
| |
| : 5. If the final decision were to cancel the exercise, then the Exercise Controller would be responsible for directing the activities of his
| |
| )
| |
| audit crew as well as for the notification of NRC; l
| |
| : 6. If the final decision were to continue the exercise, then the ;
| |
| Exercise Coordinator would be responsible for informing all l Controller / Observers of the projected change to the expected response action (s); and
| |
| : 7. The, Exercise Coordinator would direct his organization as to the appropriate action required to restore the exercise sequence.
| |
| /^T :
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| (j' 1398e
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| O
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| ')
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 4.0 CONTROLLER /0BSERVER INFORMATION O
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| O 1401e
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| L- L= w - - - - '6a.-m0 mae.as *M a m astr-O YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| : l. MARCH 1987 l
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| l l
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| 4.1 ASSIGNMENTS O
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| 1401e
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| I Rev. 1 3/21/87
| |
| . _ Page 4.1-1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 4.1 Assignments Exercise / Appraisal Manager Bill Riethle Exercise Coordinator Tom Fuller-Emergency Operations Facility Controller Ed Wojnas EOF Observer Marc Lupien EOF Observer David Pergola EOF Observer Jim Hawxhurst Control Room Controller Ed May Os CR Observer Joe Lynch Technical Support Center Controller Dan McDavitt TSC Observer Ed Tarnuzzer Operations Support Center Controller Ed Salomon
| |
| ; OSC Observer Steve Spanos OSC Observer Ron Cardarelli OSC Observer Les Esch Security Jim Kay Forward Control Point Controller Don Rice Off-Site Monitoring Team Observer Gary Stratton Off-Site Monitoring Team Observer Mark Gilmore Off-Site Monitoring Team Observer David Newmann
| |
| () 1401e
| |
| (
| |
| -w wy -- --..--- ,,.-,, 9-g m,-, < , * . - , .g , w- -
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| ,7 -,y.m. , - , ,y -- uw.,,, ., oc- w-or,~-y-a.p- y~. -
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| -*.--w-4my, y 3
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| Rev. 1 3/21/87-h.
| |
| t-Page 4.1-2.
| |
| : j. Off-Site Monitoring Team Observer Mike Thornhill I
| |
| s
| |
| [ News Media Center Controller -Ruth Zikaras News Media Center Observer Mary Schnieder, Engineering Support Center Controller Ken Traedge-I
| |
| ; North Hampton State Police, Troop B Dorsey Holsinger ,
| |
| r t
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| o i s i ,
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| O .
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| [
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| . YANKEE NUCLEAR POWER STATION i
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| l GRADED EXERCISE t
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| MARCH 1987 t
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| 1 i
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| l' 4.2 EXERCISE GUIDANCE / EVALUATION SHEETS i
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| i I
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| 1 4
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| 4 4
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| Rev. 0 U 1/12/87 Page 4.2-1 l YANKEE NUCLEAR POWER STATION p GRADED EXERCISE MARCH 1987 T
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| 4.2 EXERCISE GUIDANCE / EVALUATION SHEETS 4
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| Prior to the exercise, each Controller / Observer will be provided the contents of this package and a set of emergency plan implementing procedures which correspond to their assigned audit function. It is the responsibility of the Controller / Observer to read the contents of this package, review the procedures' associated with the assignment, and then I
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| develop a checklist of important concepts associated with the designated procedure which can be used as a reference during the exercise. In developing this checklist, an attempt should be made to categorize the concepts under general headings such as. Communications, Training / Procedural Actions, Organizational Control, etc. This checklist should supplement the Emergency Exercise / Drill Evaluation Forms which are provided in this section.
| |
| Prior to the exercise, each Controller / Observer will be requested to attend a briefing. During this meeting, each Controller / Observer should identify any questions they have with the package content and/or their assignment. It is the responsibility of each Controller / Observer to ensure that they are familiar with the various plant locations where their assignment will require their presence. Tours will be provided as a portion of the training; however, these tours will be limited in their duration. It may be advisable to plan an additional tour.
| |
| Controller / Observer should familiarize themselves with their assigned Center Controller prior to the exercise. The Controller will be responsible for directing controller activities throughout the course of the exercise. At exercise termination, each Center Controller is responsible for meeting with their abservers and directing their critique and documentation of their exercise conrnents. Each 1399e
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| Rev. O i 1/12/87
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| ._3- Page 4.2-2 (O
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| Controller will be responsible for ensuring that this documentation is provided to the Exercise Coordinator at the conclusion of the critique session. Each Controller may also be asked to proviile a brief sumary of their Controller comments or answer specific questions during the formal critique.
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| Controllers and Observers should identify themselves to players and explain their role in the exercise and what they are critiquing.
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| Controllers should inform players that if their actions are going to deviate from standard plant or emergency procedures they should tell the Controller why. Controllers / Observers should keep a detailed time log of events throughout the exercise, listing all transferred data and player responses. This log and related comments should provide the time, place, and names of involved personnel.
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| 2 e primary role of Exercise Controllers / Observers is to review and note 3
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| . p& the emergency responses of the players. In order to document the adequacy of emergency response actions during the exercise, Controllers / Observers are required to complete appropriate sections of the Emergency Exercise / Drill Evaluation Forms. When completing this form, Controllers / Observers should differentiate their comments into one of five evaluation ratings. For inadequate performance of personnel and/or equipment, the Controllers / Observers shall provide recomendations for improvement and corrective / mitigative actions either between the lines of the evaluation items or on the back pages of the forms.
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| Controllers / Observers should ny allow their biases to be documented as recognized inadequacies. Comments and recommendations should be further subdivided according to the following major headings: Facility Activation / Organizational Control, Communications. Adherence to Plans and Procedures, Equipment Capabilities, Scenario, Training, Facility 1.ayout, Off-Site Monitoring Personnel Dosimetry / Exposure Control, and General Comments.
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| 1399c
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| . m.m , . .
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| Rev. 0 7 , 1/12/87 t ) Page 4.2-3
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| , Facility activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was activated; (3) when initial activities were well organized; (4) whether personnel performance follows the organized arrangements specified by procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs, then the Controller / Observer should determine if all affected personnel are aware that the transfer has occurred.
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| Communication comments should identify: (1) personnel familiarity with emergency communications use; (2) whether sufficient communications were available to ensure a timely, efficient, and effective flow of information; (3) whether there were enough communications personnel to make use of all available equipment; (4) the adequacy of communications t
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| en 4 logs and describe the effectiveness of data transfer; (5) whether there C/ were any problems in the design of the existing communications system (i.e., location relative to traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and (7) whether center status boards are effectively used. Controllers / Observers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies.
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| Plans and procedures comments should identify: (1) whether personnel were familiar with the details or overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distracting them frcm performing their required emergency response function; and (4) whether the procedures adequately described the actions required to complete an assigned function.
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| Equipment capability comments should identify: (1) whether all necessary materials and equipment were available and functional; C/ (2) whether emergency response personnel checked operability of 1399e
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| Rev. 0 1/12/87 Page 4.2-4
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| (
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| equipment prior to conducting their assignment; (3) whether backup equipment-was readily available when malfunctions were reported; (4) whether the available systems provide an adequate service; and (5) whether equipment malfunctions impacted the expected emergency response.
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| Scenario-related comments should address: (1) whether sufficient information was available to ensure appropriate player response; (2) whether the scenario details deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompt to the player. An additional question should be answered by the Controllers concerning the adequacy of the scenario in keeping the players active and interested throughout the exercise.
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| Training comments should identify: (1) whether plant personnel have been provided sufficient training to handle "ad hoc" procedural
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| ' deviations; and (2) whether training identifies improper procedural requirements.
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| Conenents on f acility layout deficiencies / recommendations should identify: (1) whether the available work space provided was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and (5) whether f' sufficient references were available to complete the job assignment.
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| 4 Off-site monitoring team should identify; (1) the adequacy of sampling methods;.(2) the adequacy of contamination control measures; (3) the adequacy of reporting and documentation measures; and (4) the
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| ' effectiveness of the team in defining the plume condition and location.
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| ;~ Dose projection techniques should be evaluated in conjunction with this general category. Consideration of dose projection technique i deficiency / recommendations should identify: (1) the effectiveness of 1399e
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| l Rev. 0 1/12/87 g Page 4.2-5 the system in allowing the correct interpretation of off-site conditions; and (2) the eff'utiveness of using the projection technique in positioning of f -site teams.
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| Evaluation of personnel dosimetry / exposure control activities should identify: (1) the timeliness and effectiveness of dosimetry distribution; (2) the effectiveness of protective measures; (3) the adequacy of established contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques.
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| The Controllers / Observers will be provided a supply of the Emergency Exercise / Drill Evaluation Forms found at the end of this section. All such documentation must be provided to the Center Controller prior to the conclusion of the critique. Center Controllers shall forward all forms to the Exercise Coordinator.
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| 1399e w/
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| L -. .-
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| Rev. 0 1/12/87 Page 4.2-6
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| (}
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| CONTROLLER /0BSERVER EMERGENCY EXERCISE / DRILL EVALUATION FORM
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| > Exercise / Drill Date:
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| i Exercise / Drill
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| ==Title:==
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| Name:
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| Controller Location:
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| Controller
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| ==Title:==
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| O
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| * Directions:
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| Complete the following-forms for the locations or emergency responses which pertain to areas which you were respo'nsible for observing or controlling during the exercise / drill. If your evaluation indicates deficiencies in certain areas please provide a description of the problem areas and possible solutions for improvement in the space between the questions or on the back of this form. In rating the evaluation criteria, the following scale should be used where:
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| 0 = Not Applicable, Data Not Available, Not Observed 1 = Poor Unsatisfactory 2 = Adequate, Below Average 3 = Fair, Acceptable, Average i 4 = Cood Above Average 5 = Excellent, Timely f()
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| 1 I
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| 1399e I
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| Rev. 0
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| . 1/12/87 Page 4.2-7 ,
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| C]j h Rating 4.2 A. Overall
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| : 1. Did the staff demonstrate the Facility Emergency 012345 i
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| Response Organization?
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| : 2. Was the functional adequacy of the radiological 012345 emergency response plan and associated procedures in the protection of the station staff and the public in the event of an emergency at Yankee demonstrated by the center staff?
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| B. Control Room
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| : 1. Did the Control Room staff demonstrate the ability 012345 to recognize emergency initiating conditions and classify the events in accordance with OP-33007
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| : 2. Did the Control Room staff demonstrate the ability 012345 i to appropriately implement Emergency Plan Implementing Procedures OP-3301 for an Unusual Event; OP-3302 for an Alert; OP-3303 for a Site Area Emergency and OP-3304 for a General Emergency?
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| : 3. Did the Control Room staff demonstrate the, ability to 012345 analyze current operational and radiological conditions, identify projected trends and potential consequences f and provide recommendations for mitigating actions?
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| : 4. Did the Control Room staff demonstrate the ability to 012345 maintain adequate communications with the Technical Support Center throughout the exercise to complete documentation and record keeping?
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| 1399c
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| Rev. 0 1/12/87 Page 4.2-8
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| ''h
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| /[O Rating.
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| Control Room (continued)
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| Did the Control noom staff demonstrate the ability 012345 5.
| |
| to notify the plant staff of an emergency through the use of alarms and the public address system?
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| Did the Control Room staff demonstrate the ability to 012345 6.
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| notify the Emergency Response Organization of plant emergency status?
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| Did the Control Room staff demonstrate the ability to 012345 i 7.
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| notify off-site auth'orities of plant emergency status?
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| C. Technical Support Center N
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| Did the TSC staff demonstrate the ability to analyze 012345 1.
| |
| 4 changing station status, identify trends and potential consequences and reclassify the emergency in accordance with_0P-3300. " Classification of Emergencies"?
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| Was the activation and operation of the TSC 012345 2.
| |
| demonstrated?
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| 1 Did the TSC staff demonstrate the ability to open 012345 3.
| |
| communications with the NRC7 Did the TSC staff demonstrate the ability to assess 012345 i 4.
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| plant conditions and determine the need for repairs and corrective actions?
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| i i
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| i N-- 1399e
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| _ _ . . _ . . _ . _ _ _ _ _ . _ . . . _ _ - . - . . _ - . . _ _ _ _ _ . _ . . _ . _ _ _ _ __ _.~ - . . _ _ . _
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| l I Rev. 0 1/12/87 Page 4.2-9 Technical Support Center (continued) Rating
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| : 5. Did the TSC staff demonstrate the ability to provide 012345 technical information and advice on plant conditions to support efforts to stabilize the plant for the long term?
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| ;- 6. Did the TSC staff demonstrate the ability to keep 012345 ,
| |
| emergency ft.netion logs and communication record keeping forms?
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| : 7. Did the TSC staff demonstrate the ability to hold 012345 i
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| emergency briefings, including the plant status and transfer of responsibilities, and maintain status h boards?
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| : 8. Did the TSC staff demonstrate the ability to 012345 i
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| -coordinate radiological planning, monitoring and
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| > sampling with.the OSC and to communicate in-plant <
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| radiological conditions with the EOF 7
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| : 9. Did the TSC staff demonstrate the ability to use the 012345
| |
| 'l results of post-accident sampling to redefine or l confirm the condition of the reactor?
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| D. Operations Support Center l
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| : 1. Did the OSC staff demonstrate the ability to respond 012345 appropriately to an Alert. Site Area Emergency or General Emergency?
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| : 2. Did the OSC staff demonstrate the ability to activate 012345 and operate the OSC?
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| ?
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| 1399e f
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| ._I_...._-.._.._...__.____. __ .,.. . - _ _ _ _ . _ _ _ . _ _ _ _ __ . . _ , . . _ . _ _
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| 1 Rev. 0 1/12/87 Page 4.2-10 i l
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| Os Rating Operations Support Center (continued)
| |
| Did the OSC staff demonstrate the ability to direct 012345 3.
| |
| and coordinate radiation protection activities from the OSC during an emergency?
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| Did the OSC staff demonstrate the ability to provide 012345 4.
| |
| radiation protection support to maintenance emergency response teams?
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| 4 Did the OSC staff demonstrate the ability to initiate. 012345 5.
| |
| brief, and dispatch repair and corrective teams?
| |
| Did the OSC staff demonstrate the ability to implement. 012345 6.
| |
| in a timely manner, appropriate Post-Accident Sa.mpling Procedures as directed by the TSC and communicate the
| |
| (''s results back to the TSC?
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| Did the OSC staff demonstrate the adequacy, operability 012345 7.
| |
| and effective use of communications equipment for communications between the OSC Coordinator and OSC personnel with the plant?
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| Did the staff demonstrate the ability to continuously 012345 8.
| |
| monitor and control the exposure of on-site emergency workers?
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| E. Forward Control Point Did the FCP staff demonstrate the ability to operate 012345 1.
| |
| the FCP?
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| l 1399e l
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| Rev. 0 1/12/87
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| -s. Page 4.2-11 E. Forward Control Point (continued) Rating
| |
| : 2. Did the FCP staff demonstrate the ability to initiate. 012345 i'
| |
| brief, and dis, patch field monitoring and road barrier teams?
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| : 3. Did the FCP staff demonstrate the ability to maintain 012345 sice access control?
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| : 4. Did the FCP staff demonstrate the adequacy, operability. 012345 and effective use of communications equipment?
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| F. Emergency Operations Facility
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| : 1. Did the EOF staff demonstrate the ability to activate 012345 and operate.tl.e EOF in accordance with OP-33227
| |
| : 2. Did the EOF staf f demonstrate the ability to perform 012345 j off-site dose projections?
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| : 3. Did the EOF staff demonstrate' the ability to complete 012345 appropriate protective action recommendations in cooperation with state authorities?
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| : 4. Did the EOF staff demonstrate the ability to coordinate 012345 actions needed for recovery?
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| : 5. Did the EOF staff demonstrate the ability to maintain 012345 complete and accurate records, emergency function logs and communication forms?
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| : 6. Did the EOF staff demonstrate the ability to manage all 012345 corporate and plant resources and manpower during an emergency?
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| 1399c
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| Rev. 0 1/12/87 L
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| Page 4.2-12 Emergency Operations Facility (continued) Rating
| |
| : 7. Did the EOF staff demonstrate the ability to 012345 communicate plant status, radiological conditions and emergency response actions to off-site authorities?
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| : 8. Did the EOF staff demonstrate the ability to use the 012345 results of off-site monitoring and sampling?
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| : 9. Did the staff demonstrate the ability to obtain plant 012345 radiological release information?
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| G. Emergency Radiation Exposure Control
| |
| : 1. Did the staff demonstrate the ability to control the 012345 spread of contamination and the exposure of on-site and off-site emergency workers?
| |
| : 2. Did the staff demonstrate the ability to monitor the 012345 radiological conditions of emergency centers and implement appropriate controls as necessary (c.g., ventilation, respirators)?
| |
| : 3. Did the staff demonstrate the ability of emergency 012345 workers to keep track of their individual exposures?
| |
| : 4. Did the staff demonstrate that monitoring and sampling 012345 instrumentation and equipment is appropriately and i accurately calibrated and readily available for usr?
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| l l
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| 1399e 1
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| 9 7 Rev. 0 1/12/87 Page 4.2-13 y
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| Off-Site Monitoring / Sampling Rating-H.
| |
| : 1. Did the staff demonstrate the ability to complete 012345 off-site radiological monitoring and environmental sampling and analysis in a timely manner and in accordance with OP-3311?
| |
| il:'
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| : 2. Did the staff demonstrate the ability to identify 012345 plume location and intensity through the duration of an off-site radiological release? ;
| |
| $ 1
| |
| : 3. Did the staff demonstrate that adequate vehicles 012345 l,',
| |
| for off-site monitoring and sampling are readily available to transport the teams?
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| : 4. Did the staff demonstrate that off-site tearas are 012345
| |
| [ adequately briefed on radiation conditions, their mission, plant conditions and emergency response before being dispatched and are kept apprised of changing status while in the field?
| |
| : 5. Did the staff demonstrate adequate communications 012345 capabilities between the EOF and of f-site teams within the EPZ?
| |
| : 6. Did the staff demonstrate the ability to m:baunicate 012345 of f-site monitoring and sa apling resu1R to the EOF ,
| |
| l and subsequently other emergency cfntsa a timely manner?
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| \
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| 1399c , j
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| 1 5
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| s t .9 Rev. 0
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| =
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| 1/12/87 Page 4.2-14
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| 'Q[''l '
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| Direction and Control Rating I.
| |
| : 1. Was the ability of each Emergency Response Facility 012345 Manager / Coordinator to maintain command and control over all emergency response activities conducted from their facility throughout the exercise demonstrated?
| |
| .2. .Did the staff demonstrate the ability to gather. 012345 assess and disseminate information regarding status of station conditions and emergency response in a timely manner?
| |
| \'
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| J. Protectiv'e Action Decision Making i
| |
| : 1. Did the staff demonstrate the ability to formulate 012345
| |
| - [''I and implement on-site protective action measures V in a timely manner?
| |
| s s s
| |
| : 2. Did the staff demonstrate the ability to formulate 012345 appropriate protective action recommendations and
| |
| ; ccmmunicate those recommendations to state authorities in a timely manner?
| |
| K. Security
| |
| ! 1. Did the Security staff demonstrate the ability of the 012345 Station Security organization to effectively implement the appropriate security procedures for responding to emergency events?
| |
| : 2. Did the Security staff demonstrate access control at 012345 y g.
| |
| .the site?
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| i 1399e
| |
| ..#., ._...._-.._m, , . . . - . . - _ . _ - . - . , , - . . , _ . . , , ,.,-.,,4.,_,,,m m.,,_., .-..-.-..mm.. _ , ,- , . . . .
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| - . =. . _ _
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| l l
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| Rev. 0 l 1/12/87
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| <^s Page 4.2-15
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| .(J K. Security (continued) Rating l
| |
| : 3. Did Security demonstrate that responses do not impede 012345 or hinder emergency responders during an emergency, such as inadvertent locking of computer-controlled doors to vital areas without emergency bypass
| |
| , provisions?
| |
| L. Public Information
| |
| : 1. Did the PI staff demonstrate the ability to coordinate 012345 the preparation, review and release of information with station and corporate officials?
| |
| : 2. Did the PI staff demonstrate the ability to provide 012345.
| |
| accurate and timely information relesses to the O public and the news media?
| |
| : 3. Did the PI staff demonstrate the ability to establish 012345 and operate rumor control in coordination with state and local authorities?
| |
| f
| |
| : 4. Did the PI staff demonstrate the ability to brief the 012345 media in a clear, accurate and timely manner?
| |
| : 5. Did the PI staff demonstrate the ability to coordinate 012345 news releases with state officials?
| |
| : 6. Did the PI staff demonstrate the ability to provide 012345 news updates whether or not changes in status have occurred?
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| ) 1399c
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| Rev. 0 1/12/87
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| -~ Page 4.2-16 G'
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| Re-Entry and Recovery Rating M.
| |
| : 1. Did the staff demonstrate the ability to identify and 012345 discuss appropriate on-site re-entry and recovery activities based upon the current or projected conditions in the affected on-site areas?-
| |
| : 2. Did the staff demonstrate the ability to identify and 012345 discuss appropriate support to off-site re-entry and recovery activities based upon existing or projected conditions in the affected off-site areas?
| |
| : 3. Did the staff demonstrate the ability to perform 012345 post-drill critiques to determine areas of emergency response which need improvement?
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| O l
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| t l
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| 1399c l
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| s I
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| l l
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| l l
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| l I YANKEE NUCLEAR POWER STAION f
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| # GRADED EXERCISE
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| ;. i MARCH 1987-i 4-
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| )
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| i b
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| 1 L
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| i 3
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| f 5.0 EXERCISE SCENARIO i
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| l i
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| t i
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| l l
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| O ,
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| YANKEE NUCLEAR POWER STATION ,
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| l GRADED EXERCISE MARCH 1987 5.1 INITIAL CONDITIONS o m ,.
| |
| | |
| Rev. 1 3/10/87 Page 5.1-1 V :.
| |
| YANKEE NUCLEAR POWER STATION
| |
| -GRADED EXERCISE MARCH 1987 5.1 Initial conditions o The ECCS Pump LPSI 2 is out of service for a pump bearing replacement. This pump is scheduled to be back in service within 24 hours. This is well within the 72-hour Technical Specification shutdown requirement.
| |
| o Yesterday the plant tripped after the loss of a high line. The reactor is now back to full power. The reactor is at 600 MWt and has been operating at this level for the past 11 months except for yesterday's trip.
| |
| O)
| |
| C o The Burnup Number is 13,350 megawatt days / metric ton.
| |
| o The specific activity of the primary coolant has been determined to be: a) 15.0 uCi/gm gross beta / gamma, and b) the Equivalent I-131 has been >1.1 uCi/gm for the past 47-3/4 hours.
| |
| o Meteorological conditions as indicated by the tower are as follows:
| |
| Upper Wind Speed Average (UPWSAV) = 4.0 mph Lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UPWDAV) = 10 Lower Wind Direction Average (LOWDAV) = 10 Delta Temperature (UPDTAV) = -1.0 F l
| |
| I 1227e i
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| | |
| O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 5.2 SCENARIO OUTLINE O
| |
| l r
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| l O 12 -
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| Rsv. 2 3/21/87 Page 5.2-1
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| . n.
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| t
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| ) ,
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 5.2 Scenario Outline l
| |
| TIME EVENT EMERGENCY CLASS 0445 o Initial Conditions: An exercise shift of Control Room (CR) operators in a separate corner of the CR are provided the initial conditions from the CR Controller. Exercise players will also be provided station operational and radiological parameters.
| |
| () 0500 o A chemistry technician calls the CR to report a verified coolant sample with a specific activity greater than 1.0 (uci/gm) I-131 equivalent.
| |
| o Operators should declare an UNUSUAL EVENT based UNUSUAL EVENT upon " fuel damage indication verifying an increase in failed fuel > 0.1% in 30 minutes."
| |
| o Air ejector readings are increasing.
| |
| o Letdown (bleedline) radiation monitor readings are increasing. Operators may decide to initiate a controlled shutdown. This will be controlled not to exceed 5% per hour.
| |
| 1226e h, .
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| t Rev. 2 3/21/87
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| .. 'Page 5.2-2
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| -(s).
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| s~ / .
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| ' TIME EVENT EMERGENCY CLASS !
| |
| ^l
| |
| '0530- o Additional coolant sample analyses are verified !
| |
| and reported to the CR as greater than 300 (uci/gm) I-131 equivalent.
| |
| o Operators should declare an ALERT based upon ALERT
| |
| " severe loss of fuel cladding conditions."
| |
| o State and local agencies are notified and all utility Emergency Response Facilities are activated upon declaration of an ALERT.
| |
| o The bleedline radiation monitor goes off-scale and alarms.
| |
| ) o Chemistry would be sent to get a bleedline sample.
| |
| 0535 o Operators may begin a controlled shutdown of the plant. If this activity is initiated, power reduction will be controlled not to exceed 15% per hour. Any attempts to SCRAM the reactor will also be controlled.
| |
| 0729 o The bleedline radiation monitor remains off-scale high. Coolant samples continue to indicate elevated levels.
| |
| o Plant power level is at approximately 70% and decreasing.
| |
| () 1226e J
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| Rev. 2 3/21/87 Page 5.2-3 V
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| TIME EVENT EMERGENCY CLASS 0729 o An alarm annunciates in the CR upon detection (Cont'd) of a lower N 2Pressure in the upper piston cylinder of Nonreturn Valve No. 4.
| |
| 0730 o A break occurs in main steam line Loop #4 downstream of the nonreturn valve just before the junction with the main steam line Loop #3.
| |
| The break is immediately evident to operators in the operational data provided to them and also throughout the plant due to the sound that the break makes.
| |
| o A reactor trip occurs due to either high flux n or low MC pressure.
| |
| 'U) 0731 o Operators attempt to close Nonreturn Valves 1, 2, 3, and 4. Nonreturn Valve #4 NRV-405-D fails to close due to loss of nitrogen in the upper piston cylinder through the 0-ring sealed connection to the accumulator charging valve.
| |
| This causes the NRV to remain open even after a close signal has dumped the hydraulic oil in the lower piston cylinder. Continued attempts to close the nonreturn valve from the Control Room are unsuccessful.
| |
| o The Safety Injection System actuates upon a low Main Coolant System pressure signal. Borated water is injected ensuring that a return to power does not occur and provides for long-term shutdown.
| |
| 1
| |
| (
| |
| 1226e
| |
| | |
| l Rsv. 2 3/21/87 l Page 5.2-4 TIME EVENT EMERGENCY CLASS 0731 o Over the next few minutes main coolant pressure (Cont'd) drops to 1096 psig and then begins to increase slowly with the two main coolant pumps that are operational. Loops 1 and 4 MCP are tripped manually when main coolant pressure decreases below 1200 psia. Loops 2 (P-14-2) and 3 (P-14-3) MCP trip with generator trip (turbine trip) due to loss of bus.
| |
| o Operators receive alarm indications that Main Coolant Isolation Valve MC-MOV-319 fails to close upon initiation of isolation. The limit switch light does not go out. The reason is a circuit breaker trip in emergency bus switchgear due to failure of one phase line contactor burns away. Attempts to reset from the CR (done only in emergency situations) fail. Operators dispatch a maintenance technician from the OSC to reset and inspect
| |
| ;. the main coolant isolation valve circuit breaker.
| |
| o The Main Coolant System begins to cool down drastically as the rate of heat extraction in the steara generators increases.
| |
| i i
| |
| o Main steam line monitors begin to show increased radiation levels in the secondary side.
| |
| o Steam Generator #4 E-7-4 level decreases.
| |
| 1226e
| |
| | |
| Rev. 2 3/21/87l
| |
| .. Page 5.2-5 TIME EVENT EMERGENCY CLASS 0735 -o The air ejector radiation monitor alarms
| |
| ,off-scale high.
| |
| o- Audible and visual observation of a break in the steam line is reported by the
| |
| , maintenance foreman.
| |
| l o_ Operators should declare a General Emergency . GENERAL based upon " Loss of 2 of 3 fission product EMERGENCY barriers with a potential (actual) loss of ' 3rd
| |
| $ barrier." .This is indicated by a " Failure of-fuel cladding and main coolant boundary." A
| |
| - Steam Generator tube rupture accident has occurred and main coolant activity exceeds-300 (uci/gm) I-131 equivalent. It is possible that these conditions may only be classified-as a Site Area Emergency; however, it is expected that a General. Emergency will be declared based upon the opinion of the Shift Supervisor, l' 0735 o The primary to secondary leak rate, which is proportional to the square root of the primary to secondary differential pressure, increases I as the steam generator pressure drops to
| |
| ; zero. This leak continues until shortly after the MC isolated valve is closed at approximately 0815.
| |
| I o Operators maintain MC temperatures by cycling i the Automatic Steam Dump Valves (ASDVs).
| |
| I 1
| |
| 1226e i
| |
| -+s.w-,.. r,,-. .- ,- ,, ,-,,, -,.y, yo,w--, ,,,.,-,.-.-m.--.,.,,,, --~---_-,._%-,.y---,5
| |
| | |
| .Rsv. 2 3/21/87 Page 5.2-6
| |
| %./
| |
| TIME EVENT EMERGENCY CLASS 0735 o The OSC Team dispatched to investigate the (Cont'd) main coolant pump isolation valve call the Control Room to tell them that attempts to reset are unsuccessful. The OSC Team observes that the contact for the middle line is missing. Pieces are on the bottom of the box. They can see the contacts once they open up the motor controls, o Off-site dose projections are estimated based upon MSL monitor exposure rates assuming a ground level release model.
| |
| 0740 o An OSC Team is dispatched to obtain a new
| |
| () contact for MCP isolation valve from the Spare Parts Room.
| |
| 0815 o The new contact is replaced on the MCP TH Valve No. 4. The OSC Team successfully isolates and tests the breaker circuitry.
| |
| They realign the circuitry to the valve, and the valve is reported operable to the CR.
| |
| 0817 o Operators successfully isolate Loop 4 of the primary system. Loop 4 main coolant i pressures continue to decrease.
| |
| I o Plant conditions continue to stabilize.
| |
| Operators continue activities to bring the plant to a cold shutdown.
| |
| 1226e
| |
| \
| |
| t I
| |
| | |
| l Rev. 2 3/21/87
| |
| ~s Page 5.2-7
| |
| \ .
| |
| TIME EVENT EMERGENCY CLASS 0817- o- Main coolant pressure continues to increase (Cont'd) until it levels out at approximately 1500 l
| |
| psia.-corresponding to the shutoff head of the safety injection pumps.
| |
| 0820 o The isolated primary loop reaches
| |
| -atmospheric pressure approximately 5 minutes after loop isolation. . System temperatures are approximately 212 F.
| |
| 0915 o The plant secondary side continues to cool down.- Radiological levels are decreasing.
| |
| o Since radiological levels and secondary O system-pressures have decreased drastically by this time, cperators may dispatch a team to close the nonreturn valve manually.
| |
| I i
| |
| o The operators may also decide to dispatch an
| |
| : _0SC team to try to inspect the steam line
| |
| ! crack.
| |
| 0945 o Plant conditions continue to stabilize.
| |
| 1 I
| |
| I
| |
| [ o Recovery actions are discussed.
| |
| i 1000 o The exercise is terminated upon direction of I
| |
| the Exercise Coordinator.
| |
| l
| |
| () 1226e I
| |
| | |
| i YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 I.
| |
| 5.3 NARRATIVE
| |
| | |
| ==SUMMARY==
| |
| | |
| t i
| |
| 5 l
| |
| 4 I .
| |
| 4 i
| |
| i 1420e
| |
| )<
| |
| i
| |
| ,_- . . , _ , - - . ~ - . - , --, -. ._ _ - ,_ ,,-._, ,.- - - _ .- -
| |
| | |
| Rev. 1 3/21/87
| |
| . f- Page 5.3-1 t
| |
| , YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 5.3 Narrative Summary Operational Development This exercise scenario is based on a main steam line break transient.
| |
| As the plant returns to full power after the loss of a high line, it becomes apparent due to increased radiological levels that the fuel has been degraded. By 0500, the specific activity of the primary coolant exceeds 1.0 (mci /g) I-131 equivalent and declaration of an Unusual Event is warranted. Operators may begin shutting down the plant at a rate controlled not to exceed 5% per hour.
| |
| \_
| |
| Over the next half hour, air ejector and other radiological monitor
| |
| : readings continue to increase. At 0530, the emergency action level for Alert is exceeded. The emergency response facilities and organization are fully activated within the hour. Over the next two hours, operators begin shutting the plant down at a rate controlled not to exceed 15% per hour.
| |
| At 0729, the operators receive an alarm warning them of trouble with Nonreturn Valve No. 4 (NRV-405-D). It seems to have low N2 Pressure in the upper cylinder. One minute later, at 0730, when the No. 4 main steam line break occurs, this NRV fails to close and an environmental
| |
| , release is in progress.
| |
| When the operators have determined the location of the break, they will i try to isolate the loop with the affected steam generator. When they 1420e m , . . _ . . _ _ _ , . _ _ , . . _ . . _ . _ , . . ,_m_ . _ _ _ _ . , . _ , , _ _ _ _ , , , _ . _ , , _ _ . . - _ _ _ _ . _ _ _ , _ . . . . . _ _ _ _ . . _ . . _ , , , , . , - , . -
| |
| | |
| Rev. 1 3/21/87 f-ss Page 5.3-2 l
| |
| ( ) l s_ - '
| |
| I trip Main Coolant Pump No. 4, however, the No. 4 isolation valve fails to close and the primary to secondary leak continues through the No. 4 steam generator at a rate of about 120 gpm. This volume is assumed to be released to the environment through the steam line break.
| |
| By 0815, the OSC maintenance team repairs the circuitry to the main coolant isolation valve and operators isolate Loop No. 4 of the Primary System. The radiological release begins to decrease quickly. Over the next hour, plant conditions continue to stabilize.
| |
| Radiological Development The scenario begins with indications of failed fuel in the Primary System at 0500. By 0530, radiological sampling indicates severe loss of fuel cladding. As the plant is shutting down, increased radiological levels on secondary side monitors indicate increased steam generator A tube leakage along with the fuel cladding failure.
| |
| At 0730, when the steam line break occurs, there is additional cladding damage and fuel failure. Primary System activities are elevated and the leakage through the No. 4 steam generator also increases. Radiation levels on the secondary side increase.
| |
| Since the main steam line break occurs outside of any plant structures, few in-plant areas are affected radiologically. The air ejector notices increased secondary side levels due to the fuel failure, cladding damage, and steam generator leak. After the trip, however, the condenser is isolated and radiological levels in the turbine hall begin to decrease.
| |
| The environmental release through the main steam line break continues for over 45 minutes. Contamination levels for the yard area on-site are
| |
| () 1420e
| |
| | |
| Rev. 1 l 3/21/87 Page 5.3-3
| |
| ['').
| |
| \s /
| |
| also provided in Section 9.7 for the portion of the release that touches down. Iodine air concentrations, silica gel cartridge count rates, and
| |
| ~
| |
| particulate filter count rates are provided for off-site monitoring teams on Figure 9.6-1 through 9.6-6.
| |
| After the Primary System is isolated, at about 0815, it is assumed that the Secondary System radiological levels decrease considerably. This decrease reflects lower Secondary System pressures and inventory and radioactive decay of the Secondary System source term.
| |
| O 1
| |
| i I
| |
| I j 1420e 4
| |
| , . _ , , . _ . . m_. . , _ _ _ _ _ _ . . _ _ , _ _ _ _ . . . _ _. _ _ _ , _ _ _ _ . _ , _ _ , _ _ _ _ _ _ _ _ _ _ , _ _ _ . _ _ _ _ _ _ . . _ _ __ _ _ . . _ _ _ _ _ _ _
| |
| | |
| L. p, .Akb ,4Wa & 3- nL ma4 a-4a = 4 -4m*** -
| |
| * A " H e'* A^-~^-3*"--"& -" ^e Ao'- -=+ " vm 4 > 6a
| |
| +- !
| |
| 4
| |
| : 1. '
| |
| YANKEE NUCLEAR POWER STATION GRADED EXERCISE i
| |
| f MARCH 1987 4
| |
| 4 J
| |
| I 5.4 SCENARIO TIMELINE 4
| |
| 4 l
| |
| 1 i
| |
| l i
| |
| | |
| r~.
| |
| ( L Rev. 1 \d YANKEE NUCLEAR POWER STATION 3/21/87 GRADED EXERCISE
| |
| . 5.4-1 MARCH 1987 5.4 Scenario Timeline 0400 0500 0600 0700 0800 0900 1000 i
| |
| I i 1 1 i I i I I
| |
| + + +
| |
| + + + + + + +
| |
| : 1. 2. 3. 4.5.6. 7. 8. 9. 10.
| |
| : 1. Initial Conditions Established
| |
| : 2. Fuel Damage Indications - UNUSUAL EVENT
| |
| : 3. Severe Loss of Fuel Cladding - ALERT
| |
| ]
| |
| : 4. Loop 4 Nonreturn Valve Low N 2 Pressure Alarm
| |
| : 5. Loop 4 Main Steam Line Dreak - GENERAL EMERGENCY - Offsite release begins
| |
| : 6. Loop 4 Main Coolant Isolation Valve fails to close.
| |
| ]
| |
| j 7.- Main Coolant Isolation Valve circuitry is reparied -
| |
| i 54 Steam System is isolated. Ofsite release is terminated.
| |
| I 8. OSC team dispatched to manually close #4 Nonreturn Valve.
| |
| : 9. Recovery actions discussed.
| |
| : 10. Exercise terminated.
| |
| | |
| . , ._......y4,_-..____......_____..__._._ _. ... _ ,_... _ _ _.. _ _ _ _ _ - . _ _ . _ _ _ _ _ _ _ _ .
| |
| : 3. .
| |
| 9 j-1-
| |
| 1.4 ' , , ,
| |
| 4-
| |
| : j. .
| |
| Le 4.
| |
| l' f-4 i
| |
| t
| |
| . f 1: !
| |
| ! YANKEE NUCLEAR POWER STATION i i t GRADED EXERCISE MARCH 1987 [
| |
| t s
| |
| I
| |
| ^
| |
| f
| |
| ; -. 5.5 DETAILED SEQUENCE OF EVENTS 4,
| |
| r
| |
| : j. I ee j.
| |
| i i
| |
| I C
| |
| p j? . 'l 1- f I !
| |
| i
| |
| <t t
| |
| L o r i.
| |
| ~
| |
| y k
| |
| i I
| |
| l 1 '
| |
| 1 i
| |
| 4 n
| |
| 1~
| |
| r e me. ;
| |
| 4 w..
| |
| | |
| Rev. 1 3/21/87 Page 5.5-1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 5.5 Detailed Sequence of Events i TIME EVENT MESSAGE COMMAND 0445 o EXPECTED CONTROL ROOM (CR)
| |
| ACTIONS WILL BE IMPLEMENTED BY AN EXERCISE OPERATIONS CREW LOCATED IN A SEPARATED PORTION OF THE CONTROL ROOM.
| |
| o OPERATIONAL DATA WILL BE O PROVIDED ON MESSAGE CARDS, FLIP CHARTS, AND VERBALLY UPON REQUEST FROM A CONTROL ROOM CONTROLLER.
| |
| o CONTROLLERS WILL ISSUE COP 9tAND CARDS WHEN NECESSARY TO PLAYERS TO ENSURE THE EXERCISE PROCEEDS CONSISTENTLY WITH THE DESIGNATED SCENARIO.
| |
| s.
| |
| o The CR Controller provides CR-M-1 initial conditions to CR staff.
| |
| 1486e
| |
| | |
| Rev. 1 3/21/87 p Page 5.5-2 V
| |
| TIME EVENT MESSAGE COPf!Ah3 0445 (Cont'd) o Initiating messages are also TSC-M-1 OSC-C-1 provided to all emergency OSC-M-1 centers and facility staffs Security-M-1 upon subsequent activations. EOF-M-1 OPERATIONAL AND RADIOLOGICAL ESC-M-1 SPDS DATA WILL BE PROVIDED TO EOF-M-2 TSC AND EOF STAFF ON EXERCISE FCP-M-1 MESSAGE CARDS.
| |
| o Operators also receive the first set of operational and radiological station status data.
| |
| 0500 o A chemistry technician calls CR-M-2 the CR to report a verified coolant sample with a specific activity greater than 1.1 (uci/sm)
| |
| I-131 equivalent.
| |
| o Air ejector radiation readings are increasing.
| |
| o Letdown (bleedline) radiation ,
| |
| CR-C-1 monitor readings are also increasing. The operators may decide to initiate a controlled shutdown. The operators will be directed by the CR controller not to shutdown at a rate greater than 5% per hour. Operators will also be directed to simttiste normal shutdown activities within the CR-C-2 plant for exercise purposes.
| |
| 1486e
| |
| | |
| Rev. 1 3/21/87 Page 5.5-3 TIME EVENT MESSAGE C019tAND 0500 (Cont'd) o The Shift Supervisor (Plant Emergency Director) should classify an UNUSUAL EVENT based upon " fuel damage indication verifying an increase in failed fuel y,0.1% in 30 minutes."
| |
| o Control Room personnel should make plant Unusual Event announcement.
| |
| o The Nuclear Alert System should be used to notify Massachusetts and Vermont state police within 15 minutes of classification in accordance with OP-3301.
| |
| o Within one hour of the classification the NRC should be notified using the Emergency Notification System (red phone).
| |
| o Security staff initiate support action as directed. This may include notification of the Emergency Response Organization per OP-Memo 2E-4.
| |
| o The on-call Technical Support Center Coordinator should be notified and report to the TSC.
| |
| 1486e
| |
| | |
| Rev. 1 3/21/87 Page 5.5-4 N.s TIME EVENT. MESSAGE COMMAND 0500 (Cont'd) o The on-call Emergency Operations Facility Coordinator should be
| |
| - notified and report.
| |
| 0515 o If the CR staff have not declared CR-C-3 an Unusual Event or notified appropriate off-site agencies, they will be directed to do so at this time.
| |
| 0525 o All primary responders will have either called in or reported to designated locations.
| |
| o IF OPERATORS DISCUSS POSSIBLE CR-C-4 VC RESPONSE ACTIVITIES, THEY ,
| |
| WILL BE TOLD THAT ANY ATTEMPTS TO ENTER VC SHALL BE SIMULATED.
| |
| on 0530 o Additional coolant sample analyses ,i f
| |
| are verified and reported to the
| |
| \N CR as greater than 300 (uci/gm)
| |
| Q f I-131 equivalent, i
| |
| o An ALERT should be declared based upon " severe loss of fuel cladding conditions."
| |
| o The bleedline radiation monitor CR-M-2a i is off-scale and alarming.
| |
| o The operators will request l
| |
| Chemistry to obtain a bleedline i
| |
| sample.
| |
| ~~-,.m.--,~,,,---.-.,,-n.,- , .- w,---,- ,
| |
| _,--.-_,_-.___,-,,,,--_..,,,.,,,,,,,-,,,,,,,,-m,,_.,,,c._w-.,7,,.,,--,-,,-m,, , , , , - . - - , , , ,
| |
| | |
| Rev. 1 3/21/87
| |
| . , -] .
| |
| Page 5.5-5 TIME EVENT MESSAGE COMMAND 0530 (Cont'd) o Upgraded notification actions should be made in accordance with OP-3302.
| |
| o Emergency response personnel should activate the:
| |
| 1
| |
| : 1. Technical Support Center, f a
| |
| a
| |
| : 2. Operations Support Center,
| |
| : 3. Emergency Operations' Facility,,
| |
| : 4. Forward Control Point, O 5. News Media Center, and
| |
| : 6. Engineering Support Center in a timely manner.
| |
| o Notification should be made to the
| |
| * Yankee Nuclear Services Division. ,
| |
| o CR staff may accelerate the CR-C-5 shutdown rate. FOR EXERCISE PURPOSES, SHUTDOWN WILL BE CONTROLLED NOT TO EXCEED 10%
| |
| PER HOUR.
| |
| o FOR EXERCISE PURPOSES, DO NOT EOF-C-1 OPEN COMMUNICATIONS WITH THE ,'
| |
| () STATE E00s UNTIL AFTER 0630 AM.
| |
| 1486e
| |
| | |
| Rev. 1
| |
| . 3/21/87 74 a: . qj Page 5.5-6 TIME -EVENT MESSAGE . COMI%ND .
| |
| 0530 (Cont'd) o The Turbine Hall' low range- CR-M-2b radiological monitor alarms.
| |
| 0545 o If the PED has not upgraded the CR-C-6 emergency to an ALERT and completed appropriate upgraded notifications, he will be directed to do so at this time.
| |
| 0700 FOR EXERCISE PURPOSES, SHUTDOWN 'WILL BE CONTROLLED NOT TO EXCEED CR-C-6a 20% PER HOUR.
| |
| 0729 'o The blesJ11ne radiation monitor
| |
| .. remains [off-scalehigh. , Coolant samples continue to indicate elevated levels.
| |
| ()
| |
| kJ o Plant power level is at approximately 75%'and decreasing.
| |
| o The operators receive an alarm in the CR-M-3 Control Room annunciating NRV trouble.
| |
| A light on the NRV control cabinet indicates detection of a low N2Pressure in the nitrogen accumulator (upper piston cylinder) of Nonreturn Valve (NRV) 4.
| |
| 0730 o' A break occurs in main steam line Loop 4 downstream of the nonreturn valve just before the junction with the main steam 1 line Loop 3. The break is immediately evident to operators in the operational 0
| |
| .j data provided them and also throughout the plant due to the sound that the break makes.
| |
| 1486e
| |
| | |
| i'
| |
| % g Rev. 1 <
| |
| 3/21/87
| |
| <~ ~s Page 5.5-7 TIME EVENT MESSAGE ' COMMAND 0730 (Cont'd) o Low main coolant steam line.
| |
| pressure and/or high flux J. ,
| |
| initiates a reactor trip.
| |
| N o The reactor trip monitor and CR-M-4 .
| |
| turbine trip monitor are alarming.
| |
| 0731 o Operators attempt to close CR-M-5 Nonreturn Valves 1, 2, 3, and 4.
| |
| Nonreturn Valve 4. NRV-405-D, fails to close due to loss of nitrogen in the upper piston cylinder through the 0-ring sealed connection to the accumulator charging valve.
| |
| This causes the NRV to remain open even after a close signal has dumped the hydraulic oil in the lower piston cylinder.
| |
| Continued attempts to close the nonreturn valve from the CR are unsuccessful. (See Mini Scenario 7.2.1.)
| |
| l o The safety Injection System ,
| |
| actuates upon a low Main Coolant System pressure signal. dorated water is injected ensuring that
| |
| ~
| |
| a return to power does not occur and provides for long-term L shutdown.
| |
| 1486e .
| |
| L
| |
| | |
| 1 Rev. 1 3/21/87
| |
| _ Page 5.5-8 u
| |
| TIME EVENT MESSAGE COMMAND 0731 (Cont'd) o Operators receive alarm indications that Main Coolant Isolation Valve MC-MOV-319 fails to close upon initiation of isolation. The limit switch CR-M-6 light does.not go out. The reason is a circuit breaker trip in emergency bus switchgear due to failure of one phase line contactor burns away. Attempts to reset from the CR (done only in emergency situations) fail.
| |
| Operators dispatch a maintenance technician from the OSC to reset and inspect the main coolant Os ; isolation valve circuit breaker.
| |
| (See Mini Scenario 7.2.2.)
| |
| o The Main Coolant System begins to cool down drastically as the ll rate of heat extraction in the steam generators increases.
| |
| o Operational and radiological data indicate:
| |
| : 1. LPSI flow, MCS temperature, and SG No. E-7-4 are decreasing, and
| |
| | |
| Rev. 1 !
| |
| 3/21/87 Page 5.5-9 '
| |
| l TIME EVENT MESSAGE COMMAND 0731'(Cont'd) 2. Main steam line monitors are increasing. ,
| |
| o Audible and visual observation CR-M-7 of a break in the steam line is reported to the CR by a maintenance foreman.
| |
| 0733 o Loops 1 and 4 MCP are tripped manually due to low main coolant pressure. Loops 2 (P-14-2) and 3 (P-14-3) MCP trip with generator trip (turbine trip) due to loss of bus. Operators trip MCP 1 and 4 whenever MC pressure decreases
| |
| }
| |
| to below 1200 psia.
| |
| 0735 o Air ejector radiation monitor is CR-M-8 off-scale high and alarming.
| |
| o Operators should declare a GENERAL EMERGENCY based upon, [hb
| |
| " Loss of 2 of 3 fission product barriers with a potential (actual) loss of 3rd barrier."
| |
| This is indicated by a " failure of fuel cladding and main cooling boundary." A steam generator tube rupture accident has occurred and main coolant 1486e
| |
| | |
| Rev. 1 3/21/87 Page 5.5-10 (m'
| |
| qJ' TIME EVENT MESSAGE COMMAND 0735 (Cont'd) activity exceeds 300'(uci/gm)
| |
| I-131 equivalent. It is possible that these conditions may only be ,
| |
| classified as a Site Area Emergency; *AhW however, it is expected that a-General Emergency will be' declared based upon the opinion of the
| |
| ' Shift Supervisor.
| |
| o Upgraded notification actions should be nede in accordance with OP-3304.
| |
| o Protective action recommendations should be generated based on the
| |
| %) General Emergency classification.
| |
| o The primary to secondary leak rate, which is proportional to the square root of the primary to secondary differential pressure, increases as the steam generator pressure drops to zero.
| |
| This leak continues until shortly after the MC isolated valve is l
| |
| l closed at approximately 0815.
| |
| o Operators maintain MC temperatures by cycling the ASDVs.
| |
| 1486e I
| |
| - , - . . . ~ . . . , . _ - . ~ , , - - , - . , . - - -- -, -.
| |
| | |
| i l
| |
| Rev. 1 3/21/87' i Page 5.5-11 '
| |
| L TIME EVENT MESSAGE COMMAND 0735 (Cont'd) o The OSC Team dispatched to OSC-M-2 investigate the main coolant pump isolation valve call the Control Room to tell them that attempts to reset are unsuccessful. The OSC Team observes that the contact for the middle line is missing.
| |
| Pieces are on the bottom of the box. They can see the contacts once they open up
| |
| 'the motor controls.
| |
| (See Mini Scenario 7.2.2.)
| |
| o Off-site dose projections are estimated based upon MSL monitor exposure rates assuming a ground level release model.
| |
| 0740 o An OSC Team is dispatched to obtain a new contact for MCP isolation valve from the Spare Parts Room.
| |
| o Main coolant pressure begins to j increase slowly with the one main coolant pump that is operational.
| |
| i 0
| |
| () 1486e
| |
| | |
| Rev. 1 3/21/87
| |
| ,r's Page 5.5-12
| |
| \
| |
| V TIME EVENT MESSAGE COMMAND 0750 o If the PED has not upgraded the CR-C-7 emergency to a GENERAL EMERGENCY and completed appropriate upgraded notifications, he will be directed to do so at this time.
| |
| 0815 o MC pressure continues to increase.
| |
| o The new contact is replaced on OSC-M-3
| |
| .the MCP TH Valve 4 (MC-MOV-319).
| |
| The OSC Team successfully isolates and tests the breaker circuitry.
| |
| They realign the circuitry to the valve, and the valve is reported
| |
| ''N operable to the CR.
| |
| [d 0817 o Operators successfully isolate Loop 4 of the primary system.
| |
| Loop 4 main coolant pressnres continue to decrease.
| |
| o Plant conditions continued to stabilize.
| |
| o Main coolant pressure continues to increase until it levels out at approximately 1500 psia, corresponding to the shutoff head of the safety injection pumps.
| |
| 1486e
| |
| | |
| Rev. 1 3/21/87
| |
| _4 Page 5.5-13
| |
| -TIME EVENT MESSAGE COMMAND 0820' o The isolated primary loop
| |
| . reaches atmospheric pressure approximately five minutes after loop isolation.. System temperatures are approximately
| |
| ~
| |
| 212 F.
| |
| 0915- o A team may be dispatched from OSC-M-4 the OSC to try to inspect the steam line crack.
| |
| o Since radiological levels and secondary system pressures have decreased drastically by this time operators may dispatch a ON team to close the nonreturn valve manually.
| |
| (See Mini Scenario 7.2.1.)
| |
| 0945 o Recovery actions are discussed.
| |
| o Plant conditions continue to stabilize.
| |
| Approximately 1000 o The exercise is terminated.
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| l l
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| 4 ,
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| l
| |
| | |
| 2 -- - ,,-E m -
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| O l
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| 8 YANKEE NUCLEAR POWER STATION GRADED EXERCISE I
| |
| l l
| |
| MARCH 1987 !
| |
| O 6.0 SCENARIO DATA / EVENTS O
| |
| , --------~,,n. , - -- -,- , - - - - - --,--- . - _ . . -- _--- - - - , . - , - , - - - - - .-----c.---- - - - ,--,-n -- - - ,-, - --. , - , - . , , . -a ~-. -
| |
| | |
| I O GENERAL INSTRUCTIONS The following information and supplementary material are provided for those controllers tuving in-plant control assignments so ,a s to i further ensure the proper development of the scenario. The infor-nation provided in this section assumes that the " players", who are dispatched to perform repair, rescue or other activities, will take certain actions in response to the scenario. The controller must be cognizant of the actions of those " players" to which he is assigned and provide information regarding the results of the " players" actions as appropriate to those actions. The information provided in this sec-tion does not preclude the possibility that the controller will be required to provide additional information to the " players".
| |
| V O
| |
| | |
| 4 ?
| |
| O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 O
| |
| 6.1 SCENARIO EVENT MESSAGES 1
| |
| l l
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| O l
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| | |
| Rev. 1 YANKEE NUCLEAR POWER STATION 3/ 24 /8 7 GRADED EXERCISE Page 6.1-1
| |
| /ms MARCH 1987 FOR: Control Room Staff MESSAGE NO.: ca-M_1 0u5 LOCATION: Control Room TIME:
| |
| GIVEN BY: Control Room Controller THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Initial conditions a:: 04t: 5 o The ECCS Pump LPSI 2 is out of service for a pump bearing replacement. This pump is scheduled to be back in service within
| |
| : 21. hours. This is well within the 72-hour Technical Specification shutdown requirement.
| |
| i q
| |
| / o Yesterday the plant tripped after the loss of a high line. The reactor is now back to full power. The reactor is at 600 K4t and has been operating at this level for the past 11 months except for yes'terday's trip.
| |
| o The Burnup Number is 13,350 megawatt days / metric ton.
| |
| o The specific activity of the primary coolant has been determined to bei a) 15.0 uC1/gm gross beta /gema, and b) the Equivalent I-131 has been >1.1 uC1/gm for the past 47-3/4 hours.
| |
| o Meteorological conditions as indicated by the tower are as follows:
| |
| Upper Wind Speed Average (UPWSAV) = 4.0 mph ;
| |
| Lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UPWDAV) = 10' Lower Wind Direction Average (LOWDAV) = 10*
| |
| Delta Temperature (UFDTAV) = -1.0'F i
| |
| THIS IS A DRILL l
| |
| b ********************** **************************************************
| |
| i
| |
| | |
| Rev. 1 ,
| |
| 3/24/87 i YANKEE NUCLEAR POWER STATION l GRADED EXERCISE Page 6.1-2 MARCH 1987 FOR: _p -knical support center (Tsc) MESSAGE N0. Tsc-M-1 LOCATION: Tsc TIME Uoon Activation GIVEN BY: Tsc-controller THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
| |
| '"''''' ' "di'' "'
| |
| MESSAGE:
| |
| at 0445 o The ECCS Pump LPSI 2 is out of service for a pump bearing replacement. This pump is scheduled to be back in service within 24 hours. This is well within the 72-hour Technical Specificaticn shutdown require ent.
| |
| o Yesterday the plant tripped after the loss of a high line. The
| |
| /^' reactor is now back to full power. The reactor is at 600 MWt and y
| |
| has been operating at this level for the past 11 months except for yesterday'a trip.
| |
| o tlc Burnup Number is 13.350 megawatt days / metric ton.
| |
| o The specific activity of the primary coolant has been determined to be: a) 15.0 uci/gm gross beta / gamma, and b) the Equivalent I-131 has been >1.1 uC1/Cm for the past 47-3/4 hours.
| |
| j o Meteorolegical conditions as indicated by the tower are as follewa:
| |
| Upper Wind Speed Average (UPWSAV) = 4.0 rph Lower Wind Speed Average (LOWSAV) = 4.0 mph
| |
| * Upper Wind Direction Average (UPhT/.V) = 10' 14wer Wind Direction Average (1&TAV) = 10 Delta Temperature (UPCTAV) = -1.0 F i
| |
| 9 i
| |
| A THIS IS A DRILL U **....********..***.*******..***.*******.**.*********.**************.*.**
| |
| | |
| Rev.1 YANKEE NUCLEAR POWER STATION 3/24/87 GRADED EXERCISE Page 6.1-3
| |
| ,m; ,
| |
| E i V MARCH 1987 FOR: operations suppare center f osc) MESSAGE NO. osc-M-1 LOCATION: osc~ TIME Upon Activation GIVEN BY: osc controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| Initial eenaitions MESSAGE:
| |
| at 0445 o The ECCS Pump LPS! 2 is out of service for a pump bearing replacement. This pump is scheduled to be back in service within 24 hours. This is well within the 72-hour Technical Specification shutdown requirement.
| |
| o Yesterday the plant tripped af ter the loss of a high line. The
| |
| [ reactor is now back to full power. The reactor is at 600 MWt and k/ has been operating at this level for the past 11 c.onths except for yesterday's trip.
| |
| o the Burnup Nu-ter is 13,350 regawstt days / metric ton.
| |
| o The specific activity of the prin:ary coolant has been determined to bei a) 15.0 uCi/gm gross beta /ganrna, and b) the Equivalent I-131 has been >1.1 uCi/gm for the past 47-3/4 hours.
| |
| o Meteorological conditions as indicated by the tower are as follows:
| |
| Uprer Wind Speed Average (UPWSAV) = 4.0 mph 3 Lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UPWDAV) = 10 tower Wind Direction Average (LOWDAV) = 10 Delta Tereperature (UT::TAV) = -1.0 F s THIS IS A DRILL s
| |
| d *************************************************************************
| |
| | |
| 1 Rev.1 3/24/87 YANKEE NUCLEAR POWER STATION Page 6.14
| |
| -s GRADED EXERCISE
| |
| / i
| |
| \Vl MARCH 1987 FOR: Security MESSAGE N0. Security-M-1 LOCATION: Security'Gatehouse TIME 0445 GIVEN BY: Security controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE: Initial conditi "* at 0445 o The F.CCS Pump LPSI 2 is out of service for a pump bearing replacement. This pump is scheduled to be back in service within 24 hours. This is well within the 72-hour Technical Specification shutdown require: tent.
| |
| o Yesterday the plant tripped after the loss of a high line. The
| |
| [h
| |
| \ reactor is new back to full power. The reactor is at 600 MWt and has been operating at this level for the past 11 months except for yesterday's trip.
| |
| o The Burnup Number is 13.350 megawatt days / metric ton.
| |
| o The specific activity of the primary coolant has been determined to be: a) 15.0 uC1/gm gross beta /samma, and b) the Equivalent I-131 has been >1.1 uC1/gm for the post 47-3/4 hours.
| |
| o Meteorological conditions as indicated by the tower are as follows:
| |
| Upper Wind Speed Average (UPWSAV) = 4.0 mph .
| |
| Lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UPWDAV) = 10 Lower Wind Direction Average (LCWDAV) = 10 Delta Temperature (UPDTAV) = -1.0 F (N THIS IS A DRILL G .*********.******.*.******.***... . ..***..***...**.*.***...****.****.*..
| |
| | |
| YANKEE NUCLEAR POWER STATION Rev.I 3/24/87 GRADED EXERCISE p Page 6.1-5 V' MARCH 1987 FOR: Forward Control Point (FCP) MESSAGE N0. FCP-M-1 LOCATION: FCP TIME Upon Activation i
| |
| i GIVEN BY: FCP Controller THIS IS A DRILL DO NOT_ initiate actions affecting normal plant operations.
| |
| MESSAGE: initial conditions at 0445 o The ECCS Pump LPSI 2 is out of service for a pu:np bcaring replacement. This pump is scheduled to be back in service within 24 hours. This is well within the 72-hour Technical Specification shutdown requirement.
| |
| ] o Yesterday the plant tripped after the loss of a high line. The s
| |
| reactor is now tack to full power. The reactor is at 600 PfWt ar.d has been operating at this Icvel for the past 11 conti.s except for yesterday's trip.
| |
| o The turnup Number is 13.350 netawatt days /ectric ten.
| |
| o The specific activity of the primary coolant has been determined to be: a) 15.0 uct/gm gross beta /gama, and b) the Er;uivaler.t 1-131 has been >1.1 uCi/gm fcr the past 47-3/4 hours.
| |
| o Meteorological conditions as indicated by the tower are as follows:
| |
| Upper Wind Speed Average (UFWSAV) = 4.0 eph lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UFWDAV) = 10 tower Wind Direction Average (LCWDAV) = 10 Delta Tecperature (UPDTAV) = -1.0 F p THIS IS A DRILL
| |
| - ___ _-_____ _____ _ _ _ l
| |
| | |
| 1 Rev.1 3/24/87 YANKEE NUCLEAR POWER STATION Page 6.1- 6 A t GRADED EXERCISE i ,
| |
| %.) .
| |
| MARCH 1987 MESSAGE NO.
| |
| ESC-M-1 FOR: Engineerina Support Center (ESC) TIME Up n Activation LOCATION: ESC GIVEN BY: ESC Controller THIS IS A DRILL 00 NOT initiate actions aHecting nomal plant operations.
| |
| MESSAGE: initial conditions at 0445 o The ECCS Pump LPSI 2 is out of service for a pump bearing replacement. This pump is scheduled to be tack in service within 24 hours. This is well within the 72-hour Technical Specificatica shutdown requirement.
| |
| p o Yesterday the plant tripped after the loss of a high line. The
| |
| {
| |
| D reactor is new back to full power. The reactor is at 600 MWt and has been operating at this level for the past 11 r:onths execpt for yesterday's trip.
| |
| o Ite turnup Number is 13.350 messwatt days /cetric ten.
| |
| o The specific activity of the primary coolant has been determined to be: a) 15.0 uC1/gn gress teta/garra, and b) the Equivalent I-131 has been >1.1 uC1/g n for tt.e past 47-3/4 hours.
| |
| o Meteorological conditiens as indicated by the tower are as fo11cvs:
| |
| Upper Wind Speed Average (UPWSAV) = 4.0 mph Lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UPWDAV) = 10*
| |
| 14wer Wind Direction Average (LOWDAV) = 10 Delta Temperature (UPDTAV) = -1.0 F
| |
| *****e*******************************************************************
| |
| /%
| |
| THIS IS A DRILL (J) w e*e**********************************************************************
| |
| | |
| Rev. 1 YANKEE NUCLEAR POWER STATION 3/24/87 GRADED EXERCISE Page 6.1- 7 O MARCH 1987 FOR: Emergency Operations Facility MESSAGE NO. EOF-M-1 (EOF)
| |
| LOCATION: EOF TIME Upon Activation GIVEN BY: EOF Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| HESSAGE Initial conditions at G445 o The ECCS Pump LPSI 2 is out of service for a pump bearing replacement. This pump is scheduled to be back in service within 24 hours. This is well within the 72-hour Technical Specification shutdown requirement.
| |
| [O) o Yesterday the plant tripped after the loss of a high line. The reactor is now back to full power. The reactor is at 600 MWt and has been operatir.g at this level for the past 11 months except for yesterday's trip.
| |
| o The Burnup Number is 13,350 megawatt days / metric ton.
| |
| o The specific activity of the primary coolant has been determined to be: a) 15.0 uC1/gm gross bets / gamma, and b) the Equivalent I-131 has been >1.1 uC1/gm for the past 47-3/4 hours.
| |
| o Meteorological conditions as indicated by the tower are as follows:
| |
| Upper Wind Speed Average (UPWSAV) = 4.0 erb ;
| |
| lower Wind Speed Average (LOWSAV) = 4.0 mph Upper Wind Direction Average (UPWDAV) = 10' Lower Wind Direction Average (LOWDAV) = 10" Delta Temperature (UPCTAV) = -1.0 F THIS IS A DRILL (mv) *****************************************************c*******************
| |
| | |
| Rev. 1-3/24/87 YANKEE NUCLEAR POWER STATION Page 6.1- 8 GRADED EXERCISE I )
| |
| '/
| |
| 's- MARCH 1987 FOR: Dose Assesment Personnel MESSAGE N0.; EOF-M-2 LOCATION: EOF / cn / TSC / esc TIME: UPon Request GIVEN BY: EOF Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Generally cloudy conditions will prevail this morning as a weak offshore storm moves castward out of the area. Light northerly winds are expected. Temperatures will be in the mid 30's.
| |
| ( There is a slight chance of a passing shower or snow flurry.
| |
| O THIS IS A DRILL
| |
| {J )
| |
| _ - - . _ _ _ , - . . _ . , . , . . - ,_.. _ _ _ _ ...~. ,.-._
| |
| | |
| Rev. 0 1/26/87 YANKEE NUCLEAR POWER STATION Page 6.1-9 GRADED EXERCISE 77, (s-) MARCH 1987 FOR: OS.C Staff COMMAND NO.: Osc-C-1 LOCATION: OSC TIME: Upon Activatica GIVEN BY: OSC Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| FOR THE PURPOSES OF THE EXERCISE, OSC RESPONSE TEAMS i SHALL SIMULATE THE FOLLOWING:
| |
| 1.) Drawing and analysis of any radiological samples, and
| |
| (''}
| |
| kJ 2.) Entry into any radiologically controlled areas such as Vapor Container.
| |
| THIS IS A DRILL f' 3 U *************************************************************************
| |
| 8
| |
| | |
| Rev. 1 3/24/87 YANKEE NUCLEAR POWER STATION Page 6.1-10
| |
| - (m) GRADED EXERCISE MARCH 1987 FOR: control Room Staff MESSAGE NO.; CR-M-2 LOCATI0'N: control Room TIME: 0500 -
| |
| GIVEN BY: control Room Observer THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| *******************************************+**.**************************
| |
| MESSAGE:
| |
| A chemistry technician just called the Control Room to report a verified coolant sample with a specific activity greater than 1.1 (uci/gm) I-131 equivalent.
| |
| d THIS IS A DRILL
| |
| | |
| Rev. 0 1/26/87 YANKEE NUCLEAR POWER STATION Page 6.1- 11
| |
| /''T GRADED EXERCISE - -
| |
| MARCH 1987 FOR: Control Ronm Senff COMMAND N0.: CR-C'-1 LOCATION: Control Room TIME: Initiation of Shutdown GIVEN BY: Control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| FOR EXERCISE PURPOSES SHUTDOWN SHALL BE CONTROLLED NOT TO EXCEED A RATE OF 5% PER HOUR AT THIS TIME.
| |
| O
| |
| ( ,) THIS IS A DRILL
| |
| .**.*.....*.*.**..*...*.*....*...***..........*..***..*.*....*.W..*...**.
| |
| | |
| F Rev. 0 1/26/87
| |
| , . . . YANKEE NUCLEAR POWER STATION Page 6.1 12
| |
| / l- GRADED EXERCISE -
| |
| \g MARCH 1987 FOR: Control Room Staff COMMAND NO.:j CR-C-2 LOCATION: Control Room TIME: Initiation of Shutdown GIVEN BY: Control Room Controller THIS IS A DRILL l
| |
| DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| FOR EXERCISE PURPOSES, IN-STATION AO SHUTDOWN ACTIVITIES AND RESPONSES FROM THE CONTROL ROOM SHALL BE SIMULATED.
| |
| O r
| |
| ( THIS IS A DRILL
| |
| | |
| Rsv. 0 1/26/87 YAtlKEE flVCLEAR POWER STATION Page 6.1 13 GRADED EXERCISE
| |
| -( MARCH 1987
| |
| "()
| |
| Shift Supervisor C0!! MAND NO.:
| |
| CR-C-3 FOR: _ _ _ .
| |
| LOCATION: Control Room -_
| |
| __ TIME: 0545 if Unusual Event has not been ~~
| |
| declared.
| |
| GIVEN BY: Control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| DECLARE AN UNUSUAL EVENT BASED UPON FUEL DAMAGE INDICATION VERIFYING AN INCREASE IN FAILED FUEL
| |
| > 0.1% IN 30 MINUTES, O
| |
| THIS IS A DRILL O *************************************************************************
| |
| 'e
| |
| .n, - - , - - , - - - - - - - - . - , - , , - - , - - - , _ -
| |
| | |
| Rsv. 0 1/26/87 Page 6.1 14 YANKEE NUCLEAR POWER STATION
| |
| <-'sr GRADED EXERCISE t
| |
| \s_s/ HARCH 1987 FOR: Control Room /all players COMMAND N0.:j CR-C-4 LOCATION: Control Room /as appropriate TIME: if vc entry is discussed GIVEN BY: Control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| FOR PURPOSES OF THE EXERCISE, ANY ATTEMPTS TO ENTER THE VAPOR CONTAINER OR OTHER RADI0 LOGICALLY CONTROLLED AREAS SHALL BE SIMULATED.
| |
| O 4
| |
| THIS IS A DRILL
| |
| (
| |
| - . . _ ._, . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . , . . _ _ , -_ . . _ _ . . _ . . , . _ . , . . , , . _ . _ . _ . _ _ _ . _ _ _ ._ ______.r____.
| |
| | |
| Rav. 0 YANKEE NUCLEAR POWER STATION s GRADED EXERCISE Page 6.1 15 MARCH 1987 FOR: Plant Emergency Director MESSAGE NO.; CR-M-2a TIME: 0330 LOCATION: Control Room GIVEN BY: Control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| The Bleedline radiation monitor is alarming.
| |
| O G
| |
| { THIS IS A DRILL
| |
| {} *....*...*..**.............................................*.............
| |
| | |
| Rev. 0 1/26/87 Pr.ge 6.1 16 YANKEE NUCLEAR POWER STATION
| |
| (~'T GRADED EXERCISE -
| |
| u)
| |
| MARCH 1987 FOR: Control Room Staff COMMAND NO.: j CR-C-5 L
| |
| LOCATION: Control' Room TIME: Initiation of Shutdown _
| |
| GIVEN BY: Control Room Controller THIS IS A DRILL DO NOT_ initiate actions affecting normal plant operations.
| |
| ******************************.+***.**************************************
| |
| MESSAGE:
| |
| '' FOR EXERCISE PURPOSES, SHUTDOWN SHALL BE CONTROLLED HOT TO EXCEED A RATE OF 10% PER i HOUR AT THIS TIME.
| |
| (<~
| |
| , V r
| |
| r a e
| |
| 5
| |
| ( THIS IS A DRILL
| |
| | |
| YANKEE NUCLEAR POWER STATION
| |
| /~% GRADED EXERCISE 3/24/87 '
| |
| - ( ,) Page 6.1-17 MARCH 1987 EOF Staff COMMAND NO.: , EOF-C-1 FOR:
| |
| LOCATION: Emergency Operations Facility TIME; Prior to 0630 GIVEN BY: EOF Controller
| |
| ********************.**************************************************** i l
| |
| THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| FOR EXERCISE PURPOSES,D0 NOT OPEN COMMUNICATIONS WITH THE STATE EOCs UNTIL AFTER 0630 AM.
| |
| n U
| |
| THIS IS A DRILL
| |
| (
| |
| ******************************************************************+******
| |
| | |
| l nav. 1 l 3/24/87 YANKEE NUCLEAR POWER STATION Page 6.1- 18 GRADED EXERCISE
| |
| ( ,),
| |
| MARCH 1987 FOR: Plant Emergency Director COMMAND NO.: CR-C-6
| |
| , LOCATION: Control Room TIME: _
| |
| 0545 if Alert' f- has not been declared GIVEN BY: Control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| l DECLARE AN ALERT BASED UPON A SEVERE LOSS OF FUEL CLADDING CONDITIONS.
| |
| v i
| |
| THIS IS A DRILL A
| |
| (_) ********************************.****************************************
| |
| | |
| Rev.1 0 :- YANKEE NUCLEAR POWER STATION 3/27/87
| |
| ' ';f] ~ GRADED EXERCISE Page 6.1-18a V
| |
| MARCH 1987
| |
| . -1 Plant Emergency Director CR-C-6a FOR: C0!EAND NO.: ;
| |
| 0 00 LOCATION: . Control'Roo(,3 TIME:
| |
| "*' 1 ~
| |
| * "'" 11*"
| |
| t GIVEN BY:
| |
| ~
| |
| 1
| |
| - THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
| |
| f{3 *************************************************************************
| |
| MESSAGE:
| |
| P FOR EXERCISE PURPOSES, SHUTDOWN WILL BE CONTROLLED NOT TO EXCEED A RATE OF 20 % PER HOUR AT THIS TIME.
| |
| f 4
| |
| i f-s THIS IS A DRILL
| |
| | |
| - Rev. 0 1/26/87 YANKEE NUCLEAR POWER STATION Page 6.1- 19
| |
| /~'T GRADED EXERCISE V
| |
| MARCH 1987 Plant Emercency Director MESSAGE NO.: CR-M-3 FOR:
| |
| TIME: 0729 LOCATION: control Room GIVEN BY: control Room observer THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| l
| |
| * NESSAGE:
| |
| The annunciator for detection of lou N2 Pressure in the upper piston cylinder of Honreturn Valve No.4 (NRV-405-D) is Alarming.
| |
| 4 e
| |
| l() THIS IS A DRILL e,,, y - . - - , . - , , -
| |
| | |
| .Rev. O' 1/26/87 YANKEE NUCLEAR POWER STATION Page 6.1 20 7-- GRADED EXERCISE A3'' ) MARCH 1987 FOR: Plant Emergency Director MESSAGE NO ; CR-M-4 LOCATION: control Room TIME: 0730 GIVEN BY: control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| The Reactor Trip Monitor and The Turbine Trip Monitor are alarming.
| |
| l''T U
| |
| THIS IS A DRILL
| |
| _,m .- .., _ , . . _ , , - - - . - - , , , , . . , 7 - , ,, .,-, - . .._ ,-_ _ _ _, ___ _
| |
| | |
| Rev. O 1/26/87 Page 6.1 21 YANKEE NUCLEAR POWER STATION
| |
| () GRADED EXERCISE MARCH 1987 FOR: PTRnt vmorooncv ner cene MESSAGE NO.: ,
| |
| Control Room TIME: 0731 LOCATION:
| |
| GIVEN BY: control Room Observer THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Continued attempts to close Nonreturn Valve No.4 (NRV-405-D) from the Control Room are unsuccessful.
| |
| (
| |
| e
| |
| ( THIS IS A DRILL
| |
| - , , - . , . - .,-.n.-- , , - , - - - - , ,-+-,-. _-~ - -
| |
| ,a ,,,---,.----.-,n . - , - - . , - . , - -,
| |
| | |
| Rev. 0 1/26/87
| |
| # ~
| |
| m YANKEE NUCLEAR POWER STATION GRADED EXERCISE . :
| |
| MARCH 1987
| |
| -M-6 Plant Emergency Director MESSAGE NO.:
| |
| FOR:
| |
| TIME: 0731 LOCATION: Control Room GIVEN BY: cnnern1 nnne ns orvo.
| |
| THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| ESSAGE:
| |
| Main Coolant Isolation Valve No. 4 alarms indicating failure to close upon initiation of isolation. The limit switch light does not go out. Continued attempts to reset from the Control Room are unsuccessful.
| |
| s 1
| |
| O THIS IS A DRILL
| |
| = , - - .-e,,-e ,---,,,,----,,,-,,,,,,e,-.,g-r_ - , - - , , ,m -
| |
| , - , -m.,--.m, , , , , _ - - , -,r, v., , , _ - - - , - , , , , - - , , , . - - , , , _ _ , - , , - , , , , , , , , , , , - -
| |
| | |
| Rev. 0 1/26/87 Page 6.1 23 YANKEE NUCLEAR POWER STATION . .
| |
| GRADED EXERCISE : :
| |
| MARCH 1987 Plant Emergency Director MESSAGE NO.; CR-M-7 FOR: _
| |
| LOCATION: control Room TIME: 0731 GIVEN BY: control Room Observer THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| A maintenance foreman just called to report audible and visual observation of a break in the steam line just downstream of
| |
| ~
| |
| the Nonreturn valves.
| |
| O l
| |
| .***.***.*..... ....*** . . ............. .........** **a .** * ~ ~
| |
| THIS IS A DRILL
| |
| | |
| i IfE$/b7 l Page 6.1 24 l YANKEE NUCLEAR POWER STATION- i GRADED EXERCISE
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| (
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| s 8,
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| 1 N_/ MARCH 1987 FOR: Plant Emergency Director MESSAGE N0.: CR-M-8 LOCATION: Control Room TIME: 0735 GIVEN BY: Control Room Controller THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| The Air Ejector radiation monitor is alarming.
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| THIS IS A DRILL 1
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| .- -. - , _ _ . . . , _ _ , _ . . ..m._m., _ . . . , . . , _ , . _ _ _ , . _ . . .
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| Rev. 0 1/26/87
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| - Page 6.1 25 YANKEE NUCLEAR POWER STATION GRADED EXERCISE l
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| 1 MARCH 1987 l MESSAGE NO.: nsc-M-9 l
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| FOR: Osc Team Main Coolant Pump Isolation LOCATION: Valve #4 circuit Bronker Psinal TIME: o7u OSC Observer GIVEN SY.
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| THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
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| MESSAGE:
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| Continued attempts to reset the main coolant pump isolation valve #4 circuity are unsucessful. You observe that the contact for the middle line is missing.
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| e' THIS IS A DRILL
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| I Rev. 0 )
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| 1/26/87 l YANKEE NUCLEAR POWER STATION Page 6.1 GRADED EXERCISE
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| ! MARCH 1987
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| \_ /
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| FOR: Plant Emergency Director COMMAND NO.: CR-C-7 LOCATION: , Control Room TIME: 0750 if General Energency has not been dc:-
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| GIVEN BY: Control Room Controller THIS IS A DRILL 00 NOT initiate actions affecting normal clant operations.
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| 1 MESSAGE:
| |
| DECLARE A GENERAL EMERGENCY BASED UPON LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS WITH A POTENTIAL LOSS OF 3RD BARRIER.
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| Iv g-~3 THIS IS A DRILL
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| - 1
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| \~ / *************************************************************************
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| i Rev. O 1/26/87 Page 6.1- 27 O
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| t I YANKEE NUCLEAR POWER STATION -
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| GRADED EXERCISE
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| ' MARCH 1987_
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| MESSAGE NO.; osc-M-3 FOR:
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| osc Team Main Coolant Pump Isolation circuit Breaker Panel TIME: __osi s LOCATION: v.,o. 33 GIVEN BY: osc observer THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| The breaker circuitry for Main Coolant Pump Isolation Valve number 4 has been successfully realigned and the valve is operable.
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| * ** ** **e e .
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| * e e e * ** e e . . . . * * . * ** * ** * . . . . . . . . . . ,
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| * e . ** e . e * * *
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| ( THIS IS A DRILL l ****** ........**..***....***..............****
| |
| -r_. , _ , , . _ . _ _ - - . . , ..._,,__.,.___-,-r
| |
| . . _ - . _ , . . . . . _ . . _ _ _ , . - , , , _ _ - - . . _ _ . _ . _ _ . _ _ _ . . - - _ , . . , ,, ,.,__m....__ .-,, . _ . -_
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| Rev. 0 1/26/87 Page 6.1 28
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| < YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 FOR: ne mm MESSAGE NO.; osc-M-4 LOCATION: Main steam Line Inspection TIME: 0915 GIVEN 8Y: osc controller e*************eee********************************************************
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| - THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
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| MESSAGE:
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| Upon inspection of the number 4 steam line you observe a small crack in the pipe at one of the welded joints.
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| O
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| 'f 0
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| THIS IS A DRILL
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| .-+ - ----------,----w-re, ,,%,. - - - - - - w----,,-- - - - . , - - - - - - . - - - , , - - - - - - .
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| i*- e-- 4 1 A - - 4 J .,wn A e A l
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| I t_,
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| d YANKEE NUCLEAR POWER STATION
| |
| ~
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| GRADED EXERCISE MARCII 1987 k l 1
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| 4 4
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| t s .
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| 4 7
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| l' 6.2 NEWS MEDIA CENTER MESSAGES j
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| 4 1
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| l i
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| 1 l
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| i 1
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| i k~
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| h lO 1
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| r -- y - - - - - ,y-. ...-.-4,_. .- . ._,.,. - -..,-,..-..,--,.,,..-,,,_-.-_.,-,,,._....-..._,..._--_,m...,_.-_... ., - ,,_.mmm.-,-.-,,
| |
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| f Rev. 1 s 3/21/87 gd Pg. 6 2-1 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 Technical Representative MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| Reporter, WMNB, North Adams, MA Does Yankee Rowe have the same design and construction as Chernoby1?
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| O .........*........................**.....................................
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| THIS IS A DRILL
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| - . . . _ . _ . _ . . . . _ - . , _._._.____.,,._..__...,___...._,_.,,..__.s.____., - . . - . . - . . _ , _ . - - . _ . . . . _ , _ _
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| Rev. 1
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| ~
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| 3/21/87 t Pg . 6. 2-2 YANKEE NUCLEAR POWER STATION GRADE 0 EXERCISE
| |
| - MARCH 1987 MESSAGE NO.; NMC-M-FOR: Public Affairs Director News Media Center TIME:
| |
| LOCATION:
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| GIVEN BY: News Media Controller THIS IS A DRILL 001:0T_ initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, North Adams News How will we know if our food is safe to eat? I've heard that a release of radiation can spread for hundreds of miles which means that alot of dairy farms and other food processing facilities could be affected.
| |
| Are there procedures for testing food products for radioactive contamination? In short, is our milk safe to drink? If so, how do you know?
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| l l
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| l O ...................*.....................................................
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| THIS IS A DRILL
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| J Rev. 1 3/21/87 9* *
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| ~
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 MESSAGE NO.; NMC-M-FOR: Public Affairs Director LOCATION: News Media center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| correspondent, Boston Globe What are the expected health affects from the type and amount of radiation being released?
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| (
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| O .........................................................................
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| THIS IS A DRILL j
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| i l
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| Rev. 1 O 3/21/87 V Pg. 6 2-4 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
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| * MARCH 1987 l
| |
| MESSAGE NO.; NMC-M-FOR: Public Affairs Director News Media Center TIME:
| |
| LOCATION:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| . Reporter, WPLJ TV, Greenfield, MA What is being done to stop the release?
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| O .........................................................................
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| THIS IS A DRILL
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| J 4
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| Rev. 1 3/21/87 O.
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| t .
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| Pg . 6. 2-5 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| * MARCH 1987 FOR: Public Affairs Director MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| I understand there is presently a release of radiation from the plant, how long is this release expected to O occur?
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| O .........................................................................
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| THIS IS A DRILL
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| Rev. 1 p- 3/21/87
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| ., -( Pg. 6.2-6 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 FOR: Public Affairs Director MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
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| MESSAGE:
| |
| Reporter, WKLV, Greenfield, MA What kind of radiation will (is being) released?
| |
| (
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| l O .........................................................................
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| I THIS IS A DRILL
| |
| .. - .- - _ ~ , , _ . _ _ . _ - _ . , . . . - . _ . . , ~ . _ _ , , _ . . . _ . . . . _ , _ _ . . . _ - . . _ . . , - , _ . _ _ _ - . - _ _ , _ _ _ . - . . _ . . ,
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| D Rev. 1 n 3/21/87 U YANKEE NUCLEAR POWER STATION Pg. 6. 2-7 GRADED EXERCISE MARCH 1987 FOR: Public Affairs Director MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL DO NOT_ initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, WHAI, Greenfield, MA What is the likelihood of this accident turning in O to a Chernobyl?
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| l l
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| l i
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| O .........................................................................
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| THIS IS A DRILL l
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| - - . - - . - - - _ . - ~ , - , _ - - - - , . - - . - - . _ - - - - - - - - - .
| |
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| e Rev. 1 3/21/87 y, Pg . 6. 2-8 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 FOR: Public Affairs _Direc_toL_ _ MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, Greenfield Gazette n With all the publicity regarding accidents linked
| |
| (' ) to drugs in the workforce, for example the AMTRAK accident, how can we be certain that drug abuse was not involved in this incident?
| |
| O *********************************************************
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| I THIS IS A DRILL
| |
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| Rev. 1 3/21/87
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| [-) Pg. 6.2-9 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 Public Affairs Director MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL DO NOT_ initiate actions affecting normal olant operations.
| |
| MESSAGE:
| |
| Reporter, WMNB, North Adams, MA Are.there procedures for periodically checking all equipment and systems to prevent accidents from happening?
| |
| Was or could anything have been done to prevent this accident from occurring and then getting worse?
| |
| O .........................................................................
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| TilIS IS A DRILL
| |
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| 4-Rev. 1 3/21/87
| |
| (-
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| ~
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| YANKEE NUCLEAR POWER STATION Pg. 6 2-10 GRADED EXERCISE
| |
| - MARCH 1987 Public Affairs Director, MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller TIIIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Correspondent, Boston Globe Rowe is one of the older operating reactors in the United States. Did the age of the plant contribute to the cause of the accident?
| |
| O .........................................................................
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| THIS IS A DRILL
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| *eee**.e...e.......*....*..*****************.*****.*..*******************
| |
| | |
| i Rev. I 3/21/87 b)
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| YANKEE NUCLEAR POWER STATION Pg . 6. 2-11 GRADED EXERCISE MARCH 1987 FOR: Technical Representative MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, WBTZ, Bennington Q What is the weather forecast for the day?
| |
| 'V Will it have any affect on the direction of the plume?
| |
| O .........................................................................
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| THIS IS A DRILL
| |
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| gS Rev. 1 Q 3/21/87
| |
| : g. 6 2-12 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 FOR: Technical R_epresentative MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, WKVT, Springfield, MA p What is the extent of the damage? How long will it
| |
| ( take to repair? Will the cost be passed on to the ratepayer?
| |
| i.
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| i l
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| l THIS IS A DRILL I ..........................*********************...*****""""""*"***
| |
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| s Rev. 1 3/23/87 Pg. 6. 2-13 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 Rumor Control MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller THIS IS A DRILL DO NOT_ initiate actions affecting normal plant operations.
| |
| t i
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| MESSAGE:
| |
| To be called in on rumor control telephone number.
| |
| p- "THIS IS A DRILL.
| |
| Is the plant having a meltdown? If not, will it
| |
| ; happen soon? "
| |
| t i
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| (
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| , O **************************************************************
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| THIS IS A DRILL l
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| P Rev. 1 p 3/23/87 Cl YANKEE NUCLEAR POWER STATION W . 6. 2-14 GRADED EXERCISE
| |
| * MARCH 1987 Rumor Control MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Me'dia Center TIME:
| |
| GIVEN BY: NMC Controller
| |
| *****.**************************+.*************************************.*
| |
| THIS IS A DRILL 00 NOT_ initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| To be called in on rumo:: control telephone number.
| |
| < "THIS IS A DRILL.
| |
| ,* I live about 12 miles from the plant. Should I prepare to evacuate? "
| |
| O 0
| |
| O *.............. .......... .......*.............................* ....
| |
| THIS IS A DRILL e.*****.e........***.*.**.*e.*****.**.**.**.****...****.****.********.ee.
| |
| | |
| l t
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| [
| |
| Rev. I m 3/23/87 h, Pg. 6 2-15 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| * MARCH 1987 Rumor Control MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| To be called in on rumor control telephone number.
| |
| "THIS IS A DRILL.
| |
| \ My friend's brother works at the Rowe plant. He just told her that the accident is alot more serious than what the media is reporting. Are we being told the truth? "
| |
| t O ....*. . .... *......*.. ............................................ .
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| THIS IS A DRILL
| |
| | |
| k s l
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| Rev. 1 f p) l
| |
| ( 3/23/87 W. 6 2-16 YANKEE NUCLEAR POWER STATION GRADED EXERCJSE
| |
| - MARCH 1987 FOR: Rumor Control MESSAGE NO.' NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller
| |
| ' THIS IS A DRILL
| |
| #. DO NOT_ initiate actions affecting normal plant operations.
| |
| t i MESSAGE:
| |
| To be called in on rumor control telephone number.
| |
| , "THIS IS A DRILL.
| |
| 'O Q e I've heard that there have been a number of injuries at the plant. My friend works there - how can I
| |
| , find out if he's hurt? "
| |
| 6 q
| |
| a 1.
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| 4
| |
| ?
| |
| i.
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| I
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| ((
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| O ... .......... ....... . .................................._........
| |
| THIS IS A DRILL
| |
| | |
| Rev. 1
| |
| (~. ' 3/23/87 s Pg . 6. 2-17 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| * MARCH 1987 Rumor Control MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller .
| |
| THIS IS A DRILL DO NOT_ initiate actions affecting normal plant operations.
| |
| t MESSAGE:
| |
| To be called in on rumor control telephone number.
| |
| "THIS IS A DRILL.
| |
| ,v My dog has been outside. Is he contaminated?"
| |
| 4 l-O o
| |
| 9 O ....*. ......**....**.**** . ..*.........*..***.......*.* .. ....
| |
| THIS IS A DRILL
| |
| *********w.,*?***(.********************************************************
| |
| | |
| k Rev. 1 (1
| |
| s 3/23/87 Pg . 6. 2-18 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 Rumor Control MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| ************** .**********w**********************************************
| |
| MESSAGE:
| |
| To be called in on rumor control telephone number.
| |
| ,q 5 "THIS IS A DRILL.
| |
| What are the symptoms of radiation sickness? How 1
| |
| v long will it be before I start feeling sick?"
| |
| l t
| |
| l l
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| l O ...... . .... .......... . ............................... .. ....
| |
| THIS IS A DRILL l
| |
| t i
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| )
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| Rev. 1 p 3/23/87 v Pg. 6.2-19 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987 FOR: Rumor Control MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| i MESSAGE:
| |
| To be. called in on rumor control telephone number.
| |
| "THIS IS A DRILL.
| |
| O Has there been a release of radiation? How do the U plant operators know which direction it's going?
| |
| When will I be able to see it? taste it?"
| |
| b a *************************************************************************
| |
| THIS IS A DRILL
| |
| | |
| /
| |
| Rev. 1 p 3/23/87 V Pg . 6. 2-20 YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| - MARCH 1987_
| |
| FOR: Rumor Control MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: NMC Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| To be called in on rumor control telephone number.
| |
| ~
| |
| "THIS IS A DRILL.
| |
| I live west of the plant. My five year old son is throwing l
| |
| up! Help me!."
| |
| i 1
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| ?
| |
| O 4
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| I l
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| i O ...... ....... .......... ............................................
| |
| THIS IS A DRILL
| |
| | |
| Iiev . 1 3/21/87 Pg . 6 2-21 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 MA Representative MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION; News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS 13 A DRILL 00 NOT_ initiate acticas affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, WKGN, North Adams, MA Is the Governor aware of this situation? What action has he taken at this time?
| |
| t I
| |
| i O
| |
| THIS IS A ORILL l
| |
| | |
| i n
| |
| Rev. 1 3/21/87 ,
| |
| Pg. 6 2-22 l YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 MA Representative MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS 13 A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| p Reporter, W KLV , Springfield, MA O
| |
| Do you anticipate making any protective action recommendations to the public within the next few hours?
| |
| f THIS IS A DRILL
| |
| | |
| Rev. 1 7.- s 3/21/87 Q YANKEE NUCLEAR POWER STATION Pg. 6. 2-23
| |
| : GRADED EXERCISE MARCH 1987 FOR: VT Representative MESSAGE NO.; NMC-M-LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS IS A DRILL 00 NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, WHIK, Brattleboro, VT Will the State of Vermont issue the same protective action O' recommendations as Massachusetts?
| |
| o O ......*..................................................................
| |
| THIS IS A DRILL
| |
| - - . , - . . , . , - - _ . - . _ . , _ - - _ .- _. . _ - - , _ _ _ . - . - - . - _ - . __ . - ~ _ _ _ - - _ - - - - - - - -
| |
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| I l
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| P
| |
| \
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| R'ev. 1 .
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| p(j 3/21/87 Pg. 6. 2-24 YANKEE NUCLEAR POWER STATION j GRADED EXERCISE MARCH 1987 VT Representative MESSAGE NO.; NMC-M-FOR:
| |
| LOCATION: News Media Center TIME:
| |
| GIVEN BY: News Media Controller THIS 13 A DRILL DO NOT initiate actions affecting normal plant operations.
| |
| MESSAGE:
| |
| Reporter, WMNO, Brattleboro, VT Should the public take any precautionary measures at this time?
| |
| O .......................................................................**
| |
| THIS IS A DRILL
| |
| | |
| O
| |
| ! YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 O
| |
| 7.0 STATION EVENT DATA O
| |
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| J4-4. J 4_.
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| O l l
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| l YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 O
| |
| I
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| , 7.1 EVENT
| |
| | |
| ==SUMMARY==
| |
| | |
| l l
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| i l
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| l l
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| 1 Rev.0 )
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| O 1/27/87 Page 7.1-1
| |
| )
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| l l
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| YANKEE NUCLEAR POWER STATION l GRADED EXERCISE l MARCH 1987 l 7.1 EVENT
| |
| | |
| ==SUMMARY==
| |
| | |
| EVENT DESCRIPTION 7.2.1 Nonreturn Valve Number 4 NRV-405-D fails to close.
| |
| 7.2.2 Main Coolant Isolation Valve MC-MOV-319 fails to close
| |
| , upon intitiation of isolation.
| |
| i i
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| I i
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| (
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| I 1o I
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| l
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| . . _ _ . ._ . _ _ . _ . . _m . . . _ .. __ .
| |
| i 4
| |
| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 l
| |
| 7.2 EVENT MINI SCENARIOS i
| |
| l l
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| l t
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| . _ ~ . . _ . - _ . _ _ _ _ _ _ . _ _ _ . . _ _ _ _ _ - . _ _ . _ _ _ _ . . . , _ . , . _ , . _ _ . , . . _ _ _ _ _ - _ . _ _ . , _ . . _ . _
| |
| | |
| Rev. 0 2/7/87 Page 7.2.1-1
| |
| \ /
| |
| V MINISCENARIO 7.2.1 NONRETURN VALVE NO. 4 FAILURE TO CLOSE 1.0 General Description Each main steam line has a nonreturn valve located downstream of their respective safety relief valves but prior to joining with adjacent steam lines. In the event of a steam line break in any of the systems, the Nonreturn Valves (NRVs) are used to control all four systems and steam generator pressures and levels. In general, operating procedures direct operators to close the NRVs in all four systems if a break occurs in one main steam line. Jhis is done primarily to keep control of the unaffected SGs and to keep steam from those adjacent systems from flowing out the break in the affected line.
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| The NRVs are piston cylinders with hydraulic oil in the lower plenum and high nitrogen pressure in the upper plenum. To shut the valve, an
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| \ -
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| electronic close signal releases the hydraulic oil and uses the high nitrogen pressure to force the piston down.
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| At 0729 the operators receive an alarm in the Control Room annunciating trouble with No. 4 (NRV-405-D). A light on the NRV control cabinet indicates detection of a low N 2Pressure in'the nitrogen accumulator (upier piston cylinder).
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| When the postulated main steam line break occurs in Loop 4 at 0730, the i operators close NRVs 1, 2, and 3. Attempts to close NRV No. 4 are unsuccessful due to the loss of nitrogen in the upper piston cylinder.
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| It is possible that nitrogen leaked out slowly through the 0-ring sealed connection to the accumulator charging valve. This causes the NRV to remain open even after the close signal has dumped the hydraulic oil
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| ! from the lower piston cylinder.
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| 1419e
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| Rev. 0 2/7/87 y~ Page 7.2.1-2
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| ~d 2.0 Descr!jtion of Player Observations / Responses Continued attempts to shut NRV No. 4 from the Control Room are unsuccessful. The operators would probably dispatch an OSC team to try to shut the valve as soon as plant and area radiation conditions permit.
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| By about 0830 MSL No. 4 pressures and radiation levels have decreased to the point where the emergency response organization would consider sending a repair team in to shut NRV No. 4. The team may attempt to either shut the valve manually or they may attempt represssurizing the upper cylinder with nitrogen to close the valve.
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| As the repair team approaches the NRV location, the exercise observers should provide area and contamination radiation levels as it is requested or would normally by available. Area contamination level and
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| - survey maps are provided in Section 9.0.
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| (
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| As the NRV No. 4 response team completes any of - their simulated repair activities on the valve, the observer will tell them that their actions are successful and that the NRV No. 4 is closed. As long as this activity is not completed prior to 0830, there is little influence over the scenario operational data.
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| Rev. 0 2/7/87 t''N Page 7.2.2-1 i )
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| MINISCENARIO 7.2.2 MAIN COOLANT INSOLATION VALVE NO. 4 FAILURE TO CLOSE 1.0 General Description As soon as the Control Room operators observe which main steam line has the break, they will attempt to isolate that system. When they do this, they receive alarm indications that the No. 4 Main Coolant Isolation Valve (MC-MOV-31A) fails to close upon initiation of isolation. The
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| : t. limit switch light in the Control Room does not go out. Although the associated main coolant pump has been tripped, there is still a possible primary to secondary leak rate of 120 gpm until the valve is closed and the secondary system is completly isolated.
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| 2.0 Description of Player Observations / Responses Continued attempts to reset and close the isolation valve from the Control
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| ()
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| Room, all unsuccessful. Due to the high coolant activities and the release in progress, the operators would dispatch a maintenance technician from the OSC to reset and inspect the No. 4 main coolant isolation valve circuit breaker.
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| When the OSC team reaches the circuit breaker in the Switchgear Room, they attempt to reset the valve there. The observer should tell them that attempts to reset the valve are unsuccessful._ The OSC team also observes that the contact for the middle line of the breaker is missing. When they open the circuit breaker box, they observe pieces of the burned away contact on the bottom of the box. They see the contact when they open the motor controls.
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| '/''N 1419e
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| Rev. 0 2/7/87 Page 7.2.2-2 An OSC team should be dispatched to obtain a new contact for the main coolant isolation valve from the Spare Parts Room. By 0815 the OSC team should have returned to the Switchgear Room with a new contact for the main coolant isolation valve.
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| The OSC team successfully isolate and test the breaker circuitry. They realign the circuitry to the valve and the observer tells them that the valve is operable. By 0817 the operators successfully isolate Loop 4.
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| d lO 1419e O
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| f 4
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| -. -- --,-.,,--...,--,,,,--,_,,.n.- n - . , _, , , , , , . , , - , . - - , . , , . , , , , , , _ . , _ _ _ - , _ . , , , , _ , , , , , , , , , , , , , , - , . --,-.-,,
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| O YANKEE NUCLEAR POWER STATION GRADED EXE' MARCH 1987 8.0 OPERATIONAL DATA O
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| O 1 28-
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| Rev. 1
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| -3/21/87 J Page 8.0-ta-YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 I ll 8.0 OPERATIONAL DATA Point Point ID Name Description Units Time 0445 0500 0515 0530 -4 I
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| 1 PZRL Pressurizer Level, Wide Range INCHES 120 118 120 118 )
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| 2 MCPRES1 Main Coolant Pressure, Loop 1 PSIG 2020 2000 2020 2000 3 MCPRES2 Main Coolant Pressure, Loop 2 PSIC 2015 2000 2020 2000 4 MCPRES3 Main Coolant Pressure, Loop 3 PSIG 2010 2000 2020 2000 Loop 4 SI Pressure PSIG 2015 2000 2020 2000 5 TH1 Hot Leg Temperature, Loop 1 DEG. F 552 552 551 552 6 TH2 Hot Leg Temperature Loop 2 DEG. F 552 552 551 552 7 TH3 Hot Leg Temperature, Loop 3 DEG. F 550 550 550 551 8 TH4 Hot Leg Temperature, Loop 4 DEG. F 556 550 550 550 9 TC1 Cold Leg Temperature, Loop 1 DEG. F 512 512 512 512 10 TC2 Cold Leg Temperature, Loop 2 DEG. F 512 512 512 511 11 TC3 Cold Leg Temperature, Loop 3 DEG. F 510 512 511 512 12 TC4 Cold Leg Temperature, Loop 4 DEG. F 510 512 510 512 13 SGWRL1 Steam Generator Level, Loop 1 FEET 22 22 22 22 14 SGWRL2 Steam Generator Level, Loop 2 FEET 22 22 22 22 15 SGWRL3 Steam Generator Level, Loop 3 FEET 22 22 22 22 16 SGWRL4 Steam Generator Level, Loop 4 FEET 22 22 22 22-17 SGP1 Steam Generator Pressure, Loop 1 PSIG 500 500 500 500 18 SGP2 Steam Generator Pressure, Loop 2 PSIG 500 500 .500 500 19 SGP3 Steam Generator Pressure, Loop 3 PSIG 500 500 500 500 20 SGP4 Steam Generator Pressure, Loop 4 PSIG 500 500 500 500 21 _NPPR6 Nuclear Power Range, Channel 6 PERCENT 100 100 100 99 22 NPPR7 Nuclear Power Range, Channel 7 PERCENT 100 100 100 99 23 NPPR8 Nuclear Power Range, Channel 8 PERCENT 100- 100 100 99 24 NPIR4 Nuclear Inter. Range, Channel 4 AMPERES 1E-4. 1E-4 1E-4 1E-4 1228e
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| O O O Rev. 1 3/21/87 Page 8.0-2a YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time 0445 0500 0515 0530 25 NPIR3 Nuclear Inter. Range, Channel 3 AMPERES 1E-4 1E-4 1E-4 IE-4 ,
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| 26 NPSR2 Nuclear Source Range, Channel 2 CPS -- -- -- --
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| l 27 NPSR1 Nuclear Source Range, Channel 1 CPS -- -- -- --
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| l 28 SF1 Steam Flow, Loop 1 LBS/HR x.103 600 600 600 600 l 29 SF2 Steam Flow, Loop 2 LBS/HR x 103 600 600- 600 600 !
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| 30 SF3 Steam Flow, Loop 3 LBS/HR x 103 600 600 600 600 31 SF4 Steam Flow, Loop 4 LBS/HR x 103 600 600 600 600 32 FWF1 Feedwater Flow, Loop 1 LBS/HR x 103 600 600 600 600 l 33 FWF2 Feedwater Flow, Loop 2 LBS/HR x 103 600 600 600 600- l 34 FWF3 Feedwater Flow, Loop 3 LBS/HR x 103 600 600 600 600 35 FWF4 Feedwater Flow, Loop 4 LBS/HR x 103 600 600 600 600 40 SLRAD1 Steam Line Radiation, Loop 1 MR/HR 0.5 0.5 0.6- 0.6 i 41 SLRAD2 Steam Line Radiation, Loop 2 MR/HR 0.5 0.5 0.6 0.6 l 42 SLRAD3 Steam Line Radiation, Loop 3 MR/HR 0.1 0.1 0.1 0.1 43 SLRAD4 Steam Line Radiation,Toop 4 MR/HR 0.5 0.5 0.6 0.6 44 VCPLR VC Pressure, Low Range PSIG 1.2 1.2 1.2 1.2 45 VCPHR1 VC Pressure, High Range 1 PSIG <2 <2 <2 <2 46 VCPHR2 VC Pressure, High Range 2 PSIG <2 (2 <2 <2 47 VCRAD1 VC Radiation, Channel 1 R/HR <1.0 <1.0 <1.0 <1.0 ,
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| 48 VCRAD2 VC Radiation, Channel 2 R/HR <1.0 <1.0 <1.0 <1.0 l 49 VCH1 VC Hydrogen, Channel 1 PERCENT 0 0 0 0 1228e
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| O O O
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| 'Rev. 1 3/21/87
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| .Page 8.0-3a
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| ; YANKEE NUCLEAR POWER. STATION GRADED EXERCISE
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| ; MARCH 1987
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| ; Point Point
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| : ID Name Description Units Time
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| ) 0445 0500 0515 0530 l
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| j 50 VCH2 VC Hydrogen, Channel 2 PERCENT 0 0 0 0
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| ; 51 VCL1 VC Flood Level, Channel 1 FEET ~ 0 0- 0 0
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| ] 52 VCL2 VC Flood Level, Channel 2 FEET 0 0 0- 0 59 AEJRM Air Ejector Radiation Monitor CPM 250 500 800 1200-60 SITL Safety Injection Tank Level FEET 27 27 27 27 61 DWSTL Demineralized Water Tank Level FEET 10-13 13- 13 13 i
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| 62 IAPA Instrument Air Pressure, Header N PSIG 95 95 95 95
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| ) 63 IAPB Instrument Air Pressure, Header S PSGI 95 95 95 95' 67 VBUSV Vital Bus Volts (Not in CR) VOLTS 120 120 120 120 68 GMWE Gross Megawatts Electric MWE 184 184 184 184 69 STP Steam Throttle Pressure PSIG 490 490 490 490 j 70 VCDTL VC Drain Tank Level 8 gal /in. INCHES 10 - 30 15 15 15 15 j' 71 FWT Feedwater Temperature DEG. F Not in CR 350 350 350 350
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| #1 FWH-l 72 OAT Outside Air Temperature DEG. F 62 62 62- _ 62
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| } 74 PVSRAD PVS Noble Gas Radiation MR/HR As Read As Read As Read- As Read l 75 SIUPF/HPSIF SI High Pressure Flow GPM 0 0 0 0
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| { 76 SILPF SI Low Pressure Flow GPM 0 0 0 0 i 87 VCT11 VC Air Temperature, RTD 911 Deg. F 105 105 105 105
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| ; 88 VCT12 VC Air Temperature, RTD 912 Deg. F 105 105 105 105 89 VCT13 VC Air Temperature, RTD 913 Deg. F 105 105 105 105 l 90 VCT14 VC Air Temperature, RTD 914 Deg. F 105 105 105 105 l 91 VCT15 VC Air Temperature, RTD 915 Deg. F 115 115 115 115
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| } 92 VCT16 VC Air Temperature, RTD 916 Deg.-F 105 105 105 105 l 93 VCT17 VC Air Temperature, RTD 917 Deg. F 77 77 77 77 94 VCT18 VC Air Temperature, RTD 918 Deg. F 74 74 74 74
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| ! 95 VCT19 VC Air Temperature, RTD 919 Deg. F 83. 83- 83 83 96 VCT20 VC Air Temperature, RTD 920 Deg. F 80 80 80 80 i
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| 1228e l
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| I
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| O O O Rev. 1 3/21/87 Page 8.0-4a YANKEE NUCLEAR POWER STATION i GRADED EXERCISE MARCH 1987 1
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| i Point Point ID Name Description Units Time 0445 0500 0515 0530 l 97 CETH7 Core Exit Temperature, H7 DEF. F 560 560 560 560 98 CETG-3 Core Exit Temperature, G-3 DEF. F 560 560 560 560 99 CETB-7 Core Exit Temperature, B-7 DEF. F 560 560 560 560 100 CETH-5 Core Exit Temperature, H-5 DEF. F 560 560 560 560 j 101 CETF-7 Core Exit Temperature, F-7 DEF. F 560 560 560 560 102 CETD-8 Core Exit Temperature, D-8 DEF. F 560 560 560 560 103 CETE-5 Core Exit Temperature, E-5 DEG. F 560 560 560 560 104 CETC-3 Core Exit Temperature, C-3 DEG. F 560 560 560 560 108 RHT1 Reactor " Head" Temperature, 1 DEG. F 910 510 510 510.
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| 109 RHT2 Reactor " Head" Temperature, 2 DEG. F 510 510 510 510 i
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| i 1
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| I j 1228e
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| O O O Rev. 1 3/21/87
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| . Page 8.0-5a YANKEE NUCLEAR POWER STATION
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| ;I GRADED EXERCISE MARCH 1987 2
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| Point Point i ID Name Description Units Time j 0445 0500. 0515 0530 i
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| i 150 MWT Megawatts Thermal MWT 600 600 600 600 i
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| HLIF Hot Leg Injection Flow INCHES 0 0 0 0 i HPSIP HPSI Header Pressure PSIG 0 0 0 0 ;
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| LPSIP LPSI Header Pressure PSIG 0 0 0 0
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| ; LPSTL LPS Tank Level INCHES 35 35 35 35 LPSTP LPS Tank Pressure PSIG 12 - 15 13 13 13 13 '
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| i Main Coolant System Leakage Air 4 Particulate Monitor (MCSLAPM)
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| ! South CPM 1.0E5 1.0E5 '5.0E5 9.0E5 North CPM 1.0E5 1.0E5 5.0E5 9.0E5 Primary Vent Stack Gas Monitor CPM As Read As Read 125 150 l Primary Vent Stack Iodine Monitor CPM OOS 00S 00S 00S l Primary Vent Stack Particulate Monitor CPM As Read As Read 100 125 l Primary Water Tank-39 FEET 20 - 25 23 23 23
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| ; SCHM1 Subcooled Margin Monitor (DEG) 65 - 70 76 76 76 j SCHM2 Subcooled Margin Monitor (PSIG) 800 860 860 860 i Gravity Drain Tank Level (Not in CR) PERCENT 30 30 30- 30 PZRP Pressurizer Pressure PSI 2020 2000 2020 2000 l
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| f i
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| l
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| ; 1228e I
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| i
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| O O O Rev. 1 j
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| 3/21/87 j Page'8.0-1b-YANKEE NUCLEAR POWER STATION l GRADED EXERCISE
| |
| , MARCH 1987 8.0 OPERATIONAL DATA Point Point ID Name Description Units Time 0545 0600 0615 0630 0645 0700 I
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| ~
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| { 1 PZRL Pressurizer Level, Wide Range . INCHES 120 118- 119 118 120 118 i 2 MCPRES1 Main Coolant Pressure, Loop 1 PSIG 2015 2000 2010_ 2015 2020 2000
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| } 3 MCPRES2 Main Coolant Pressure, Loop 2 PSIG 2015 2000 2010 2015 2020 2000
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| ! 4 MCPRES3 Main Coolant Pressure, Loop 3 PSIG 2015 2000 2010 2015 2020 2000 l Loop 4 SI Pressure PSIG 2015 2000 2010 2015 '2020 2000
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| ) 5 TH1 Hot Leg Temperature, Loop 1 DEG. F 551 551 552 550 548 545 6 TH2 Hot Leg Temperature, Loop 2 DEG. F 552 551 552 550 548 548 l 7 TH3 Hot Leg Temperature, Loop 3 DEG. F 551 551 550 549. 548 548
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| ! 8 TH4 Hot Leg Temperature, Loop 4 DEG. F 551 551 550 549 548 548
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| ! 9 TC1 Cold Leg Temperature Loop 1 DEG. F 511 511 512 511 510 508
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| ! 10 TC2 Cold Leg Temperature. Loop 2 DEG. F 512 511 512 511 510 510
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| ! 11 TC3 Cold Leg Temperature, Loop 3 DEG. F 511 511 512 511 510 510
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| ; 12 TC4 Cold Leg Temperature, Loop 4 DEG. F 512 511 512 511 510 510 l 13 SGWRL1 Steam Generator Level, Loop 1 FEET 22 22 23 23 23- 23 l 14 SGWRL2 Steam Generator Level, Loop 2 FEET 22 22- 23 23 23 23
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| ; 15 SGWRL3 Steam Generator Level, Loop 3 FEET 22 22 23 23 23 23 i 16 SGWRL4 Steam Generator' Level, Loop 4 FEET 22 22 23 23 23 23 l 17 SGP1 Steam Generator Pressure,. Loop 1 PSIG 510 515 525 530 540 555 j 18 SGP2 Steam Generator Pressure, Loop 2 PSIG 510 515 525 530 540 555 j 19 SGP3 Steam Generator Pressure, Loop 3 PSIG 510 515 525 530 540 .555' 20 SCP4 Steam Generator Pressure, Loop 4 PSIG 510 515 525 530 540 .555 21 NPPR6 Nuclear Power Range, Channel 6 PERCENT 97 95 93 91 89 87 j 22 NPPR7 Nuclear Power Range, Channel 7 PERCENT 97 95 93 91 89 87 23 NPPR8 Nuclear Power Range, Channel 8. PERCENT 97 95 93 91 89 87' i 24 NPIR4 Nuclear Inter. Range, Channel 4 AMPERES IE-4 1E-4 9E-5 9E-5 9E-5 8E-5 i
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| 1228e l
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| : O O Q .
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| Rev. 1' 3/21/87
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| ! Page 8.0-2b YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 j Point Point ID Name Description Units Time 0545 0600 0615 0630 0645 0700 l '
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| 3 25 NPIR3 Nuclear Inter. Range, Channel 3 AMPERES 1E-4 1E-4 1E-4 1E-4 1E-4 1E-4 j 26 NPSR2 Nuclear Source Range, Channel 2 CPS - - - - - -
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| 1 27 NPSR1 Nuclear Source Range, Channel 1 CPS .
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| i 28 SF1 Steam Flow, Loop 1 LBS/HR x 103 590 585 580 '575 570 540
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| ] 29 SF2 Steam Flow, Loop 2 LBS/HR x 103 590 585 580 575 570 540' 30 SF3 Steam Flow, Loop 3 LBS/HR x 103- 590 585 580 575 570 540
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| [ 31 SF4 Steam Flow, Loop 4 LBS/HR x 103 590 585 580 575 570 540 32 WF1 Feedwater Flow, Loop 1 LBS/HR x 103 590 585 580 575 570 540 ,
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| l 33 WF2 Feedwater Flow, Loop 2 LBS/HR x 103 590 585 580 575 570' 540 34 WF3 Feedwater Flow, Loop 3 'LBS/HR x 103 590 585 580 575 570 540 l 35 WF4 Feedwater Flow, Loop 4 LBS/HR x 103 590 585 580 575 570 540 40 SLRAD1 Steam Line Radiation, Loop 1 MR/HR 0.6. 0.6 0.6 0.4 0.3 0.3
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| ! 41 SLRAD2 Steam Line Radiation, Loop 2 MR/HR 0.5 0.5 0.6 0.6 0.7 0.7 j 42 SLRAD3 Steam Line Radiation, Loop 3 MR/HR 0.1 0.1 0.1 0.1 0.1 0.1 43 SLRAD4 Steam Line Radiation, Loop 4 MR/HR 0.6 0.6 0.6 0.6 0. !, . 0.7 44 VCPLR VC Pressure, Low Range PSIG 1.2 1.2 1.2 1.7 1.2 1.2 45 VCPHR1 VC Pressure, High Range 1 PSIG <2 <2 <2- <2 <2 <2 46 VCPHR2 VC Pressure, High Range 2 PSIG <2 <2 <2 <2 <2 <2 47 VCRAD1 VC Radiation, Channel 1 R/HR <1 <1 <1 <1 <1 <1
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| . 48 VCRAD2 VC Radiation, Channel 2 R/HR <1 <1 <1 <1 <1 <1 49 VCH1 VC Hydrogen, Channel 1 PERCENT 0 0 0 0 0 0 l,
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| l 1228e
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| Rev. I 1
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| 3/21/87 t
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| Page 8.0-3b YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name pescription Units Time ,
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| 0545 0600 0615 0630 0645 0700
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| ; 50 VCH2 VC Hydrogen, Channel 2 PERCENT 0 0 0 0 0 0
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| ; 51 VCL1 VC Flood Level, Channel.1- FEET 0 0 0 0 0' O 52 VCL2 VC Flood Level, Channel 2 FEET 0, 0 0 0 0 0 59 AEJRM Air Ejector Radiation Monitor CPM 1100 1300 1400 1400 1500 1700 60 SITL Safety Injection Tank Level FEET 27 27 27 27 27 27 61 DWSTL Demineralized Water Tank Level FEET 13 13 13 13 13 13 i 62 IAPA Instrument Air Pressure, Header N PSIG 95 95 95 95 95 95 4
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| 63 IAPB Instrument Air Pressure, Header N PSIC 95 95 95 95 95 95 67 VBUSV Vital Bus Volts (Not in CR) VOLTS 120 120 120 120 120 120 68 GMWE Gross Megawatts Electric MWE 184 184 184 179 174.8 165.6 69 STP Steam Throttle Pressure PSIG 490 490 490 479 472 472 VC Drain Tank Level l 70 VCDTL INCHES 15 15 15 15 15- 15
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| } 71 FWT Feedwater Temperature DEG.F 350 350 350 350 350 350 ;
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| j 72 OAT Outside Air Temperature DEG.F 62 62 62 63 63 63 74 PVSRAD PVS Noble Gas Radiation MR/HR As As As As. As As Read Read Read Read Read Read .
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| ! 75 SIHPF/HPSIF SI High Pressure Flow GPM 0 0 0 0 0 0 !
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| i 76 SILPF SI Low Pressure Flow GPM- 0 0 0 0 0 0 i 87 VCT11 VC Air Temperature, RTD 911 Deg. F 105 105 105 105 105 105 j 88 VCT12 VC Air Temperature, RTD 912 Deg. F 105 105 105 105 105 105-
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| ; 89 VCT13 VC Air Temperature, RTD 913- Deg. F 105 105 105 105 105 105 j 90 VCT14 VC Air Temperature, RTD 914 Deg. F 105 105 105 105 105 105 I 91 VCT15 VC Air Temperature, RTD 915 Deg. F 115 115 115 115 115 115 i 92 VCT16 VC Air Temperature, RTD 916 Deg. F 105 105 105 105 105 105 I 93 VCT17 VC Air Temperature, RTD 917 Deg. F 77 77 77- 77 -77 77 94 VCT18 VC Air Temperature, RTD 918 Deg. F 74 74 74 74 74 74 95 VCT19 VC Air Temperature, RTD 919 Deg. F 83 83 83 83 83 83 .,
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| 96 VCT20 VC Air Temperature, RTD 920 Deg. F 80 80 80 80 80 80 i
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| i 1228e
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| O O O Rev. 1 3/21/87 Page 8- 0-4b YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description. Units Time 0545 0600 0615 0630 0645 0700.
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| 97 CETH7 Core Exit Temperature, H7 DEF. F 560 560 558 556 '554 553l 98 CETG-3 Core Exit Temperature, G-3 DEF. F 560 560 558 556 554 553 99 CETB-7 Core Exit Temperature, B-7 DEF. F 560 560 558 556 554 .553 100 CETH-5 Core Exit Temperature, H-5 DEF. F 560 560 558 556 554~ 553 101 CETF-7 Core Exit Temperature, F-7 DEF. F 560 560 558 556 554 553 102 CETD-8 Core Exit Temperature, D-8 DEF. F 560 560 558 556 554 553' 103 CETE-5 Core Exit Temperature, E-5. DEG. F 560 560 558 556 554 553 104 CETC-3 Core Exit Temperature, C-3 DEG. F- 560 '560 558 556 554 553-108 RHT1 Reactor " Head" Temperature, 1 DEG. F 510 510 510 510 510 508 109 RHT2 Reactor " Head" Temperature, 2 DEG. F 510 510- 510 510 510 508 l
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| O O O Rev. 1 3/21/87 Page 8.0-5b YANKEE NUCLEAR POWER STATION
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| , GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time 0545 0600 0615 0630 0645 0700 150 MWT Megawatts Thermal MWT 600 600 590 570 550 540 HLIF Hot Leg Injection Flow INCHES 0 0 0 0 0 0 HPSIP HPSI Header Pressure PSIG 0. 0 0 0 0 0 LPSIP LPSI Header Pressure PSIG 0 0 0 0 0 0 LPSTL LPS Tank Level INCHES 35 35 35 34 33 31 LPSTP LPS Tank Pressure PSIG 10 10 9 9 8 7 Main Coolant System Leakage Air Particulate Monitor (MCSLAPM)
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| South CPM 9.0E5 9.0E5 9.2E5 9.3E5 9.7E5 1.0E6 North CPM 9.0E5 9.0E5 9.2E5 9.3E5 9.7ES 1.0E6 Primary Vent Stack Gas Monitor CPM 200 225 250 275 300 350 Primary Vent Stack Iodine Monitor CPM OOS 00S 00S 00S- OOS 00S Primary Vent Stack Particulate Monitor CPM 175 185 200 225 250 325 Primary Water Tank-39 FEET 23 23 23 23 23 23 SCHM1 Subcooled Margin Monitor (DEG) 76 76 76 .78 81 83 SCHM2 Subcooled Margin Monitor (PSIG) 860 860 875 885 903 938 Gravity Drain Tank Level PERCENT 30 30 30 30 30 30.
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| PZRP Pressurizer Pressure PSI 2020 2010 2000 2010 2020 2000 1228e
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| - ' ~ *-
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| _1__1 - . _ "M,__ - ,
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| Rev.~1. '
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| 3/21/87 Page 8.0-Ic
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| , YANKEE NUCLEAR POWER STATION GRADED EXERCISE-MARCH,1987 4
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| 8.0 OPERATIONAL DATA +
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| ~
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| Time Point Point Accident Starts - Partial STM Line Break l ID Name Description Units With S/G Tube Failure
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| ! 0715 0730 0731- 0732 1 PZRL Pressurizer Level, Wide Range INCHES 120- 120 0 0 2 MCPRES1 Main Coolant Pressure, Loop 1 PSIG 1990: '2000 1096 1110-j 3 MCPRES2 Main Coolant Pressure, Loop 2 PSIG 1990 2000 1096 1110
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| ; 4 MCPRES3 Main Coolant Pressure, Loop 3 PSIG 1990 2000 -1096 1110
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| : Loop 4 SI Pressure PSIG 1990 2000. 1096 1110-5 TH1 Hot Leg Temperature, Loop'1 DEG. F 539- 525 ~525 525 6 TH2 Hot Leg Temperature, Loop 2 DEG. F 538 525 525 525 7 TH3 Hot Leg Temperature, Loop 3 DEG. F 538 525 525 525 8 TH4 Hot Leg Temperature, Loop 4 DEG. F 539 525 525 425 9 TCl Cold Leg Temperature, Loop 1 DEG. F -506 497_ 525 525 10 TC2 Cold Leg Temperature, Loop 2 DEG. F 506 497 525 525 11 TC3 Cold Leg Temperature, Loop 3 DEG. F 506 497 525 525 12 TC4 Cold Leg Temperature, Loop 4 DEG. F. 506 497 450 350 13 SGWRL1 Steam Generator Level, Loop 1 FEET 22 22 20 21 14 SGWRL2 Steam Generator Level, Loop 2 FEET 22 22 20 21 15 SGWRL3 Steam Generator Level, Loop 3 FEET 22 22 20 21 16 SGWRL4 Steam Generator Level, Loop 4' FEET 23 23 19 15 17 SGP1 Steam Generator Pressure, Loop 1 PSIG 560 448 850 850 18 SGP2 Steam _ Generator Pressure, Loop 2 PSIG 560 448 850 850 19 SGP3 Steam Generator Pressure, Loop 3 PSIG 560 448 850 850 4
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| 20 SGP4 Steam Generator Pressure, Loop 4 PSIG 560- 448 300 200 21 NPPR6 Nuc1 car Power Range, Channel 6 PERCENT 81 75 0 0 22 NPPR7 Nuclear Power. Range, Channel 7 PERCENT 81 75 'O O 23 NPPR8 Nuclear Power Range, Channel 8 PERCENT 81, 75 0 0
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| , 24 NPIR4 Nuclear Inter. Range, Channel 4 AMPERES 8E-5. 8E-5 IE-8 1E-11
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| , 1228e
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| ---- _-_ _ _~ _
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| O -
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| o; L Q:
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| ^ '
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| Rev. 1:
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| 3/21/87..
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| Page 8.0-2c
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| ,,. . YANKEE NUCLEAR POWER STATION
| |
| , GRADED EXERCISE m.,
| |
| 8 [W C. ,. ~
| |
| MARCH 1987 4 .L ,.e
| |
| ., 4 ;,,
| |
| Point Point .,'
| |
| ID Name Description '~
| |
| , Units . Time 0715 0730 0731 0732 25 NPIR3 Nuclear Inter. Range, Channel 3 AMPERES 8E 8E-5 1E-5 . ' 1E-6 .. -
| |
| l 26 NPSR2 Nuclear Source Range -Channel 2 CPS - - .
| |
| 27 NPSR1 Nuclear Source Range, Channel 1 CPS 28 SF1 Steam Flow, Loop 1 LBS/HR x 103 Si0 480 'O. 'O 29 SF2 . Steam Flow, Loop 2 LBS/HR x 103 510 480 0. 0 30 SF3 Steam Flow, Loop 3 LBS/HR x-103 510 480' O O ,
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| 31 SF4 Steam Flow, Loop 4 LBS/HR x-103 510 e/80 0 0:
| |
| 32 FWF1 Feedwater Flow, Loop 1 LBS/HR x 103 510 yS0 0 0 33 FWF2 Feedwater Flow, Loop'2 LBS/HR x 103 510 180 0 0 34 WF3 Feedwater Flow, Loop 3 LBS/HR x 103 510 VSO O O 35 FWF4 Feedwater Flow, Loop 4 LBS/HR x 103 500 yy0 0 0 40 SLRAD1 Steam Line Radiation, Loop 1 MR/HR 0.3 1000 1300 1500 41 SLRAD2 Steam Line Radiation, Loop 2 MR/HR 0. 7- .1000 1300~ 1500 42 SLRAD3 . Steam Line Radiation, Loop 3 MR/HR' 7 0.1 ~1500 2000 .2500 43 SLRAD4 Steam Line Radiation, Loop 4 MR/HR 0.7 2000 2500' 3000 44 VCPLR VC Pressure, Low Range- PSIG 1.2- 1. 2' 1;2 1.2 45 VCPHR1 VC Pressure High Range 1 PSIG <3 . <3 <3 <3 46 VCPHR2 VC Pressure, High Range 2 PSIG <3 ' <3 <3 <3 47 VCRAD1 VC Radiation, Channel 1 R/HR <1 10 . 1.0 1.0 48 VCRAD2 VC Radiation, Channel 2 R/HR <1 1.0 1.0 1.0 49 VCH1 VC Hydrogen, Channel 1 -
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| PERCENT 0 0 0 0' w ,-
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| s-1228e
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| r Rev. 1 3/21/87
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| . Page 8.0-3c YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time 0715 0730 0731 0732 50 VCH2 VC Hydrogen, Channel 2 PERCENT 0 0 0 0 51 VCL1 VC Flood Level, Channel 1 FEET 0 0 0 0 4
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| 52 VCL2 VC Flood Level Channel 2 FEET 0 0 0 0 l 59 AEJRM Air Ejector Radiation Monitor CPM 1200 OSH OSH 300 60 SITL Safety Injection Tank Level FEET 27 27 27 27 61 DWSTL Demineralized Water Tank Level FEET 13 13 62 IAPA Instrument Air Pressure, Header N PSIG 95 95 95 95 63 IAPB Instrument Air Pressure. Header S PSIG 95 95 959 95 67 VBUSV Vital Bus Volts (Not in CR) VOLTS 120 120 120 120 68 GMWE Gross Megawatts Electric MWE 156.4 147.2 0 0 69 STP Steam Throttle Pressure PSIG 435 448 0 -0
| |
| ! 70 VCDTL VC Drain Tank Level INCHES 15 15 15 15 71 FWT Feedwater Temperature DEG.F 290 270 350 350 72 OAT Outside Air Temperature DEG. F 63 64 64 64 74 PVSRAD PVS Noble Gas Radiation MR/HR As Read 70 75 80 75 SIUPF/HPSIF SI High Pressure Flow GPM 0 0 420 420 76 SILPF SI Low Pressure Flow GPM 0 0 420 420 87 VCT11 VC Air Temperature, RTD 911 Deg. F 105 105 105 105 88 VCT12 VC Air TemN rature, RTD 912 Deg. F 105 105 105 105 89 VCT13 VC Air Temperature, RTD 913 Deg. F 105 105 105 105 90 VCT14 VC Air Temperature, RTD 914 Deg. F 105 105 105 105 91 VCT15 VC Air Temperature, RTD 915 Deg. F 115 115 115 115 92 VCT16 VC Air Temperature, RTD 916 Deg. F 105 105 105 105 93 VCT17 VC Air Temperature, RTD 917 Deg. F 77 77 77 77 94 VCT18 VC Air Temperature, RTD 918 Deg. F 74 74. 74 74 95 VCT19 VC Air Temperature, RTD 919 Deg. F 83 83 83 83 96 VCT20 VC Air Temperature, RTD 920 Deg. F 80 80 80 80
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| , 1228e
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| O O O Rev. 1 3/21/87 Page 8.0-4c YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time
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| : 0715 0730 0731 0732 97 CETH7 Core Exit Temperature, H7 DEF. F 550 540 490 425 98 CETG-3 Core Exit Temperature, G-3 DEF. F 550 540 490 425 99 CETB-7 Core Exit Temperature, B-7 DEF. F 550 540 490 425 l 100 CETH-5 Core Exit Temperature, H-5 DEF. F 550 540 490 425
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| ! 101 CETF-7 Core Exit Temperature, F-7 DEF. F 550 540 490 425
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| ; 102 CETD-8 Core Exit Temperature, D-8 DEF. F 550 540 490 425 103 CETF.-5 Core Exit Temperature, E-5 DEG. F 550 540 490 425
| |
| : 104 CETC-3 Core Exit Temperature -C-3 DEG. F 550 540 490 425 108 RHT1 Reactor " Head" Temperature, 1 DEG. F 506 500 500 500 109 RHT2 Reactor " Head" Temperature, 2 DEG. F 506 500 -500 500 1
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| -Rev. 1
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| , 3/21/87 Page 8.0-Se YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point
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| ! ID Name Description Units Time 0715 0730. 0731 0732 150 MWT Megawatts Thermal MWT 510 480 0 0
| |
| +
| |
| HLIF Hot Leg Injection Flow INCHES 0 0 0 0 i HPSIP HPSI Header Pressure PSIG 0 0 1160 1180
| |
| ) LPSIP LPSI Header Pressure PSIG 0 0 690' 690 LPSTL LPS Tank Level INCHES 31 31 33 35 LPSTP LPS Tank Pressure PSIG 7 7 8 9 4
| |
| I Main Coolant System Leakage Air Particulate Monitor (MCSLAPM)
| |
| South CPM 1.0E6 OSH OSH OSH North CPM 1.0E6 OSH OSH OSH Primary Vent Stack Gas Monitor CPM 400 1.0E5 1.2E5 1.5ES Primary Vent Stack Iodine Monitor CPM 00S 00S 00S 00S
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| ; Primary Vent Stack Particulate Monitor CPM 350 7.5E4 9.0E4 1.2E5
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| ; Primary Water Tank-39 FEET 23 23 23 23
| |
| ] SCHM1 Subcooled Margin Monitor (DEG) 86 96 57 134 SCHM2 Subcooled Margin Monitor (PSIG) 940 1038 490 800' Gravity Drain Tank Level PERCENT 30 30 30 30
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| ! PZRP Pressurizer Pressure PSI 1990 2000 1096 1110 1
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| w ______ _ _ _ _ _ _ _ _ _ _ _ -
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| O O O Rev. 1 3/21/87 Page 8.0-Id YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987
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| -8.0 OPERATIONAL DATA Point Point ID Name Description Units. Time 0733 0735 0745 0800 1 PZRL Pressurizer Level, Wide Range INCHES 0 50 100 110 2 MCPRES1 Main Coolant Pressure, Loop 1 PSIG 1200' 1300 1460 1500 3 MCPRES2 Main Coolant Pressure, Loop 2 PSIG 1200 1300 1460 1500 4 MCPRES3 Main Coolant Pressure, Loop 3 PSIG 1200 '1300 1460' 1500 Loop 4 SI Pressure PSIG 1200 11300 1460 1500 5 TH1 Hot Leg Temperature, Loop 1 DEG. F 525 525 525 525 6 TH2 Hot Leg Temperature Loop 2 DEG. F 525 525 525 525 7 TH3 Hot Leg Temperature, Loop 3 DEG. F 525 525 525 '525 8 TH4 Hot Leg Temperature . Loop 4 DEG. F 375 360 350 300 9 TC1 Cold Leg Temperature, Loop 1 DEG. F 525 525 525- 520 10 TC2 Cold Leg Temperature, Loop 2 DEG. F 525 525 525 520 11 TC3 Cold Leg Temperature, Loop 3 DEG. F 525 525 525 520 12 TC4 Cold Leg Temperature, Loop 4 DEG. F 300 290 280 270 13 SGWRL1 Steam Generator Level, Loop 1 FEET 22 22 23 22 14 SGWRL2 Steam Generator Level, Loop 2 FEET 22 22 23 23 15 SGWRL3 Steam Generator Level. Loop 3 FEET 22 22 23 22 16 SGWRL4 Steam Generator Level, Loop 4 FEET 11 6 0 0 17 SGPL Steam Generator Pressure.. Loop 1 PSIG 850 850 850 810 18 SGP2 Steam Generator Pressure, Loop 2 PSIG 850 850 850 812 19 SGP3 Steam Generator Pressure, Loop 3 PSIG 850 850 .850 810 20 SGP4 Steam Generator Pressure, Loop 4 .PSIG 100 90 10 10 21 NPPR6 Nuclear Power Range, Channel 6 PERCENT 0 0 0 0 22 NPPR7 Nuclear Power Range, Channel 7 PERCENT 0 0 0 0 23 NPPR8 Nuclear Power Range, Channel 8 PERCENT 0 0 0 0 24 NPIR4 Nuclear Inter. Range, Channel 4 AMPERES 1E-11 1E-11 1E-11 1E-11 1228e
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| Rev. 1 3/21/87
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| ! Page 8.0-2d YANKEE NUCLEAR POWER STATION
| |
| : GRADED EXERCISE MARCH 1987 i
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| l Point Point i
| |
| ID Name Description Units Time 0733 0735 0745 0800 25 NPIR3 Nuclear Inter. Range, Channel 3 AMPERES lE-6 1E-7 1E-10.. IE-11 26 NPSR2 Nuclear Source Range, Channel 2 CPS - - 100,000 10,000 i 27 NPSR1 Nuclear Source Range, Channel 1 CPS - --
| |
| 100,000 10,000 I' 28 SF1 Steam Flow, Loop 1 LBS/HR x 103 o o o o 29 SF2 Steam Flow, Loop 2 LBS/HR x 103 o o o o 4
| |
| 30 SF3 Steam Flow, Loop 3 LBS/HR x 103 o o o o 31 SF4 Steam Flow, Loop 4 LBS/HR x 103 0 0 0 0 i 32 WF1 Feedwater Flow, Loop 1 LBS/HR x 103 0 0 0 0 i 33 WF2 Feedwater Flow, Loop 2 LBS/HR x 103 o o o o 34 WF3 Feedwater Flow, Loop 3 LBS/HR x 103 0 0 0 '0
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| : 35 WF4 Feedwater Flow, Loop 4 LBS/HR x 103 0 0 0 0
| |
| } 40 SLRAD1 Steam Line Radiation Loop 1 MR/HR 1,800 2,000 2,300 1.400 l 41 SLRAD2 Steam Line Radiation, Loop 2 MR/HR 1,800 2,000 2,300 1,400 i 42 SLRAD3 Steam Line Radiation, Loop 3 MR/HR 3,000 3,400 3,800 4,000
| |
| ; 43 SLRAD4 Steam Line Radiation, Loop 4 MR/HR 3,500 4,000 4,500 4,800
| |
| ?
| |
| 44 VCPLR VC Pressure, Low Range PSIG 1.2 1.2 1.2 .1.2 i 45 VCPHR1 VC Pressure, High Range 1 PSIG <3 <3 <3 <3 46 VCPHR2 VC Pressure, High Range 2 PSIG <3 <3 <3, <3
| |
| ) 47 VCRAD1 VC Radiation, Channel 1 R/HR 1.0 1.0 2.0 5.0
| |
| ! 48 VCRAD2 VC Radiation, Channel 2 R/HR 1.0 1.0 2.0 5.0 l 49 VCH1 VC Hydrogen, Channel 1 PERCENT 0 0 0 0 i
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| l l
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| 1 4
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| O O (QJ l Rev.1 1'
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| : 3/21/87' j 1Page 8.0-3d YANKEE NUCLEAR POWER STATION GRADED EXERCISE j MARCH 1987 1
| |
| i Point Point ID Name Description Units Time '
| |
| 0733 0735 0745 0800 t
| |
| 50 VCH2 VC Hydrogen, Channel 2 PERCENT 0 0 0 0 51 VCL1 VC Flood Level, Channel 1 FEET 0 0 0 ~0 52 VCL2 VC Flood Level, Channel 2 FEET 0 0 0 0
| |
| , 59 AEJRM Air Ejector Radiation Monitor CPM 300 300 300 300 j 60 SITL Safety Injection Tank Level FEET 27 26.5 26.5 25.9 i 61 DWSTL Demineralized Water Tank Level FEET 13 13 13 13 l 62 IAPA Instrument Air Pressure, Header N PSIG 95 95 95 95
| |
| , 63 IAPB Instrument Air Presrure Header N PSIG 95 95 95 95 I
| |
| 67 VBUSV Vital Bus Volts (Not in CR) VOLTS 120 120 120 120 l 68 GMWE Gross Megawatts Electric MWE O O .0 0 i 69 STP Steam Throttle Pressure PSIG 0 0 0 .0 l 70 VCDTL VC Drain Tank Level INCHES 15 15 15 15 i 71 FWT Feedwater. Temperature DEG.F- 350 200 200 200 l 72 OAT Outside Air Temperature DEG.F 62 62 62 62
| |
| ) 74 PVSRAD PVS Noble Gas Radiation MR/HR 90 100 150 180 j 75 SIHPF/HPSIF SI High Pressure Flow GPM 420 360 180 120 9 76 SILPF SI Low Pressure Flow GPM 420 360 180 120 87 VCT11 VC Air Temperature, RTD 911 Deg. F. 105 105 105 105 88 VCT12 VC Air Temperature, RTD 912 .Deg. F 105 105 105 105 j 89 VCT13 VC Air Temperature, RTD 913 Deg. F 105 105 105 .105 j 90 VCT14 VC Air Temperature, RTD 914 Deg. F 105 '105- 105 105~
| |
| 91 VCT15 VC Air Temperature, RTD 915 Deg. F 115 115 115 115 i 92 VCT16 VC Air Temperature, RTD 916 Deg. F 105 105 105 105 93 VCT17 VC Air Temperature, RTD 917 Deg. F 77 77 77 77 l 94 VCT18 VC Air Temperature, RTD 918 Deg. F. 74 74 74 74 l 95 VCT19 VC Air Temperature, RTD 919 Deg. F 83 83 83 83 i 96 VCT20 VC Air Temperature, RTD 920 Deg. F 80 80 80 80 .p I
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| I l
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| 1228e
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| ; Rev. 1 3/21/87
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| .Page 8.0-4d YANKEE NUCLEAR POWER STATION I.
| |
| GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time
| |
| ] 0733 0735 0745 0800 j 97 CETH7 Core Exit Temperature, H7 DEF. F 480 475 460 460 1 98 CETG-3 Core Exit Temperature, G-3 DEF. F 480 475 460- 460 j 99 CETB-7 Core Exit Temperature, B-7 DEF. F 480 475 460 460 l 100 CETH-5 Core Exit Temperature, H-5 DEF. F 480 475 460 460 101 CETF-7 Core Exit Temperature, F-7 DEF. F 480 475 460 460 102 CETD-8 Core Exit Temperature, D-8 DEF. F 480 475 460 460 i 103 CETE-5 Core Exit Temperature, E-5 DEG. F 480 475 460 460 104 CETC-3 Core Exit Temperature, C-3 DEG. F 480 475 460 460 108 RHT1 Reactor " Head" Temperature, 1 DEG. F 490 485 470 470 i 109 RHT2 Reactor " Head" Temperature, 2 DEG. F 490 485 470 470 j
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| 4 9
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| i i
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| }
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| l 1228e 1
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| p jm.
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| O Rev. 1 3/21/87 Page 8.0-5d YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 4
| |
| Point Point ID Name Description Units Time
| |
| , 0733 0735 0745 0800 l
| |
| t l 150 MWT Megawatts Thermal MWT 0 0 0 0 HLIF Hot Leg Injection Flow INCHES 0 0 0 0 HPSIP HPSI Header Pressure PSIG 1270 1370 1510 1530 LPSIP LPSI Header Pressure PSIG 690 690 690 690 LPSTL LPS Tank Leve'. INCHES 35 35 35 35 LPSTP LPS Tank P mssure PSIG 10 10 10 10 Main Coolarit System Leakage Air Particulate Monitor (MCSLAPM)
| |
| South CPM OSH OSH OSH OSH North CPM OSH OSH OSH OSH Primary V.ent Stack Gas Monitor CPM 1.7E5 2E5 2.4E5 2.8E5 Primary Vent Stack Iodine Monitor CPM 00S 00S 00S 00S Primary Vent Stack Particulate Monitor CPM 1.5ES 1.7E5 2.1E5 2.6E5 Primary Water Tank-39 FEET 23 23 23 23 SCHM1 Subcooled Margin Monitbr (DEG) 89 104 134 138 SCHM2 Subcooled Margin Monitor (PSIG) 649 775 1008 1048 Gravity Drain Tank Level PERCENT 30 30 30 30' PZRP Pressurizer Pressure PSI 1200 1300 1460 1500
| |
| .l
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| )
| |
| l l
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| 1228e
| |
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| __ _ _ _ ., _. _ . . ._ ~ _.. . ._ _ ._
| |
| Rev..'1
| |
| . 3/21/87: '
| |
| l Page 8.0-le YANKEE NUCLEAR POWER STATION
| |
| , GRADED EXERCISE
| |
| < MARCH 1987 i
| |
| j 8.0 OPERATIONAL DATA 1
| |
| Point Point l ID Name Description Units Time j 0815 0830 0845 0900 I
| |
| l 1 PZRL Pressurizer Level, Wide Range INCHES 120 120 120 120 2 MCPRES1 Main Coolant Pressure, Loop 1 PSIG 1500 1500 1500- 1500 -
| |
| i 3 MCPRES2 Main Coolant Pressure, Loop 2 PSIG 1500 1500 1500 1500 j 4 MCPRES3 Main Coolant Pressure, Loop 3 PSIG 1500 1500 1500 1500 j Loop 4 SI Pressure PSIC 1500 0 0 0 Hot Leg Temperature, Loop 1
| |
| ^
| |
| 5 TH1 DEG. F 460 450 440 430 l 6 TH2 Hot Leg Temperature, Loop 2 DEG. F 460 450 440 '430 7 TH3 Hot Leg Temperature, Loop 3 DEG. F 460 450 440 430 8 TH4 Hot Leg Temperature, Loop 4 DEG. F 300 290 250- 240
| |
| ] 9 TC1 Cold Leg Temperature, Loop 1 DEG. F 460 450. 440 430 i 10 TC2 Cold Leg Temperature, Loop 2 DEG. F 460 450- 440 430' l 11 TC3 Cold Leg Temperature. Loop 3 DEG. F 460 450 440 430 12 TC4 Cold Leg Temperature, Loop 4 DEG. F 220 220 220 220
| |
| ! 13 SGWRL1 Steam Generator Level, Loop 1 FEET 22 22 22 22' 14 SGWRL2 Steam Generator Level, Loop 2 FEET -22 22 23 22 15 SGWRL3 Steam Generator Level, Loop 3 FEET 23 22 23 22 a 16 SGWRL4 Steam Generator Level, Loop 4 FEET 0 0 0 .O j 17 SGP1 Steam Generator Pressure, Loop 1 PSIG 810 810 730- 730' l
| |
| 18 SGP2 Steam Generator Pressure, Loop 2- PSIG 812 812 735 735 1 19 SGP3 Steam Generator Pressure, Loop 3 PSIG 810 812 725 730 20 SGP4 Steam Generator Pressure, Loop 4 PSIG 10 0 0 0 21 NPPR6 Nuclear Power Range, Channel 6 PERCENT 0 0 0 0 22 NPPR7 Nuclear Power Range, Channel 7 PERCENT 0 0 0 0-23 NPPR8 Nuclear Power Range, Channel 8 PERCENT 0 0 0 0 24 NPIR4 Nuclear Inter. Range, Channel 4 AMPERES 1E-11 1E-11 1E-11 1E-11 a
| |
| j 1228e i .
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| Rev. 1 3/21/87 i Page 8.0-2e YANKEE NUCLEAR POWER STATION l GRADED EXERCISE' j' MARCH 1987
| |
| )
| |
| i Point Point ID Name Description Units Time 0815 0830 0845 0900 i 25 NPIR3 Nuclear Inter. Range, Channel 3 AMPERES 1E-11 1E-11 1E-11 1E-11 26 NPSR2 Nuclear Source Range, Channel 2 CPS 10,000 10,000 10,000 10,000 1 27 NPSR1 Nuclear Source Range, Channel 1 CPS 10,000 10,000 10,000 '10,000.
| |
| 28 SF1 Steam Flow, Loop 1 LBS/HR x 103 o o .o o j 29 SF2 Steam Flow, Loop 2 LBS/HR x 103 o o o o j 30 SF3 Steam Flow, Loop 3 LBS/HR x 103 o o o o i 31 SF4 Steam Flow, Loop 4 LBS/HR x 103 o o o o
| |
| ! 32 FWF1 Feedwater Flow, Loop 1 LBS/HR x 103 50 40 50 50 i 33 WF2 Feedwater Flow, Loop 2 LBS/HR x 103 50 45 50 50
| |
| ! 34 WF3 Feedwater Flow, Loop 3 LBS/HR x 103 50 50 50 50 I
| |
| 35 FWF4 Feedwater Flow, Loop 4 LBS/HR x 103 0 0 0 0 40 SLRAD1 Steam Line Radiation, Loop 1 MR/HR 2,100 250 10 10 1 41 SLRAD2 Steam Line Radiation, Loop 2 MR/HR 2,100. 250 10 10 42 SLRAD3 Steam Line Radiation, Loop 3 MR/HR 3,150 375 75 75 43 SLRAD4 Steam Line Radiation, Loop 4 MR/HR 4,200 500 100 100 1 44 VCPLR VC Pressure, Low Range PSIG 1.2 1.2 1.2 1.2 I 45 VCPHR1 VC Pressure, High Range 1 PSIG <3 <3 <3 <3 46 VCPHR2 VC Pressure, High Range 2 PSIG <3 <3 <3 <3 j 47 VCRAD1 VC Radiation, Channel 1 R/HR 4.0 1.0 1.0 1.0 4
| |
| 48 VCRAD2 VC Radiation, Channel 2 R/HR 4.0 1.0 1.0 1.0 49 VCH1 VC Hydrogen, Channel 1 PERCENT 0 0 0 0 f
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| i J
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| 1
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| -l 1228e i
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| l
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| Rev. l' j 3/21/87 Page 8.0-3e l YANFEE NUCLEAR POWER STATION ,
| |
| j GRADED EXERCISE ;"
| |
| MARCH 1987 l
| |
| f Point Point
| |
| ! ID Name Description Units Time i 0815 0830 0845. 0900 1
| |
| 50 VCH2 VC Hydrogen, Channel 2 PERCENT 0 0 0 'O 4 51 VCL1 VC Flood Level, Channel 1 FEET 0 0 0 0-l 52 VCL2 VC Flood Level, Channel 2 FEET 0 0 0 0 4
| |
| 59 AEJRM Air Ejector Radiation Monitor CPM 300 300 300 .300 I 60 SITL Safety Injection Tank Level FEET 25.5 25.5 25.5 25.5
| |
| ! 61 DWSTL Demineralized Water Tank Level FEET 13 13 13- 13 j 62 IAPA Instrument Air Pressure, Header N PSIG 95 95 .95 95 l 63 IAPB Instrument Air Pressure, Header S PSGI 95 95 95 95 <
| |
| 67 VBUSV Vital Bus Volts (Not in CR) -VOLTS 120 120 120 120.
| |
| l! 68 GMWE Gross Megawatts Electric MWE O O O O i 69 STP Steam Throttle Pressure PSIG 0 0' 0' 0 j 70 VCDTL VC Drain Tank Level INCHES 15 15 15 15 j 71 FWT Feedwater Temperature DEG. F 200 200 200 200 J 72 OAT Outside Air Temperature DEG. F 62 62 62 .62
| |
| ] 74 PVSRAD PVS Noble Gas Radiation MR/HR 160 100 As Read As Read I 75 SIHPF/HPSIF SI High Pressure Flow GPM 120 120 120 120
| |
| ) 76 SILPF SI Low Pressure Flow GPM 120 120 120- 120 j 87 VCT11 VC Air Temperature, RTD 911 Deg. F 105 105 105 105
| |
| ) 88 VCT12 VC Air Temperature, RTD 912 Deg. F 105 105 105 105
| |
| ! 89 VCT13 VC Air Temperature, RTD 913 Deg. F 105 105 105 105 l 90 VCT14 VC Air Temperature, RTD 914 Deg. F 105 105 105 105 j 91 VCT15 VC Air Temperature, RTD 915 Deg. F 115 115 115 115
| |
| ~
| |
| 92 VCT16 VC Air Temperature, RTD 916 Deg. F 105 -105 105 105 93 VCT17 VC Air Temperature, RTD 917 Deg. F 77' 77- 77 77 94 VCT18 VC Air Temperature, RTD 918 Deg. F 74 74 74 74' 95 V0T19 VC Air Temperature, RTD 919 Deg. F 83 83 .83 83 3
| |
| 96 VCT20 VC Air Temperature, RTD 920 Deg. F 80- 80 80 80 l
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| } 1228e
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| ) i l
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| . rg
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| ! V '
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| I ,-
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| J-Rev. 1.
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| : 3/21/87 i Page 8.0-4e j YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time 1 0815 0830 0845- 0900 97 CETH7 Core Exit Temperature, H7 DEF. F .460 450 440 430 98 CETG-3 Core Exit Temperature, G-3 DEF. F 460 450 440 430
| |
| ) 99 CETB-7 Core Exit Temperature, B-7 DEF. F 460 450 440 430 j 100 CETH-5 Core Exit Temperature, H-5 DEF. F 460 450 440. 430 1 101 CETF-7 Core Exit Temperature F-7 DEF. F 460 450 440 430 i 102 CETD-8 Core Exit Temperature, D-8 DEF. F 460 450 440- 430 103 CETE-5 Core Exit Temperature, E-5 DEG. F '460 450 440 430 i 104 CETC-3 Core Exit Temperature, C-3 DEG. F 460 450 -440 430 f 108 RHT1 Reactor " Head" Temperature, 1 DEG. F 470 460 440 '430-l 109 RHT2 Reactor " Head" Temperature, 2 DEG. F 470 '460 440- 430 l
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| I 1228e ,
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| I 1
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| o . - _ - _ _ - _ _ .__ -_. .
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| : O O O Rev. 1~
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| 3/21/87-i Page 8.0-Se '
| |
| ! YANKEE NUCLEAR POWER STATION l GRADED EXERCISE j MARCH 1987 4
| |
| Point Point i
| |
| ID Name Description Units Time j 0815 0830 0845 0900.
| |
| j 150 MWT Megawatts Thermal MWT 0 0 0 0 HLIF Hot Leg Injection Flow INCHES 0 0 0 0
| |
| , HPSIP .HPSI Header Pressure PSIG 1500 1500' 1500 1500 l LPSIP LPSI Header Pressure PSIG 690 '690 690 690.
| |
| ] LPSTL LPS Tank Level INCHES 35 35 35 35
| |
| ; LPSTP LPS Tank Pressure PSIG 10 10 10 .10 Main Coolant System Leakage Air l
| |
| ! Particulate Monitor (MCSLAPM)
| |
| South CPM OSH OSH OSH OSH
| |
| . North CPM OSH OSH OSH OSH
| |
| : Primary Vent-Stack Gas Monitor CPM 2.6ES As Read As Read As Read; j Primary Vent Stack Iodine Monitor CPM OOS 00S 00S 00S i Primary Vent Stack Particulate Monitor CPM 2.3E5 .As Read As Read As Read i Primary Water Tank-39 FEET 23 23 23 23-SCHM1 Subcooled Margin Monitor (DEG) 138 148 158 -170
| |
| ] SCHM2 Subcooled Margin Monitor (PSIG) 1048 1092' 1118 1150 i PZRP Pressurizer Pressure PSI 1500 1500 1500 1500 I
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| i i
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| i i
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| i 1228e
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| - - .. . - - . . - - - .. . . - - - - .- .. .- - .-.- - -- .. ~ . .. .
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| i Rev. 1
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| ; 3/21/87 Page 8.0-1f. L' jl YANKEE NUCLEAR POWER STATION.
| |
| ; GRADED EXERCISE MARCH 1987 i
| |
| l 8.0 OPERATIONAL DATA j Point Point
| |
| ) ID Name Description Units Time j 0915 9530 0945 1000 1 PZRL Pressurizer Level, Wide Range INCHES 120 120 120 120
| |
| ; 2 MCPRES1 Main Coolant Pressure, Loop 1 PSIG 1500 1500 1500 1500
| |
| ! 3 MCPRES2 Main Coolant Pressure. Loop 2 PSIG 1500- 1500 1500^ 1500 l 4 MCPRES3 Main Coolant Pressure, Loop 3 PSIG 1500 1500 1500 1500-5 TH1 Hot Leg Temperature, Loop 1 DEG. F 420 420 420 420 6 TH2 Hot Leg Temperature, Loop 2 DEC. F 420 420 420- .420 7 TH3 Hot Leg Temperature, Loop 3 DEG. F 420 420 420 420 8 TH4 Hot Leg Temperature, Imop 4 DEG. F 220 220 210 210 9 TCl Cold Leg Temperature, Loop 1 DEG..F 410 410 410 410 10 TC2 Cold Leg Temperature, Loop 2 DEG. F 410 410 410 410 1 11 TC3 Cold Leg Temperature Loop 3 DEG. F 410 410 410 410 l l 12 TC4 Cold Leg Temperature, Loop 4 DEG. F 220 220 210 210
| |
| ! 13 SGWRL1 Steam Generator Level, Loop 1 FEET 22 22 22 22
| |
| ! 14 SGWRL2 Steam Generator Level, Loop 2 FEET 22 22 22 23 1 15 SGWRL3 Steam Generator Level, Loop 3 FEET 22 22 '22 23
| |
| } 16 SGWRL4 Steam Generator Level Loop 4 FEET 0 0 0 0 l 17 SGP1 Steam Generator Pressure, Loop 1 PSIG 730 735 725 675 '
| |
| j 18 SGP2 Steam Generator Pressure. Loop 2 PSIG 730 735 725 680 j 19 SGP3 Steam Generator Pressure, Loop 3 PSIG 730 735 725 675 1 20 SGP4 Steam Generator Pressure Loop 4 PSIG 0 0 0 0
| |
| ! 21 NPPR6 Nuclear Power Range, Channel 6 PERCENT 0 0 0 O j 22 NPPR7 Nuclear Power Range, Channel 7 PERCENT 0 0 0 0 f
| |
| 23 NPPR8 Nuclear Power Range, Channel 8 PERCENT 0 0 0 .0 24 NPIR4 Nuclear Inter. Range, Channel 4 AMPERES 1E-11 lE-11 1E-11 1E-11 l
| |
| 1
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| ! L 1228e i
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| O O O '
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| Rev. 1 3/21/87 Page 8.0-2f YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time 0915 0930 0945 1000 25 NPIR3 Nuclear. Inter. Range Channel 3 AMPERES lE-11 lE-11 1E-Il IE-11 26 NPSR2 Nuclear Source Range, Channel 2 CPS 10,000 10,000 10,000 10,000 27 NPSR1 Nuclear Source Range, Channel 1 CPS 10,000 10,000 10,000 10,000 28 SF1 Steam Flow,. Loop 1 LBS/HR x 103 55 55 55 55 29 SF2 Steam Flow, Loop 2 LBS/HR x 103 50 50 50 50 30 SF3 Steam Flow, Loop 3 LBS/HR x 103 50 50' -50 50 31 SF4 Steam Flow, Loop 4 LBS/HR x 103 o o o o 32 WF1 Feedwater Flow, Loop 1 LBS/HR x 103 o o o o 33 FWF2 Feedwater Flow, Loop 2 LBS/HR x 103. o o o o 34 WF3 Feedwater Flow Icop 3 LBS/HR x 103 o o o o 35 FWF4 Feedwater Flow, Loop 4 LBS/HR x 103 .o o o o 40 SLRAD1 Steam Line Radiation, Loop 1 MR/HR 10 10 10 10 41 SLRAD2 Steam Line Radiation, Loop 2 MR/HR 10 10 10 10 42 SLRAD3 Steam Line Radiation, Loop 3 MR/HR 75 75 75 75 43 SLRAD4 Steam Line Radiation, Loop 4 MR/HR 100 100 100 100 44 VCPLR VC Pressure. Low Range PSIG 1.2 1.2 1.2 1.2' 45 VCPHR1 VC Pressure, High Range 1 PSIG <3 <3 <3 <3 46 VCPHR2 VC Pressure, High Range 2 PSIG <3 <3 <3 <3 47 VCRAD1 VC Radiation, Channel 1 R/HR 1.0 1.0 -1.0 1.0 48 VCRAD2 VC Radiation, Channel 2 R/HR 1.0 1.0 1.0 1.0 49 VCH1 VC Hydrogen, Channel 1 PERCENT 0 0 0 0 1228e
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| O O O .
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| Rev. l'"
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| 3/21/87-Page 8.0-3f YANKEE NUCLEAR POWER STATION GRADED EXERCISE 3.
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| MARCH 1987 Point Point ID Name Description Units Time 0915 0930 0945 1000 50 VCH2 VC Hydrogen, Channel 2 PERCENT 0 0 0 0 51 VCL1 VC Flood Level, Channel 1 FEET 0 0 0 0 52 VCL2 VC Flood Level Channel 2 FEETO 0 0 0 .0-59 AEJRM Air Ejector Radiation Monitor CPM 300 300 300 300 60 SITL Safety Injection Tank Level FEET 25.5 25.5 25.5 '25.5 61 DWSTL Demineralized Water Tank Level FEET ,
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| 62 IAPA Instrument Air Pressure. Header N PSIG 95 95 95 .95 !
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| 63 IAPB Instrument Air Pressure, Header N PSIG 95 95 95 95 l 67 VBUSV Vital Bus Volts (Not in CR) . VOLTS 120 120 120 120-68 GMWE Gross Megawatts Electric MWE O O O O 69 STP Steam Throttle Pressure PSIG 0 0 0 0 70 VCDTL VC Drain Tank Level INCHES 15 15 15 15 71 FWT Feedwater Temperature DEG. F 90 90 90 90 ,
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| 72 OAT Outside Air Temperature DEG. F 63. 64 64 65 ,
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| i 74 PVSRAD PVS Noble Gas Radiation MR/HR As Read As Read As Read As Read 75 SIHPF/HPSIF SI High Pressure Flow GPM 0 0 0' O 76 SILPF SI Low Pressure Flow GPM 0 0 0 0 87 VCT11 VC Air Temperature, RTD 911 Deg. F 105 105 105 105 88 VCT12 VC Air Temperature, RTD 912 'Deg. F 105 105 105 105 89 VCT13 VC Air Temperature, RTD 913 Deg. F 105 105 105 105 90 VCT14 VC Air Temperature, RTD 914 Deg. F 105 105 105 105 91 VCT15 VC Air Temperature, RTD 915 Deg. F 115 115 115 115 92 VCT16 VC Air Temperature, RTD 916 Deg. F 105 105 105 105.
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| 93 VCT17 VC Air Temperature, RTD 917 Deg. F 77 77 77 77 94 VCT18 VC Air Temperature, RTD 918 Deg. F 74- 74 74 74 95 VCT19 VC Air Temperature, RTD 919 Deg. F 83 83 83 83 96 VCT20 VC Air Temperature, RTD 920 Deg. F 80 80 80 80 1228e
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| O O O Rev. 1 3/21/87 Page 8.0-4f YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point Time ID Name Description Units 0915 9530 0945 1000 97 CETH7 Core Exit Temperature, H7 DEF. F 420 420 420 420 98 CETG-3 Core Exit Temperature, G-3 DEF. F 420 420 420 420 99 CETB-7 Core Exit Temperature, B-7 DEF. F 420 420 420 420 100 CETH-5 Core Exit Temperature, H-5 DEF. F 420 420 420 420 101 CETF-7 Core Exit Temperature, F-7 DEF. F 420 420 420 420 102 CETD-8 Core Exit Temperature, D-8 DEF. F 420 420 420 420-103 CETE-5 Core Exit Temperature, E-5 DEG. F 420 420 420 420 104 CETC-3 Core Exit Temperature, C-3 DEG. F 420 420 420 420 108 RHT1 Reactor " Head" Temperature, 1 DEG. F 430 420 420 420 109 RHT2 Reactor " Head" Temperature, 2 DEG. F 430 420 420 420 1228e
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| O O O-Rev. 1 3/21/87 Page 8.0-5f YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 Point Point ID Name Description Units Time 0915 9530 0945 1000 150 MWT Megawatts Thermal MWT 0 0 0 0 HLIF Hot Leg Injection Flow INCHES 0 0 0 0 HPSIP HPSI Header Pressure PSIG 0 0 0 0 LPSIP LPSI Header Pressure PSIG 0 0 0 0 LPSTL LPS Tank Level INCHES 35 35 35 35 LPSTP LPS Tank Pressure PSIG 10 10 10 10 Main Coolant System Leakage Air Particulate Monitor (MCSLAPM)
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| South CPM OSH OSH OSH OSH North CPM OSH OSH OSH OSH Primary Vent Stack Gas Monitor CPM As Read As Read As Read As Read Primary Vent Stack Iodine Monitor CPM 00S 00S 00S 00S Primary Vent Stack Particulate Monitor CPM As Read As Read As Read As Read Primary Water Tank-39 FEET 23 23 23 23 SCHM1 Subcooled Margin Monitor (DEG) 180 180 180 180 SCHM2 Subcooled Margin Monitor (PSIG) 1207 1207 1207 1207' PZRP Pressurizer Pressure PSI 1500 1500 1500 1500 l
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| 1228e l
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| l E _. m
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| O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 9.0 RADIOLOGICAL DATA O
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| s O :
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 9.1 AREA RADIATION MONITORS i
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| !O 1
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| Rev. 1' 3/21/87 Page 9.1-1 9.1 Area Radiation Monitors (mR/hr Unless Noted Otherwise)
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| ARM No.
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| On Surveys CTMT Clock VC AARM (R/hr) VC (R/hr) Main Steam Lines PAB Chargina Pump Time No. 1 East No. 2 West Fuel Crane No. 1 No. 2 No. 3 No. 4 No. 1 No. 2 No. 3 0445 <1.0 <1.0 <1.0 0.5 0.5 0.1 0.5 10.0- 1.5 1.5 0500 <1.0 (1.0 (1.0 0.5 0.5 0.1 0.5 10.0 1.5 1.5 0530 <1.0 <1.0 <1.0 0.6 0.6 0.1 0.6 6.5 2.0 2.0 0615 <1.0 <1.0 <1.0 0.6 0.6 0.1 0.6 7.5 2.0 2.0 0700 <1.0 <1.0 <1.0 0.3 0.7 0.1 0.7 8.5 2.0 2.0 0730 1.0 1.0 1.0 1000 1000 1500 2000 500 400 400 0745 2.0 2.0 2.0 2300 2300 3800 4500 560 560 560 0800 5.0 5.0 5.0 1400 1400 4000 4800 600 600 600 0815 4.0 4.0 4.0 2100 2100 3150 4200 500 500 500 0830 1.0 1.0 1.0 250 250 375 500 100 100 100 0845 <1.0 <1.0 <1.0 10.0 10.0 75 100 15 3.0 3.0 0900 <1.0 (1.0 <1.0 10.0 10.0 75 100 12 2.0 2.0 0915 <1.0 <1.0 <1.0 10.0 10.0 25 100 12 2.0 2.0 0930 <1.0 <1.0 <1.0 10.0 10.0 75 100 12 2.0 2.0 1000 <1.0 <1.0 <1.0 10.0 10.0 75 100 12 2.0 2.0 1415e
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| : j. , GRADED EXERCISE i
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| i.
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| MARCH 1987-h l
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| ! YANKEE NUCLEAR. POWER STATION .
| |
| 4 l GRADED EXERCISE 1
| |
| l 1 '
| |
| ! MARCH 1987 t
| |
| s t -
| |
| i 4
| |
| i T
| |
| 4 t I
| |
| ;- 9.4- PRIMARY VENT STACK RELEASE DATA i
| |
| k t
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| | |
| Rev. 0 l 2/6/87 9.4-1 O--
| |
| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 9.4 Primary Vent Stack Release Data (Source Term)
| |
| Isotopic Conc. Time (uci/ce) 0730/0745 0745/0800 0800/0815 0815/0830 0830/0845 Noble Gases Kr-85m 2.5E-8 3.3E-8 3.5E-8 3.0E-8
| |
| * Kr-85 1.0E-8 1.3E-8 1.4E-8 1.2E-8
| |
| * Kr-87 3.5E 4.6E-8 4.9E-8 4.2E-8
| |
| * Kr-88 6.1E-8 7.9E-8 8.5E-8 7.3E-8
| |
| * Xe-133m 1.0E-8 1.3E-8 1.4E-8 1.2E-8
| |
| * Xe-133 2.1C-7 2.7E-7 2.9E-7 2.5E-7
| |
| * O Xe-135m 3.5E-8 4.6E-8 4.9E-8 4.2E-8
| |
| * Xe-135 1.2E-7 1.5E-7 1.6E-7 1.4E-7
| |
| * Total 5.0E-7 6.5E-7 7.0E-7 6.0E-7
| |
| * i ,
| |
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| |
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| |
| 1418e
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| | |
| Rev. 0 2/6/87 9.4-2 O YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 9.4 Primary Vent Stack Release Data (Source Term)
| |
| Isotopic Conc. Time
| |
| __juCi/cc) 0730/0745 0745/0800 0800/0815 0815/0830 0830/0845 Noble Cases I-131 2.4E-9 3.1E-9 3.4E-9 2.9E-9
| |
| * I-132 1.0E-9 1.3E-9 1.4E-9 1.2E-9
| |
| * I-133 3.7E-9 4.8E-9 5.2E-9 4.4E-9
| |
| * I-134 6.0E-10 7.8E-10 8.4E-10 7.2E-10
| |
| * I-135 2.3E-9 3.0E-9 3.2E-9 2.8E-9
| |
| * O Total 1.0E-8 1.3E-8 1.4E-8 1.2E-8
| |
| * Note: Primary vent stack sample exposure rates are "As Read".
| |
| * = Below detectable limits.
| |
| ~, 1410e U
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 9.5 CHEMISTRY DATA O
| |
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| |
| i GRADED EXERCISE .
| |
| i !
| |
| ! MARCH 1987 t i !
| |
| !. .i i
| |
| i f 1
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| 4 .
| |
| . i l- 9.5.1 REACTOR COOLANT ACTIVITY CONCENTRATIONS 1 !
| |
| I -1 I
| |
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| |
| | |
| Rev. 1 3/21/87 Page 9.5.1-1 (m }
| |
| 9.5.1 Reactor Coolant Activity Concentrations (uCi/ml)
| |
| Time 0445 0500. 0530 0615 0700 0715 Kr-85m 3.6E+00 3.6E+00 3.6E+02 3.6E+02 3.6E+02 3.6E+02 Kr-85 1.6E+00 1.6E+00 1.6E+02 1.6E+02 1.6E+02 1.6E+02 Kr-87 4.4E+00 4.4E+00 4.4E+02 4.4E+02 4.4E+02 4.4E+02 Kr-88 8.2E+00 8.2E+00 8.2E+02 8.2E+02 8.2E+02 8.2E+02 Xe-133m- 1.36E+00 1.36E+00 1.36E+02 1.36E+02 1.36E+02 1.36E+02 Xe-133 2.8E+01 2.8E+01 2.8E+03 2.8E+03 2.8E+03 2.8E+03
| |
| 'Xe-135m 4.8E+00 4.8E+00 4.8E+02 4.8E+02 4.8E+02 4.8E+02 Xe-135 1.5E+01 1.5E+01 1.5E+03 1.5E+03 1.5E+03 1.5E+03 Total Noble Gas 67 67 6700 6700 6700 6700
| |
| (,p) I-131 9.0E-01 9.0E-01 9.0E+01 9.0E+01 9.0E+01 9.0E+01 I-132 3.6E-01 3.6E-01 3.6E+01 3.6E+01 3.6E+01 3.6E+01 I-133 1.4E+00 1.4E+00 1.4E+02 1.4E+02 1.4E+02 1.4E+02 I-134 2.2E-01 2.2E-01 2.2E+01 2.2E+01 2.2E+01 2.2E+01 I-135 8.4E-01 8.4E-01 8.4E+01 8.4E+01 8.4E+01 8.4E+01
| |
| '' Total Iodine 3.7 3.7 370 370 370 370
| |
| () 1092e
| |
| - , ,w,- , - - - - - - - -
| |
| | |
| l Rev. 1 3/21/87
| |
| ~~ Page 9.5.1-2
| |
| .\-Y l 9.5.1 Reactor Coolant Activity Concentrations (uCi/ml) (Cont'd)
| |
| Time 0730 0745 0800 0815 0830 Kr-85m 3.7E+02 6.0E+02 6.5E+02 6.0E+02 6.0E+02 Kr-85 1.9E+02 3.1E+02 3.3E+02 3.1E+02 3.1E+02 Kr-87 5.3E+02 8.6E*02 9.3E+02 8.4E+02 8.2E+02 Kr-88 9.8E+02 1.6E+03 1.7E+03 1.6E+03 1.6E+03 Xe-133m 1.6E+02 2.6E+02 2.8E+02 2.6E+02 2.6E+02 s
| |
| Xe-133 3.4E+03 5.5E+03 5.9E+03 5.4E+03 5.4E+03 Xe-135m 5.7E+02 9.2E+02 9.9E+02 9.2E+02 9.2E+02 Xe-135 1.8E+03 2.9E+03 3.1E+03 2.9E+03 3.0E+03 Total Noble Gas 8.0E+03 1.3E+04 1.4E+04 1.3E+04 1.3E+04
| |
| ( I-131 3.9E+01 6.2E+01 7.0E+01 6.5E+01 6.5E+01 I-132 1.5E+01 2.4E+01 2.7E+01 2.5E+01 2.5E+01 I-133 6.0E+01 9.6E+01 1.1E+02 1.0E+02 1.0E+02 I-134 9.5E+00 1.5E+01 1.7E+01 1.5E+01 1.5E+01 I-135 3.6E+01 5.6E+01 6.5E+01 5.9E+01 5.9E+01 Total Iodine 160 252 289 264 264
| |
| () 1092e
| |
| | |
| c Rev. 1 3/21/87 Page 9.5.1-3 9.5.1 Reactor Coolant Activity Concentrations (uCi/ml) (Cont'd)
| |
| Time 0900 0930 1000 Kr-85m 6.0E+02 6.0E+02 6.0E+02 Kr-85 3.1E+02 3.1E+02 3.1E+02 Kr-87 8.0E+02 7.6E+02 7.0E+02 Kr-88 1.6E+03 1.6E+03 1.6E+03 Xe-133m 2.6E+02 2.6E+02 2.6E+02 Xe-133 5.4E+03 5.4E+03 5.4E+03 Xe-135m + + +
| |
| Xe-135 3.0E+03 3.2E+03 3.3E+03 Total Noble Gas 1.3E+04 1.3E+04 1.3E+04
| |
| \ I-131 6.5E+01 6.7E+01 7.0E4A1 I-132 2.5E+01 2.3E+01 2.0E+01 I-133 1.0E+02 1.0E+02 1.0E+02 I-134 1.5E+01 1.5E+01 1.5E+01 I-135 5.9E+01 5.9E+01 5.9E+01 Total Iodine 264 264 264 i
| |
| | |
| y- - - , . - - - -
| |
| '+Y YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 9.5.2 VAPOR CONTAINMENT AIR CONCENTRATIONS O
| |
| 4 1097e
| |
| | |
| Rev. 1 3/21/86 j-~c Page 9.5.2-1 9.5.2 Vapor Containment Air Concentrations (uCi/cc)
| |
| Time 0500 0530 0615 0700 0730 Kr-85m
| |
| * 1.1E-06 1.1E-06 1.1E-06 5.0E-06 Kr-85
| |
| * 4.8E-07 4.8E-07 4.8E-07 3.0E-06 Kr-87
| |
| * 1.3E-06 1.3E-06 1.3E-06 5.1E-06 Kr-88
| |
| * 2.5E-06 2.5E-06 2.5E-06 1.0E-05 Xe-133m 3.0E-07 4.0E-07 4.0E-07 4.0E-07 2.6E-06 Xe-133 4.6E-06 8.4E-06 8.4E-06 8.4E-06 4.9E-05 Xe-135m
| |
| * 1.4E-06 1.4E-06 1.4E-06 5.0E-06 Xe-135 1.0E-07 4.4E-06 4.4E-06 4.4E-06 2.0E-05 Total Noble Gas 5.0E-06 2.0E-05 2.0E-05 2.0E-05 1.0E-04
| |
| ("%
| |
| (s-) I-131 3.2E-09 1.2E-08 1.2E-08 1.2E-08 7.2E-08 I-132
| |
| * 5.0E-09 5.0E-09 5.0E-09 3.0E-08 I-133 5.3E-09 1.9E-08 1.9E-08 1.9E-08 1.1E-07 I-134
| |
| * 3.0E-09 3.0E-09 3.0E-09 1.8E-08 I-135
| |
| * 1.1E-08 1.1E-08 1.1E-08 6.8E-08 Total Iodine 8.5E-09 5.0E-08 5.0E-08 5.0E-08 3.0E-07
| |
| * Less than detectable
| |
| ) 1097e
| |
| | |
| Rev.-1 !
| |
| 3/21/86 Page 9.5.2-2 p.y-
| |
| : (s,): i 9.5.2 Vapor Containment Air Concentrations (uCi/cc) (Cont'd)
| |
| Time 0800 0830 0900 0930 1000 Kr-85m 8.7E-06 7.9E-06 7.9E-06 7.9E-06 7.9E-06
| |
| .Kr-85 5.1E-06 4.6E-06 4.6E-06 4.6E-06 4.6E-06 Kr-87 8.9E-06 8.0E 8.0E-06 8.0E-06 8.0E-06 Kr-88 1.7E-05 1.5E-05 1.5E-05 1.5E-05 1.5E-05 Xe-133m 4.5E-06 4.1E-06 4.1E-06 4.1E-06 4.1E-06
| |
| .Xe-133 8.5E-06 7.7E-06 7.7E-06 7.7E-06 7.7E-06 Xe-135m 8.7E-06 7.9E-06 7.9E-06 7.9E-06 7.9E-06 Xe-135 3.5E-06 3.1E-06 3.1E-06 3.1E-06 3.1E-06 Total Noble Gas 1.75E-04 1.6E-04 1.6E-04 1.6E-Oh 1.6E-04 I-131 1.3E-07 1.1E-07 1.1E-07 1.1E-07 1.1E-07 O 'I-132 5.2E-08 4.7E 4.7E-08 4.7E-08 4.7E-08 I-133' 1.9E-07 1.7E-07 1.7E-07 1.7E-07 1.7E-07 I-134 3.1E-08 2.8E-08 2.8E-08 2.8E-08 2.8E-08 ,
| |
| I-135 1.1E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 Total Iodine 5.25E-07 4.8E-07 4.8E-07 4.8E-07 4.8E-07 I
| |
| +
| |
| f
| |
| | |
| _ _ - . _ _ _ . _ . . ~ . . . . . . - _ . _ _ _ _ . _ _ . _ . . . . . - - _ . . . _ _ - . _ . _ . _ . . . _ . _ _ - . _ _ _
| |
| i 4
| |
| l 1
| |
| I i-Y YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 1
| |
| t
| |
| (_
| |
| l
| |
| ! 9.5.3 SECONDARY SIDE STEAM ACTIVITY CONCENTRATIONS i~
| |
| l l
| |
| t i
| |
| i.
| |
| J t
| |
| e P
| |
| i 1473e c
| |
| -..,- - --. . . _ - - - - , _ _ . . . . . - . , . . _ _ . , . . , _ __ . - , . . - - ~ - - - , . -
| |
| | |
| I Rev. 1 3/03/87 Page 9.5.3-1 SECTION 9.5.3 SECONDARY SIDE STEAM ACTIVITY CONCENTRATIONS (uCi/cc)
| |
| TIME Radioisotope 0630 0700 0715 Kr-85m -
| |
| 1.6E-2 8.5E-1 Kr-85 -
| |
| 6.4E-3 3.4E-1 Kr-87 -
| |
| 2.2E-2 1.2 Kr-88 -
| |
| 3.9E-2 2.1 Xe-133m -
| |
| 6.4E-3 3.4E-1 Xe-133 -
| |
| 1.3E-1 7.1 Xe-135m -
| |
| 2.2E-2 1.2 Xe-135 -
| |
| 7.4E-2 3.9 Total Noble Gas 3.2E-1 1.7E-1 I-131 -
| |
| 6.7E-7 3.6E-5 I-132 -
| |
| 2.8E-7 1.5E-5 I-133 -
| |
| 1.0E-6 5.6E-5 I-134 -
| |
| 1.7E-7 9.0E-6 I-135 -
| |
| 6.4E-7 3.5E-5 Total Iodine 2.8E-6 1.5E-4
| |
| () 1473e
| |
| | |
| Rev. 1-3/03/87 Page 9.5.3-2 SECTION 9.5.3 SECONDARY SIDE STEAM ACTIVITY CONCENTRATIONS (uCi/cc)
| |
| TIME 6
| |
| Radioisotope 0730 0745 0800 0815 0830 - 1000 Kr-85m 4.0E+1 6.5E+1 7.0E+1 6.5E+1 6.5E+1 Kr-85 1.6E+1 2.6E+1 2.8E+1 2.6E+1 2.6E+1 Kr-87 5.6E+1 9.1E+1 9.8E+1 9.1E+1 9.1E+1 Kr-88 9.8E+1 1.6E+2 1.7E+2 '1.6E+2 1.6E+2 Xe-133m 1.6E+1' 2.6E+1 2.8E+1 2.6E+1 2.6E+1-Xe-133 3.4E+2 5.5E+2 5.9E+2 5.5E+2 5.5E+2 Xe-135m 5.6E+1 9.1E+1 9.8E+1 9.1E+1 9.1E+1 Xe-135' 1.8E+2 3.0+2 3.2E+2 3.0E+2 3.0E+2 O Total Noble Gas 8.0E+2 1.3E+3 -1.4E+3 1.3E+3 1.3E+3 I-131 7.7E-4 1.2E-3 1.3E-3 1.3E-3 2.6E-5 I-132 3.2E-4 5.0E-4 5.3E-4 5.3E-4 1.1E-5 I-133 1.2E-3 1.9E-3 2.0E-3 2.0E-4 4.1E-5 I-134 1.9E-4 3.0E-4 3.2E-4 3.2E-4 6.6E-5 I-135 7.4E-4 1.2E-3 1.2E-3 1.2E-3 2.5E-5 i
| |
| Total Iodine 3.2E-3 5.0E-3 5.3E-3 5.3E-3 1.1E-4 j
| |
| ID 1473e l- U
| |
| _ _ _ . . _ . _ _ _ _ _ _ _ - - ~ . _ _ _ . _ . . _ _ _ . _ _ _ _ _ _ . _ . _ _ . _ _ _ _ . - _ _ _ _ _ _ _ - . - - _ _ _ . . _ _ , _ _ _ _ _ .
| |
| | |
| _u_m h4.e .A . 4 a E.&, __ @ .. A a.4, - 4 a m -.,s4 4
| |
| . i G YANKEE NUCLEAR POWER STATION i
| |
| i GRADED-EXERCISE j l MARCH 1987 f
| |
| a f
| |
| I l
| |
| 9.5.4 REACTOR COOLANT AND SECONDARY SIDE j_ i (BLOWDOWN) SAMPLE DOSE RATES
| |
| 'l 4
| |
| i i
| |
| j
| |
| *-. . . .,_____._,_-__..,....._-_-....m.--_.,,_--_... . . . . . - _ _ . . - , _ . . - - _ - , _ - - _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ - _ _ _ _ _ . . _ . , _ . , . _ . -
| |
| | |
| Rev. 1 g- 3/21/87 !
| |
| ( ]j Pg. 9.5.4.-l -
| |
| 9.5.4 REACTOR COOLANT SAMPLE DOSE RATES l
| |
| UNSHIELDED SHEILDED lmR/hr per cc)* (1 in. lead in mR/hr per cc)*
| |
| TIME CONTACT 1 FT. CONTACT 1 FT.
| |
| 0445-0500 2.0E0 1.4E-2 2.5E-2 1.8E-4 0530-0715 2.0E+2 1.4E0 2.SEO 1.8E-2 0730 8.8E+1 6.lE-1 1. LEO 7.6E-3 0745 1.4E+2 9.6E-1 1.7EO 1.2E-2 0800 1.6E+2 1.1EO 2.0E0 1.4E-2 0815-1000 1.4E+2 1.0E0 1.8E0 1.3E-2 i
| |
| *Given dose rates must be mutiliplied by the sample volume in
| |
| () in cubic centimeters.
| |
| I O
| |
| | |
| Rev. 1 3/11/87 Pg. 9.5.4-2 9.5.4 SG#4 BLOWDOWN SAMPGE DOSE RATES UNSHIELDED 3HEILDED (mR/hr per cc)* (1 in, lead in mR/hr per cc)*
| |
| TIME CONTACT 1 FT. CONTACT 1 FT.
| |
| 0700 1.5E-3 1.lE-5 1.9E-5 1.3E-7 0715 8.2E-2 5.7E-4 1.0E-3 7.lE-6 0730 1.8E0 1.2E-2 2.2E-2 1.5E-4 0745 2.7E0 1.9E-2 3.4E-2 2.4E-4 -
| |
| 0800 2.9E0 2.0E-2 3.6E-2 2.5E-4
| |
| '0815 2.9E0 2.0E-2 3.6E-2 2.5E-4 0830 6.0E-2 4.2E-4 7.5E-4 5.2E-6
| |
| *Given dose rates must be multiplied by the sample
| |
| ) volume in cubic centimeters.
| |
| NOTE: All other SG Blowdown samples "as. read" 1
| |
| i 1
| |
| 0
| |
| | |
| O YANKEE NUCLEAR POWER STATION
| |
| ' GRADED EXERCISE MARCH 1987 3
| |
| t l;
| |
| i LO I
| |
| 9.5.5 STEAM GENERATOR #4 BLOWDOWN SAMPLE t
| |
| ACTIVITY CONCENTRATIONS e
| |
| 3 O
| |
| | |
| Rev. 0 3/11/87 Pg. 9.5.5-l ;
| |
| . /'] SG #4
| |
| '- 9.5.5 BLOWDOWN SAMPLE ACTIVITY CONCENTRATION (uCi/cc) 0630 0700 0715 0730 I-131 - 6.7E-4 3.6E-2 7.7E-1 I-132 - 2.8E-4 1.5E-2 3.2E-1 I-133 - 1.0E-3 5.6E-2 1.2E0 I-134 -
| |
| 1.7E-4 9.0E-3 1.9E-1 I-135 -
| |
| 6.4E-4 3.5E-2 7.4E-1 Total 2.8E-3 1. 5 E-1 3.2 Iodine 0745 0800 0815 0830 I-131 1.2E0 1.3E0 1.3E0 2.6E-2 I-132 5.0E-1 5.3E-1 5.3E-1 1.lE-2 I-133 1.9EO 2,0E0 2.0E-1 4.lE-2 I-134 3.0E-1 3.2E-1 3.2E-1 6.6E-3 I-135 1.2E0 1.2E0 1.2E0 2.5E-2 Total 5.0 5.3 5.3 1.lE-1 Iodine l
| |
| l l
| |
| Note: All other SG samples are "as read" l
| |
| O i
| |
| | |
| l 1
| |
| l YANKEE NUCLEAR POWER STATION GRADED EXERCISE
| |
| 'i MARCif 1987 9.6 0FF-SITE MONITORING TEAM OBSERVER INSTRUCTIONS / DATA
| |
| ;0 t
| |
| O 1099e 1
| |
| | |
| l Rev. 0
| |
| /~'h 2 / 4 / 11 7 s s/ Page 9.6-1 YANKEE NUCLEAR POWER STATION '
| |
| GRADED EXERCISE MARCH 1987 9.6 0FF-SITE' MONITORING TEAM OBSERVER INSTRUCTIONS / DATA Off-site plume centerline whole body dose rates have been estimated as a function of time and distance from the site using a variable trajectory dose assessment model. Geographical representations of the plume are provided in this package for each 15-minute average of meteorological conditions, starting at 07:30 a.m. During the exercise, off-site Monitoring Team Observers will use the information contained in this package to provide field monitoring teams with radiological data for various times and locations.
| |
| During the exercise, the Off-Site Monitoring Coordinator will direct Off-Site Monitoring Teams to locations relative to the meteorological conditions postulated for the exercise scenario. Observers will use Figures 9.6-1 through 9.6-6 to provide survey results to the off-site monitoring teams.
| |
| - Figures 9.6-1 through 9.6-6 depict the plume conditions at various times throughout the exercise. Each figure will be used for a 15-minute time interval as indicated in each key. These figures represent a plume width which is equivalent to a 3-sigma value of the centerlire conditions. Since the figures show a plume width relative to the centerline, gamma dose rates and iodine air sample count rates can be estimated for the outer edges of the plume by multiplying the provided centerline rates by 0.01. Radiological data for other locat!ons within the plume can be calculated as a function of the centerline end outer edge values at a given segment / distance. Radiological data has been provided for each particular segment at centerline. Dose and count rates for locations between two segments can be estimated as a function of the values at those segments.
| |
| Prior to the exercise an instruction session will be provided to the Off-Site Monitoring Team Controllers on the use of this package.
| |
| Specific actions which Off-Site Monitoring Team Controllers should take during the exercise can be listed as follows:
| |
| : 1. As Off-Site Monitoring Tamam are designated, check that OP-3311
| |
| " Emergency Off-Site Radiation Monitorin.," is followed by team members. This will incinuy the inittel equipment check.
| |
| 1099e
| |
| | |
| Rev. 0
| |
| .p g
| |
| 2/4/87 Page 9.6-2
| |
| : 2. While enroute to your assigned monitoring location, or while traversing the plume, use the attached figures and tables to issue appropriate radiological data.
| |
| -3. Attempt to estimate the team's accrued exposure as a function of their continual job assignment. Do not issue pocket dosimeter results to team members, unless they actually simulate checking their dosimeter reading. The pocket dosimeters in the kits have a range of 0-500 mR. which are subdivided into 20 mR intervals. Try to provide realistic values! They also may have 0-5 R dosimeters given to them. Always check to ask them the range.
| |
| : 4. Ask the Off-Site Monitoring Teams what equipment they have available for their use. Ask them the scales associated with the equipment; log these answers to ensure that you do not provide them with data that exceeds the range of their equipment. If, at any point during the exercise, a situation occurs where the upper range-of their equipment is exceeded, then issue them an "off-scale high" value.
| |
| : 5. If the Off-Site Monitoring Team stops to take an air sample:
| |
| : a. Report the appropriate whole body dose levels at that location.
| |
| : b. As sample counts are completed, report the appropriate data from Figures 9.6-1 through 9.6-6. These figu.es assume that a 15 ft3 air sample was taken. In some instances, the teams may be dire,ted to take a shorter sample period. Under these circumstances, you should adjust the figure values to account for the actual sample volume.
| |
| : c. If the team attempts to count the samples while still in tha plume, then the Controller should estimate the RM-14. HP-210, or PIC-6A radiation survey instrument background count rate using the following relationships, and add them to the given count rates:
| |
| (1) 17 mR/hr will cause the RM-14, HP-210 survey instrument to read "off-scale high"; and (2) The upper range of RM-14, HP-210 equals 60,000 cpm.
| |
| O 1099c
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| of f-site andtelegical conditions et Clect Tisedh M7 'S
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| .k M O N A tr R ,RA3L Servey Inet.: FIC+64 $A E $t C tW
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| f YANKEF. NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 O 9.7 ONSITE MONITORING DATA i
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| l-O
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| * I Rev. O
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| \ 3/10/87 s EL uzs ss'c*
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| g ,f , Pg. 9.7-1 i
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| FIGURE 9.7-1
| |
| ;i SITE AREA CONTAMINATION MAP 1
| |
| 4
| |
| | |
| Rev. 0 3/10/87 Pg. 9.7-2 TABLE 9.7
| |
| ' (_j ONSITE AIRBONE ACTIVITY (uCi/cc) and CONTAMINATION LEVELS TOTAL IODINE '
| |
| CONCENTRATIONS TIME LINE il0R DISTANCE LEVEL (dpm/100cm2) (uCi/cc)
| |
| -0730- 1 4.2E+5 4E-6 0745 2 5.3E+4 SE-7 3 2.8E+4- 2E-7 4 2.lE+4 2E-7 5 >l.1E+4 lE-7 6 2.6E+3 2.5E-8 7 1.9E+3 1.8E-8 (a) 0.5 mi 7,2E+2 7E-9 (a) 1.0 mi 3.4E+2 3E-9 f
| |
| I 0745 1 1.lE+6 6E-6 2 1.4E+5 7E-7 O 3 4
| |
| 5 7.3E+4 5.3E+4 2 EE+4 4E-7 3E-7 lE-7 6 6.9E+3 3.8E-8 7 4.8E+3 2.7E-8 (a) 0.5 mi 1.8E+3 lE-8
| |
| ; (a) 1.0 mi 5.3E+2 SE-9 0800 -
| |
| f 1 1.7E+6 6E-6 2 2.lE+5 7E-7 3 1.lE+5 4E-7 4 8.7E+4- 3E-7 5 4.3E+4 lE-7 6 1.lE+4 3.8E-8 7 7.9E+3 2.7E-8 1.8E+3 lE-8 (a) 0.5 mi SE-9 (a) 1.0 mi 5.3E+2 O
| |
| | |
| - - = .
| |
| Rev. 1 TOTAL IODINE 3/21/87 CONCENTRATIONS 9.7-3 0815 END OF EXERCISE (uCi/cc) gg 0815- 0830 End LEVEL (dpm/100cm2 ) 0830 of Exericse A,j LINE # OR DISTANCE
| |
| 'l 2.4E+6 6E-6 lE-7 2 3.0E+5 7E-7 1.75E-8 3 1.6E+5 4E-7 6.7E-9 4 1.2E+5 3E-7 7E-9 5 6.0E+4 lE-7 2.5E-9 6 1.5E+4 3.8E-8 6.25E-10 7 1.1E+4 2.7E-8 4.5E-10 (a) 0.5 mi 1.8E+3 lE-8 2.5E-10 (a) 1.0 mi 5.3E+2 SE-9 lE-10 ON-SITE AMBIENT RADIATION LEVELS AFTER PLUME PASSAGE LINE # SURFACE LEVEL WAIST LEVEL mR/hr cpm mR/hr cpm 1 15.0 36,000 4.0 9,600 2 2.0 4,500 0.5 1,200 3 1.0 2,400 0.3 720
| |
| () 4 5
| |
| 0.7 0.40 1,800 900-0.2 0.10 480 240 6 0.10 300 0.03 70 7 0.06 150 0.01 25 MILES
| |
| .5 0.01 30 Bkg. Ekg.
| |
| 1.0 Bkg. Bkg. Bkg. Bng.
| |
| l . Note: If players walk through a contaminated area the observer should provide data to them if they frisk their shoes anytime afterwards. Observers can obtain the shoe contamination level by dividing the surface level cpm or mR/hr reading from the table above by 100 for any given isodose area that the player may have walked through. For example:
| |
| If a player walks from the gatehouse to the PAB after the plume has passed and they walk within isodose curve number 3 from Figure 9.7-1 they will observe 2,400 cpm /100 = 24 cpm on the bottom of their shoes when they eventually frisk themselves.
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| ()
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| i 4
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| .e. -, - - - . - . .-- . . _ . . . - , _ - _ . . _ . . . _ , . , . . . . . - . _ _ , , . , . , , , , . . . , , ,,, . y_.7, . , - ,- . . _m.. _ .
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| E YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCil 1987 9 10.0 METEOROLOGICAL DATA O
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| . . . . ~ . . . . - . . . . . - . . . . . . . - = _ - . . .. - - - . ,..--
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| 1 l YANKEE NUCLEAR POWER STATION J
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| GRADED EXERCISE i
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| MARCH 1987 t
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| i l
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| ' 10.1 METEOROLOGICAL DATA (Control Room)
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| Revision 1 i 'Page 10.1-1
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| ! 3/24/87-l YANKEE NUCLEAR POWER STATION l GRADED EXERCISE l MARCH 1987 i
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| l 10.1 METEOROLOGICAL DATA (5:00 - 6:30) f Provided in Control Room (15-Minute Seaments) 5:00 ~5:15 5:30 5:45 6:00 '6:15 6:30
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| ! UPWSAV AVERAGE UPPER SPEED (MPH) 4.21 4.03 4.52 4.64 4.76 4.80 4.60 l UPWDAV AVERAGE UPPER DIRECTION (DEG) 13.9 10.2 8.5 6.5 9.7 10.0 9.0 i UPDTAV AVERAGE UPPER DELTA T (DEG F) -0.91 -1.01 -0.91 -1.01 -1.03 -1.06 -1.08 l UPDTST UPPER DELTA T STABILITY D D D D- D' D D l UPWDSD UPPER WIND DIRECTION (SIGMA) 14.91 14.82 12.62 12.12 13.50 14.81 15.51'
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| ] LOWSAV AVERAGE LOWER SPEED (MPH) 3.82 4.01 3.93 4.24 4.47 4.17 4.31 l LOWDAV AVERAGE LOWER DIRECTION (DEG) 10.0 10.4 11.2- 10.1 10.5 10.3' 10.2 LOWDSD LOWER WIND DIRECTION (SIGMA) 16.12 '11.58 10.61 11.21 11.58 15.01- 15.21 i LOTTAV AVERAGE LOWER TEMPERATURE (DEG F) 24.1 24.3 23.8 25.2 25.5 26.2 26.1-I LODPAV AVERAGE LOWER DEWPOINT (DEG F) 20.1 20.3 21.2 21.5 21.7 22.1 22.3-l SOLRAV AVERAGE SOLAR RADIATION (LANGS) 0.00 0.00 0.00 0.00 0.001 -0.001 0.001 j RAINTO 15-MINUTE RAINFALL (INCHES) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 l W1DTAV CIRCULATING H2O DATA AVERAGE l W2DTAV GENERATING H2O COOLER DATA AVERAGE
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| ! W3DTAV TURBINE LUBE OIL COOLING DATA AVERAGE j W4DTAV PRIMARY PLANT DATA AVERAGE
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| ! W5DTAV CREEWOO2 DATA AVERAGE 26.17 26.07 26.15 26.21 26.12 26.41 26.57 l WATIAV CIRCULATING H O2 TEMPERATURE AVERAGE 59.26 59.25 59.40 59.4 ~59.41 59.37 59.40 l WAT2AV CREEL (002 TEMPERATURE 64.5 64.4 64.6 .64.6 64.6 64.8 64.7 4
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| WAT3AV CIRCULATING H 2O INLET TEMPERATURE AVERAGE 39.3 39.2 39.3 39.4 39.3 39.4 39.2 f BUWSAV BACKUP AVERAGE SPEED (MPH) 3.92 4.13 3.81 4.12 5.25 ,4.01 4.35 i BUWDAV BACKUP AVERAGE DIRECTION (DEG) 11.2 10.1 9.5 10.1 10.2 10.4 9.5 l BUWDSD BACKUP DIRECTION (SIGMA) ,
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| ; BUDTAV BACKUP AVERAGE DELTA (DEG F) -0.28 -0.28 -0.28- --0.28 -0.29 -0.28 -0.28 BUDIST BACKUP DELTA T STABILITY D- D D D D D D 1488e a
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| Revision-1 Page 10.1-2' 3/24/87 YANKEE NUCLEAR POWER STATION-GRADED EXERCISE MARCH 1987 10.1 METEOROLOGICAL DATA (6:45 - 8:15)
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| Provided in Control Room (15-Minute Seaments) 6:45 7:00 7:15 7:30 7:45 8:00 8:15 UPWSAV AVERAGE UPPER SPEED (MPH) 4.51 4.11 4.0 4.1 4.21 4.41 4.31 UPWDAV AVERAGE UPPER DIRECTION (DEG) 358 0.0 6.8 9.8 10.3 10.1 11.3 UPDTAV AVERAGE UPPER DELTA T (DEG F) -1.15 .-l.12 -1.14 -1.16 -1.11 -1.11 -1.21 UPDTST UPPER DELTA T STABILITY D D 'D D D D D, UPWDSD UPPER WIND DIRECTION (SIGMA) 17.62- 19.51 12.5 14.01 14.95 9.52 9.56 LOWSAV AVERAGE LOWER SPEED (MPH) 2.01 2.52 2.80 3.21 3.97 4.01' 4.51 LOWDAV AVERAGE LOWER DIRECTION (DEG) 8.5 8.0 9.0 9.2 12.2~ 10.5 10.9 LOWDSD LOWER WIND DIRECTION (SIGMA) 21.31 24.5 14.9 16.7 15.12 10.3- 10.8 LOTTAV AVERAGE LOWER TEMPERATURE (DEG F) 26.8 27.3 27.0 27.2 27.2 28.3 28.1-LODPAV AVERAGE LOWER DEWPOINT (DEG F) 19.4 19.8 20.1 21.0 21.3 21.2 21.5 SOLRAV AVERAGE SOLAR RADIATION (LANGS) 0.001 0.001' O.001 0.002 0.002 0.002 0.002 RAINTO 15-MINUTE RAINFALL (INCHES) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WIDTAV CIRCULATING H 2O DATA AVERAGE W2DTAV GENERATING H2O COOLER DATA AVERAGE W3DTAV TURBINE LUBE OIL COOLING DATA AVERAGE W4DTAV PRIMARY PLANT DATA AVERAGE WSDTAV CREWOO2 DATA AVERAGE 26.65 26.01 25.59 24.31 24.21 23.01 23.01 WATIAV CIRCULATING H O 2 TEMPERATURE AVERAGE 59.31 59.2 59.91 58.7 57.21 56.2 56.31 WAT2AV CREEK 002 TEMPERATURE 64.5 64.7 64.8 '64.5 64.1 63.1 62.1 WAT3AV CIRCULATING H2O INLET TEMPERATURE AVERAGE 39.3 39.4 39.5 39.5 39.6 39.8 39.7 BUWSAV BACKUP AVERAGE SPEED (MPH) 4.61 4.13 4.54 4.32 4.12 4.43 4.22 BUWDAV BACKUP AVERAGE DIRECTION (DEG) 6.2 6.5 7.1 7.2 11.0 11.0 12.0 BUWDSD BACKUP DIRECTION (SIGMA)
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| BUDTAV BACKUP AVERAGE DELTA (DEC F) -0.28 -0.30 -0.31 -0.35 -0.40 -0.48 -0.52.
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| BUDIST BACKUP DELTA T STABILITY D D D D D- D D 1488e
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| n f. /m.
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| Revision 1 Page 10.1-3 3/24/87 YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 10.1 METEOROLOGICAL DATA (8:30 - 10:00)
| |
| Provided in Control Room (15-Minute Segments) 8:30 8:45 9:00 9:15 9:30 9:45 10:00 UPWSAV AVERAGE UPPER SPEED (MPH) 4.12 4.34 4.31 4.51 5.20 5.4 5.8 UPWDAV AVERAGE UPPER DIRECTION (DEG) 9.6 9.7 9.0 8.5 8.6 8.7 8.0 UPDTAV AVERAGE UPPER DELTA T (DEG F) -1.22 -1.21 -1.28 -1.30 -1.33 -1.30 -1.31 UPDTST UPPER DELTA T STABILITY D D D D D D D UPWDSD UPPER WIND DIRECTION (SIGMA) 10.2 10.71 10.51 10.6 9.81 11.21 10.51 LOWSAV AVERAGE LOWER SPEED (MPH) 3.91 3.85 3.61 3.9 4.1 4.2 4.8 LOWDAV AVERAGE LOWER DIRECTION (DEG) 10.1 10.2 9.5 10.2 10.8 10.2 10.1 LOWDSD LOWER WIND DIRECTION (SIGMA) 11.65 11.72 12.01 10.58 10.61 11.72 10.81 LOTTAV AVERAGE LOWER TEMPERATt)RE (DEG F) 28.0 28.7 29.5 29.3 29.8 .29.8 29.7 LODPAV AVERAGE LOWER DEWPOINT (DEG F) 22.1 22.3 22.8 23.1 23.5 23.4 23.1 SOLRAV AVERAGE SOLAR RADIATION (LANGS) 0.002 0.002 0.002 0.003 0.003 0.003 0.003 RAINTO 15-MINUTE RAINFALL (INCHES) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W1DTAV CIRCULATING H 2O DATA AVERAGE W2DTAV GENERATING H2O COOLER DATA AVERAGE W3DTAV TURBINE LUBE OIL COOLING DATA AVERAGE W4DTAV PRIMARY PLANT DATA AVERAGE W5DTAV CREEK 002 DATA AVERAGE 22.17 21.35 21.31 21.50 20.11 20.19 20.15 WATIAV CIRCULATING H O 2 TEMPERATURE AVERAGE 55.11 55.01 55.31 55.10 54.70 54.12 54.31 i WAT2AV CREEK 002 TEMPERATURE 60.3 60.2 60.1 60.0 59.7 59.4 59.2 l WAT3AV CIRCULATING H 2O INLET TEMPERATURE AVERAGE 39.7 39.5 40.1 40.1 40.2 40.1 40.2 j BUWSAV BACKUP AVERAGE SPEED (MPH) 4.22 4.31 4.28 3.98 3.99 4.01 4.88 '
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| BUWDAV BACKUP AVERAGE DIRECTION (DEG) 7.0 8.5 8.8 9.0 9.1 8.9 8.5 BUWDSD BACKUP DIRECTION (SIGMA)
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| BUDTAV BACKUP AVERAGE DELTA (DEG F) -0.51 -0.52 -0.51 -0.51 -0.53 -0.61 -0.62 BUDIST BACKUP DELTA T STABILITY D D D D D D D 1488e
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| .._ __._.__. _. _ . . . . _ _ . . . _ . . . _ = __ _ _ __. . . _ _ _ . . . _ . . _ . . . _ . _ . . _ _
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| e YANKEE NUCLEAR POWER STATION i
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| ! GRADED EXERCISE 4
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| MARCH 1987 l
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| 1 i
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| j ..
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| 1 f
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| I i
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| iO 10.2-METEOROLOGICAL DATA (EOF / ESC) e s
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| Rev. 1 Page 10.2-1 3/24/87
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| [s)
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| \- /
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 10.2 METEOROLOGICAL DATA (5:00 - 10:00)
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| PROVIDED IN EOF / ESC THROUGH CENTRAL MET (MIDA'S)
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| SITE: YANKEE R0WE YANKEE ATOMIC ELECTRIC COMPANY THE PLANT AT R0WE / -YR-LATITUDE LONGITUDE ELEV (FT ABOVE MSL) 42.72750 72.93190 1120.
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| USUL USIL USLL DTUL-DTLL DTUL-DTIL DTIL-DTLL TAL TDL PCP 2.3 0.0 2.3 0.0 0.0 0.0 0.0 14.4 0.0 JULIAN M/ M/ M/ DEGDEGDEG C/ C/ C/ DEG DEG MM DATE TIME DEG DEG DEG SEC SEC SEC 100M 100M 100M C C YYJJJ HH MM UDU UDI UDL USU USI USL STU/STI/STL DTUL DTUI DTIL TAL TDL PCP S 87 90 05 00 14 999 10 1.9 99.9 1.7 15 99 16 -1.0 99.9 99.9 -4.4 -6.6 0.0 4 87 90 05 15 10 999 10 1.8 99.9 1.8 15 99 12 -1.1 99.9 99.9 -4.4 -6.6 0.0 4 87 90 05 30 9 999 11 2.0 99.9 1.8 13 99 11 -1.0 99.9 99.9 -4.5 -5.9 0.0 4 87 90 05 45 7 999 10 2.1 99.9 1.9 12 99 11 -1.1 99.9 99.9 -3.8 -5.8 0.0 4 87 90 06 00 10 999 11 2.1 99.9 2.0 14 99 12 -1.1 99.9 99.9 -3.8 -5.5 0.0 4 2.1 99.9 3.9 15 99 15 -5.5 0.0 4
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| (~'T 87 90 06 15 10 s ,/ 87 90 06 30 9 999 10 999 10 2.1 99.9 1.9 16 99 15
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| -1.2
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| -1.2 99.9 99.9 99.9 99.9
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| -3.2
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| -3.2 -5.4 0.0 4 87 90 06 45 358 999 -9 2.0 99.9 0.9 18 99 21 -1.3 99.9 99.9 -2.9 -7.0 0.0 4 87 90 07 00 0 999 8 1.8 99.9 1.7 20 99 25 -1.3 99.9 99.9 -2.6 -7.0 0.0 4 87 90 07 15 7 999 9 1.8 99.9 1.3 12 99 15 -1.3 99.9 99.9 -2.6 -7.0 0.0 4 87 90 07 30 10 999 9 1.8 99.9 1.6 14 99 17 -1.3 99.9 99.9 -2.6 -6.6 0.0 4 87 90 07 45 10 999 12 1.9 99.9 1.8 15 99 15 -1.3 99.9 99.9 -2.6 -6.1 0.0 4 87 90 08 00 10 999 11 2.0 99.9 1.8 10 99 10 -1.3 99.9 99.9 -2.0 -5.8 0.0 4 87 90 08 15 11 999 11 1.9 99.9 2.0 10 99 11 -1.3 99.9 99.9 -2.0 -5.7 0.0 4 87 90 08 30 10 999 10 1.8 99.9 1.7 10 99 12 -1.4 99.9 99.9 -2.2 -5.5 0.0 4 87 90 08 45 10 999 10 1.9 99.9 1.7 11 99 12 -1.4 99.9 99.9 -1.8 -5.5 0.0 4 87 90 09 00 9 999 10 1.9 99.9 1.6 11 99 12 -1.5 99.9 99.9 -1.4 -5.5 0.0 4 87 90 09 15 9 999 10 2.0 99.9 1.7 11 99 11 -1.5 99.9 99.9 -1.3 -4.9 0.0 4 87 90 09 30 9 999 11 2.3 99.9 1.8 11 99 11 -1.5 99.9 99.9 -1.4 -4.7 0.0 4 87 90 09 45 9 999 10 2.4 99.9 1.9 11 99 11 -1.5 99.9 99.9 -1.4 -4.7 0.0 4 87 90 10 00 8 999 10 2.6 99.9 2.1 11 99 11 -1.5 99.9 99.9 -1.4 -4.9 0.0 4 YYJJJ HH MM UDU UDI UDL USU USI USL STU STI STL DTUL DTUI DTIL TAL TDL PCP S 1487e O
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| . ~ . - . ~ . - . - . . . . - - . . . . . . . - . . . - . - . . . - . - . . - - . - . . . - . - . . . - - . . - . . . . - . - . . . _
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| i YANKEE NUCLEAR POWER STATION 1 i GRADED EXERCISE ,
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| : s. 1 i !
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| ! MARCil 1987 .
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| t i t.
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| 1
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| . 4
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| : l i i 1- :
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| i b
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| !9 -10.3 WEATilER FORECAST i i ,
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| YANKEE NUCLEAR POWER STATION Rev. 1
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| / GRADED EXERCISE 3/25/87
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| ( ' MARCH 1987 Page 10.3-1
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| _TO BE PROVIDED TO DOSE ASSESSMENT PERSONNEL LOCATED IN THE CONTROL ROOM, TECHNICAL SUPPORT CENTER, EMERGENCY OPERATIONS FACILITY, AND THE ENGINEERING SUPPORT CENTER BY THE RESPECTIVE FACILITY CONTROLLERS, UPON REQUEST.
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| Generally cloudy conditions will prevail this morning as a weak offshore storm moves eastward out of the area. Light northerly winds are
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| ~
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| expected. Temperatures wil1 be in the mid 30's.
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| O o
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| There is a slight chance of a passing shower or snow flurry.
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| O :
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| )
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| .. .. .___._._-_______.__..._______.___...._._..___________m._-_______._ _ _ _ _ _ _ _ . _ . _ . . . . . - _ _
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| 1 1:
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| 1 i +
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| i i YANKEE NUCLEAR POWER STATION i
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| 4 GRADED EXERCISE l
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| I MARCH 1987 -
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| i -
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| 10.4 ESC METEOROLOGICAL DATA I
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| YANKEE NUCLEAR POWER STATION Rev. 1 GRADED EXERCISE 3/25/87 MARCH 1987 Page 10.4-1 O To be provided _to the ESC Meteorologist by the ESC Controller at 0700.
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| FORM: YA-REG-410.1 REVISIGN: 0 DATE: 3/87 WEATHER FORECAST FOR SITE /ANkE E Date of Forecast: 3 / !F7 Time of Forecast: 0?oo Current Site Meteorology (as of 0030 ):
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| Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower Y.O mph /0 deg from 0F '
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| in/15 min Upper 5. 0 mph /0 deg from -/. o & OF p Forecast Site Meteorology:
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| Delta-Time Wind Speed Wind Direction Temnerature Stability Precipitation A. 7g Lower S. 0 mph /0 deg from CF in/15 min Upper 5. O mph /0 deg from 0F D B. 7- 1 Lower f. 0 mph II,0 deg from 0F ~~ in/15 min Upper 7.o sph 3 6 0 deg f rom 0F D C. $ -/O Lower 6. O mph 3To deg from 0F ~ in/15 min Upper F. O mph 3 50 des from 0F D National Weather Service Forecast for site region:
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| Generally cloudy conditions will prevail this morning as a weak offshore storm moves eastward out of the area. Light northerly winds are expected. Temperatures will be in the mid 30's.
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| There is a slight chance of a passing shower or snow flurry.
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| Severe Weather Reports:
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| YANKEE NUCLEAR POWER STATION Rev. 1 GRADED EXERCISE 3/25/87 MARCH 1987 Page 10.4-2 1
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| O To be provide to the ESC Mteteorologist by the ESC Controller at 0800.
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| i 4
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| - FORM: YA-REG-410.1 REVISION:~ 0 DATE: 3/87 WEATHER FORECAST FOR SITE ANNE E Date of Forecast: I!Il !87 Time of Forecast: 0800 Current Site Meteorology (as of 07JO ):
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| Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 3 mph /o des from 0F - id15 min Upper V mph /0 deg from -/. / 6 0F o Forecast Site Meteorology:
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| Delta-j Time Wind Speed Wind Direction Temperature Stability Precipitation A. g- y Lower f sph Jf 0 deg from 0F F in/15 min i
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| Upper 6 mph "J60 deg from 0F Lower f sph TfeO des from 0F M /- in/15 min t
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| B. 1-/O T(,0 deg from 0F Upper 6 mph 7 o770 deg from P l- in/15 min i
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| * C. /d -// Lower mph aph 4 70 deg f rom 0F CF Upper &
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| National Weather Service Forecast for alte region:
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| Precipitation (in/15 min)
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| ]
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| Very Light (VL) Light (L) Medium (M) Heavy (H)
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| ~- .ol .05 .05 .09 .10 .19 .20 .30 Generally cloudy conditions will prevail this a'
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| morning as a weak offshore storm moves eastward out of the area. Light northerly winds are i
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| expected. Temperatures will be in the mid 30's.
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| Severe Weather Reports: There is a slight chance of a passing shower or snow flurry.
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| i h_ . . _ . _ _ _ _ . . . _ . . . _ _ _ . . . _ . _ _ _ . . . _ _ . _ , _ _ , . _ . . . . . . . _ _ . _ . , _ . - . _ _ . _ _ . , . . . . . , _ _ _ , . _ _ . _ _ . . , _ .
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| YANKEE NUCLEAR POWER STATION Rev. 1 GRADED EXERCISE 3/25/87 MARCH 1987 Page 10.4-3
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| \
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| V To be provide to the ESC Meteorologist by the ESC Controller at 0900.
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| FORM: YA-REG-410.1 REVISION: 0 DATE: 3/87 WEATHER FORECAST FOR SITE eke E Date of Forecast: 7/ 7 Time of Forecast: 0100 Current Site Meteorology (as of 0UO ):
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| Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower YO mph /0 deg from 0F in/15 min Upper v. o mph /0 deg from - /. J a CF D Forecast Site Meteorology:
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| Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. q-/0 Lower I sph 3.f0 deg from 0F P in/15 min Upper 6 mph f ro deg f rom 0F B. /o -// Lower 6 mph M O des from 0F P ' in!!5 min Upper 8 mph 790 deg from 0F C. //- / A Lower /0 mph E Vf deg from 0F P M in/15 min Upper /f sph e?VS deg from 0F National Weather Service Forecast for site region:
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| Generally cloudy conditions will prevail this morning as a weak offshore storm moves eastward out of the area. Light northerly winds are expected. Temperatures will be in the mid 30's.
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| There is a slight chance of a passing shower or snow flurry.
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| Severe Weather Reporta: Precipitation (in/15 min)
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| Very Light (VL) Light (L) Medium (M) licavy (II) I
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| .20 .30
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| .ol .05 .05 .09 .10 .19 l
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE MARCH 1987 CONTROLLER / OBSERVER BRIEFING AGENDA Date: March 30, 1987 Location: Yankee Information Center Time: 2:00 PM Introduction Bill Riethle Emergency Response Organization Bill Riethle Emergency Preparedness Organization Exercise Augmentation Schedule of Events / Exercise Evaluation Bill Riethle Briefings Debriefings Critique Exercise Logistics Bill Riethle Questions / Answers i L
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| Errata Tom Fuller j a
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| r Controller / Observer Assignments Tom Fuller
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| }t Exercise Manual Overview Tom Fuller Controller Guidelines ,
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| Objectives / Extent of play i I
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| Simulation List -
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| (Contamination Control) k Player Instructions Exercise Termination Exercise Scenario Tom Fuller Intitial Conditions I Sequence of Events (Event Messages, Mini Scenarios)
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| Operational Data Tom Fuller Radiological Data Tom Fuller Meteorological Data Tom Fuller Exercise Security Activities Jim Kay Emergency Response Facility / Facility controllers Offsite Monitoring Team Small Groups
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| f i
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| YANKEE NUCLEAR POWER STATION GRADED EXERCISE ;
| |
| MARCH 1987 ERRATA 1 Point ID 74 PVS Noble Gas Radiation on pages 8.0-3a, 3b, 3c, 3d, 3e, ,
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| f 3f should read "As Read" (or 0.1 mR/hr) for the daration of the exercise.
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| : 2. The Primary Vent Stack Gas Monitor should read 100 CPM for the duration of the exercise. The Primary Vent Stack Particulate Monitor should read 75 CPM for the duration of the exercise. These parameters are listed on pages 8.0-5a, 5b, Sc , 5d , Se , Sf . !
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| : 3. News Media Center Message Cards will be provided to players upon the discretion of the News Media Center Controller.
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| : 4. Page 9.1-3 Switchgear Room ARM should read 5.0 (mR/hr) rather than 50 (mR/hr).
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| : 5. Page 8.0-lf Loop 4 SI Pressure should be added to the parameter list.
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| All values are zero.
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| : 6. Pages 5.5-4 and 6.1-15, Bleedline radiation monitor alarm nessage Cr -M-2a has been deleted since these alarms are provided on strip chart messages.
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| : 7. Page 5.5-6 Turbine Hall radiological alarm, CR-M-2b has been deleted since this alarm is provided on strip chart messages.
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| : 8. Page 3.3-2, Simulation List #15 should be added to say "The Control Room SAS Operators should SIMULATE notifications to NEPSCO Superintendent, Harriman Station, and NEPSCO #4 Hydro Station.
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