ML18047A429

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Responds to NRC 820528 Ltr Requesting Addl Info Re NUREG-0737,Item I.A.2.1, Upgraded Senior Reactor Operator & Reactor Operator Training, & Item II.B.4, Training for Mitigating Core Damage.
ML18047A429
Person / Time
Site: Palisades, Big Rock Point, 05000000
Issue date: 07/06/1982
From: Vandewalle D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM NUDOCS 8207130361
Download: ML18047A429 (32)
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consumers Power company David J VandeWalle Nuclear Licensing Administrator General Offices: 1945 Wes~ Parnall Road, Jackson, Ml 49201 * (517) 788-1636 July 6, 1982 Dennis M Crutchfield, Chief Operating Reactors Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

DOCKET 50-255 - LICENSE DPR PALISADES PLANT NUREG-0737 (I.A.2.1 AND II.B.4) UPGRADED SRO AND RO TRAINING AND TRAINING FOR MITIGATING CORE DAMAGE -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION In NRC letter dated May 28, 1982, additional information was requested regarding NUREG-0737 Item I.A. 2. 1 "Upgraded SRO and RO Training" and Item II.B.4 "Training for Mitigating Core Damage" for Consumers Power Company's Big Rock Point and Palisades Plants. Specifically, this May 28, 1982 letter contained four questions dealing with the above topics, requiring response by Consumers Power Company. Attachment A provides our responses. Attachments B and C provide further detail on both the generic Prevention and Mitigation of Core Damage lectures and the training in specific procedures.

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Nuclear Licensing Administrator CC Administrator, Region III, USNRI NRC Resident Inspector-Big Rock ioint Attachments A, B & C oc0682-0010al42 0207130:361. ,-82.07 06 PDR ADOCK 05000155 p PDR

ATTACID1ENT A BIG ROCK POINT & PALISADES PLANTS Consumers Power Company Response To NRC May 28, 1982 LETTER ic0682-0010cl42

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ATTACHMENT A CONSUMERS POWER COMPANY RESPONSE TO NRC MAY 28, 1982 LETTER Q 1. The training programs for reactor operators and for senior reactor operators replacement and the requalification program for reactor operators have lectures which appear to have the potential for covering the subjects of heat transfer, fluid flow and thermodynamics as called out in enclosure 1 of Denton's March 28, 1980, letter. Do these lectures in fact cover this material and is the coverage to the level spelled out in enclosure 2 of the Denton letter?

  • A 1. The lectures are specifically tailored to address the recommendations of HR Denton's March 28, 1980 letter, Enclosure 2.

Q 2. The section in your response to NUREG-0737, dated December 19, 1980 pertaining 'to II.B.4 states that your training program does not include some of the topics in Enclosure 3 of Denton's March 28, 1980 letter.

For item II.B.4 please provide a detailed outline of the training program for mitigating core. damage, including the number of training hours involved. Your outline can include any training program which relates to the training for mitigating core damage. Follow the guidelines given in the enclosure 3 of H. R. Denton's letter dated March 28, 1980 and INFO Guidelines for Training to Recognize and Mitigate the Consequences of Core Damage (Document Number STG-01, Rev. 1, January 15, 1981). NRC requires a minimum of 80 contact hours of training for mitigating core damage. Any omission from the list of topics in the enclosure 3 will not be acceptable to NRC without explicit and adequate justification.

A 2. Many of the items under topics A through F of Enclosure 3 to HR Denton's letter of March 28, 1980 pertain to equipment or procedures which are of a plant specific nature and, as such, are not included in our lectures on Prevention and Mitigation of Core Damage. Instead they are addressed in training lecture's on the plant's Emergency Operating Procedures, Off-Normal Operating Procedures and Site Emergency Plan Implementing Procedures. Attachments B and C for Big Rock Point and Palisades, respectively, provide further detail on both the generic Prevention and Mitigation of Core Damage lectures and the training in procedures provided to complete the recommendations of Enclosure 3.

Consumers Power Company considers training programs involving heat transfer, fluid flow and thermodynamics to be an integral part of the training for mitigating core damage. The training programs covering these topics involve 80 contact hours for each plant and are in addition to the hours stated in attachments B and C. Therefore, Consumers Power Company satisfies the NRC minimum of 80 contact hours of training for mitigating core damage.

Q 3. Do the training and requalification program elements which involve heat transfer, fluid flow, thermodynamics and accident mitigation involve 80 contact hours? (A contact hour of instruction is a one-hour period in which the course instructor is present or available for instructing or nu0682-0010b142

Big Rock Point & Palisades Plants Response to NRC 5/28/82 Letter assisting students; lectures, seminars, discussions, problem-solving sessions, and examinations are considered contact periods under this definition.)

A 3. The initial training provided for new license candidates and for requalification of personnel already licensed at the time of the implementation of the program in heat transfer, fluid flow, thermodynamics, and accident mitigation exceeded 80 contact hours.

Subsequent requalification lecture topics are selected on an as-needed basis reflecting the general results of the annual examinations, input from operations supervisors, and available operational experience information. Special requalification programs are provided for individuals exhibiting deficiencies in required knowledge or skills.

The aggregate hours devoted to these specific topics in a given year will depend upon the indicated need for such training.

Q 4. Is there an increased emphasis on reactor and plant transients in the reactor operator and senior reactor operator training programs? If there is, does this training deal with both normal transients and abnormal (accident) transients?

A 4. (a) Yes. License candidate training now specifically addresses these topics, and requalification training for simulators is approximately double that provided prior to the accident at TMI-2.

(b) Emphasis is placed in training both on prevention (response to normal transients), and mitigation (response to abnormal transients).

nu0682-0010bl42

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ATTACHMENT B BIG ROCK POINT PLANT Training for Mitigating Core Damage (GE Degraded Core Presentation)

(16 Hours) and Listing of Emergency and Off-Normal Procedures for Which Training is Conducted (80 Hours) nu0682-0010b142

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TRAINING FOR MITIGATING CORE DAMAGE (GE DEGRADED CORE PRESENTATION)

THE COURSE OUTLINE

  • HEAT SOURCES
  • CORE COOLING MERCHANISMS
  • FUEL AND CORE DAMAGE THRESHOLD
  • RECOGNITION OF INADEQUATE CORE COOLING
  • SPECIFIC DEGRADED CORE CONDITIONS (H. DENTON'S LETTER)

USE OF FIXED OR MOVABLE INCORE DETECTORS INSTRUMENT RESPONSE DURING ACCIDENT CONDITIONS

- RADIOCHEMICAL RESULTS FROM A DEGRADED CORE CORROSION EFFECTS

- RESPONSE OF PROCESS AND AREA RADIATION MONITORS

- DETERMINING DOSE RATES INSIDE CONTAINMENT FROM DETECTORS OUTSIDE CONTAINMENT

- GAS GENERATION

  • EXAM

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VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS ONP - OFF NORMAL PROCEDURES Index ONP 2.0 OFF NORMAL PROCEDURES ONP 2.1 LOSS OF SERVICE AIR SYSTEM 2 .1.1 Symptoms 2.1.2 Automatic Actions 2.1.3 Immediate Operator Action 2.1.4 Subsequent Operator Action ONP 2.2 LOSS OF INSTRUMENT AIR SYSTEM 2.2.1 Symptoms 2.2.2 Automatic Operations 2.2.3 Immediate Operator Action 2.2.4 Subsequent Operator Action DNP 2.3 LOSS OF CONDENSATE SYSTEM 2.3.1 Loss of Condensate Pump (One-Pump Operation) 2.3.1.1 Symptoms 2.3.1.2 Automatic Actions 2.3.1.3 Immediate Operator Action 2.3.1.4 Subsequent Operator Action 2.3.2 Loss of Condensate Pump (With Two-Pump Operation) 2.3.2.1 Symptoms 2.3.2.2 Automatic Operations 2.3.2.3 Immediate Operator Action 2.3.2.4 Subsequent Operator Action 2.3.3 Condensate Demineralizer Failure 2.3.3.1 Symptoms 2.3.3.2 Automatic Actions 2.3.3.3 Immediate Operator Action 2.3.3.4 Subsequent Operator Action 2.3.4 Failure of Makeup Valve 2.3.4.1 Symptoms 2.3.4.2 Automatic Actions 2.3.4.3 Immediate Operator Action 2.3.4.4 Subsequent Operator Action 2.3.5 Failure of Reject Valve 2.3.5.1 Symptoms 2.3.5.2 Automatic Operations 2.3.5.3 Immediate Operator Action 2.3.5.4 Subsequent Operator Action 2.3.6 Failure of Fill Valve 12/18/81 ONP - i Rev 23 br0781-2066a123-20

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  • VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.3.6.1 Symptoms 2.3.6.2 Automatic Operations 2.3.6.3 Immediate Operator Action 2.3.6.4 Subsequent Operator Action ONP 2.4 LOSS OF CONTAINMENT INTEGRITY 2.4.1 Symptoms 2.4.2 Automatic Actions 2.4.3 Immediate Operator Action 2.4.4 Subsequent Operator Actions ONP 2.5 ABNORMAL RADIOACTIVE RELEASES IN CONTAINMENT BUILDING AND EMERGENCY ENTRY 2.5.1 Symptoms 2.5.2 Automatic Actions 2.5.3 Immediate Operator Actions 2.5.4 Subsequent Operator Actions ONP 2.6 LOSS OF CONTROL ROD DRIVE POSITION INDICATION 2.6.1 Loss of Control Rod Drive Position Indication (Individual Position) 2.6.1.1 Symptoms 2.6.1.2 Automatic Actions 2.6.1.3 Immediate Operator Action 2.6.1.4 Subsequent Action 2.6.2 Loss of Control Rod Position (Entire Control Rod Drive) 2.6.2.1 Symptoms 2.6.2.2 Automatic Action 2.6.2.3 Immediate Operator Action 2.6.2.4 Subsequent Action 2.6.3 Loss of Numerical Position or Color Position for Fully Inserted or Full Withdrawn Position 2.6.4 Loss of Position Indication - A-2 Thru C-6 or D-1 Thru F-5 2.6.4.1 Symptoms 2.6.4.2 Automatic Actions 2.6.4.3 Immediate Operator Actions 2.6.4.4 Subsequent Operator Actions ONP 2.7 MISPOSITIONED CONTROL RODS (INCLUDING ROD DROPS) 2.7.1 Rod Withdrawal Out-of-Sequence 2.7.1.1 Symptoms 2.7.1.2 Immediate Actions 12/18/81 ONP - ii Rev 23 br0781-2066a123-20

VOLIDIE 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.7.1.3 Subsequent Action 2.7.2 Rod Insertion Out-Of-Sequence 2.7.2.1 Symptoms 2.7.2.2 Subsequent Actions 2.7.3 An Uncoupled Rod Which Drops After the Drive is Withdrawn 2.7.3.1 Symptoms 2.7.3.2 Automatic Actions 2.7.3.3 Immediate Operator Actions 2.7.3.4 Subsequent Actions 2.7.4 Suspected Uncoupled Control Rod During Power Operations 2.7.4.1 Symptoms 2.7.4.2 Automatic Actions 2.7.4.3 Immediate Operator Actions 2.7.4.4 Subsequent Operator Actions ONP 2.8 SINGLE ROD INSERT FAILURE 2.8.1 Symptoms 2.8.2 Automatic Operations 2.8.3 Immediate Operator Actions 2.8.4 Subsequent Operator Action ONP 2.9 MULTIPLE ROD INSERT FAILURE 2.9.2.1 Symptoms 2.9.2.2 Automatic Actions 2.9.2.3 Immediate Operator Actions 2.9.3.1 Symptoms 2.9.3.2 Automatic Actions 2.9.3.3 Immediate Operator Action 2.9.3.4 Subsequent Operator Actions ONP 2.10 LOSS OF CONDENSER COOLING WATER SYSTEM 2.10.1 Symptoms 2.10.2 Automatic Actions 2.10.3 Immediate Operator Actions 2.10.3.1 For Condenser Circulating Water Pumps Overload 2.10.3.2 For Circulating Water Pump Trip - One Pump Operating 2.10.3.3 For Circulating Water Pump Trip - Two Pumps Operating 2.10.3.4 For Condenser Low Vacuum Alarm 2.10.3.5 For Condenser Low Vacuum Scram 2.10.4 Subsequent Operator Action 2.10.4.1 For Circulating Water Pump Overload 12/18/81 ONP - iii Rev 23 br0781-2066a123-20

VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.10.4.2 For Circulating Water Pump - One Pump Operating 2.10.4.3 For Circulating Water Pump - Two Pumps Operating 2.10.4.4 For Condenser Low Vacuum Alarm 2.10.4.5 For Condenser Low Vacuum Scram ONP 2.11 LOSS OF MAKEUP DEMINERALIZER SYSTEM

~ .11.1 Loss of Water From the Well Water System 2.11.1.1 Symptoms 2.11.1.2 Automatic Operations 2.11.1.3 Immediate Operator Actions 2.11.1.4 Subsequent Operator Action 2.11.2 Failure of Demineralizer Water Feed Pump 2.11.2.1 Symptoms 2.11.2.2 Automatic Operations 2.11.2.3 Immediate Operator Actions 2.11.2.4 Subsequent Operator Action 2 .11. 3 Failure of Controls 2.11.3.1 Symptoms 2.11.3.2 Automatic Operations 2.11.3.3 Immediate Operator Action 2.11.3.4 Subsequent Operator Action 2 .11. 4 Failure of Sand Filters 2.11.4.1 Symptoms 2.11.4.2 Automatic Operations 2.11.4.3 Immediate Operator Actions 2.11.4.4 Subsequent Operator Action 2.11.5 Failure of Demineralizer on High Conductivity or Total Flow 2.11.5.1 Symptoms 2.11.5.2 Automatic Operations 2.11.5.3 Immediate Operator Actions 2.11.5.4 Subsequent Operator Action ONP 2.12 LOSS OF WELL WATER SYSTEM 2.12.1 Loss of Well Pump 2 .12 .1.1 Symptoms 2 .12 .1. 2 Automatic Operations 2 .12 .1. 3 Immediate Operator Action 2.12.1.4 Subsequent Operator Action 2.12.2 Loss of Domestic Water Pump 2:12.2.1 Symptoms 2.12.2.2 Automatic Operations 2.12.2.3 Immediate Operator Action 2.12.2.4 ?ubsequent Operator Action 2.12.3 Failure of the Domestic Accumulator 12/18/81 ONP - iv Rev 23 br0781-2066a123-20

VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.12.3.1 Symptoms 2.12.3.2 Automatic Operations 2.12.3.3 Immediate Operator Action 2.12.3.4 Subsequent Operator Action ONP 2.13 LOSS OF COOLING WATER TO EMERGENCY CONDENSER 2.13.1 Symptoms 2.13.2 Automatic Operations 2.13 .3 Immediate Operator Actions 2.13.4 Subsequent Operator Action ONP 2.14 LOSS OF EMERGENCY DIESEL GENERATOR 2.14.1 Symptoms 2 .14 .1.1 Automatic Action 2 .14 .1. 2 Immediate Operator Action 2 .14 .1. 3 Subsequent Operator Actions 2.14.2 Second Standby Emergency Diesel Generator 2.14.2.1 Operation of Standby Portable Generator ONP 2.15 TURBINE GENERATOR TRIPS 2.15.1 Symptoms 2.15.2 Automatic Actions 2.15.3 Immediate Operator Actions 2.15.4 Subsequent Operator Actions ONP 2.16 LOSS OF FIRE PROTECTION SYSTEM 2.16.1 Loss of Jockey Fire Pump 2 .16 .1.1 Symptoms 2 .16 .1. 2 Automatic Operations 2 .16 .1. 3 Immediate Operator Action 2.16.1.4 Subsequent Operator Action 2.16.2 Loss of Electric Fire Pump 2.16.2.1 Symptoms 2.16.2.2 Automatic Operations 2.16.2.3 Immediate Operator Actions 2.16.2.4 Subsequent Operator Action 2.16.3 Loss of Diesel Fire Pump 2.16.3.1 Symptoms 2.16.3.2 Automatic Operations 2.16.3,3 Immediate Operator Actions 2.16.3.4 Subsequent Operator Action 2.16.4 Break in Fire System Header 2.16.4.1 Symptoms 2.16.4.2 Automatic Operations 2.16.4.3 Immediate Operator Actions 12/18/81 ONP - v Rev 23 br0781-2066a123-20

VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.16.4.4 Subsequent Operator Action 2.16.5 Loss of Flow or High AP on Strainer 2.16.5.1 Symptoms 2.16.5.2 Immediate Operator Action 2.16.5.3 Subsequent Operator Action 2.16.6 Malfunction of the Accumulator 2.16.6.1 Symptoms 2.16.6.2 Automatic Operations 2.16.6.3 Immediate Operator Action 2.16.6.4 Subsequent Operator Actions 2.16.7 Loss of Heat or Smoke Detectors 2.16.7.1 Symptoms 2.16.7.2 Automatic Actions 2.16.7.3 Immediate Operator Action 2.16.7.4 Subsequent Operator Action 2.16.8 Loss of Sprinkler System at the Containment Penetration (Exterior) Cable Spreading Area Under Control Room or Recirc Pump Sump Area 2.16.8.l Symptoms 2.16.8.2 Automatic Actions 2.16.8.3 Immediate Operator Action 2.16.8.4 Subsequent Operator Action 2.16.9 Loss of Fire Hose Station 2.16.9.1 Symptoms 2.16.9.2 Automatic Actions 2.16.9.3 Immediate Operator Action 2.16.9.4 Subsequent Operator Action 2.16 .10 Loss of Penetration Fire Barriers Protecting Safety-Related Areas 2 .16 .10 .1 Symptoms 2 .16 .10. 2 Automatic Actions 2 .16 .10. 3 Immediate Operator Action 2.16 .10 .4 Subsequent Operator Action ATTACHMENT 2.16 A ONP 2.17 ABNORMAL OFF-GAS OR STACK-GAS 2.17.1 Abnormal Off-Gas or Stack-Gas 'Release 2.17.1.1 Symptoms 2.17.1.2 Automatic Operations*

2.17.1.3 Immediate Operator Action 2.17.1.4 Subsequent Operator Action 2.17.2 The Off-Gas Monitor Loses Sensitivity 2.17.2.1 Symptoms 2.17.2.2 Automatic Operations 2.17.2.3 Immediate Operator Action 2.17.2.4 Subsequent Operator Action ONP 2.18 LOSS OF TRANSMISSION SYSTEM 12/18/81 ONP - vi Rev 23 br0781-2066a123-20

VOLUME 3:

e OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.18.1 Generator On Line - No Scram 2 .18 .1.1 Symptoms 2 .18 .1. 2 Automatic Actions 2 .18 .1..3 Immediate Operator Actions 2 .18 .1. 4 Subsequent Operator Action 2.18.2 Generator On Line - Scram Occurs 2.18.2.1 Symptoms 2.18.2.2 Automatic Actions 2.18.2.3 Immediate Operator Actions 2.18.2.4 Subsequent Operator Actions 2.18.3 Generator Is Off Line 2.18.3.1 Symptoms 2.18.3.2 Automatic Actions 2.18.3.3 Immediate Operator Actions 2.18.3.4 Subsequent Operator Actions 2.18.4 System Emergencies - Manual SeEaration From Transmission System for Severe System Disturbances 2.18.4.1 Symptoms 2.18.4.2 Automatic Actions 2.18.4.3 Immediate Operator Actions 2.18.4.4 Subsequent Operator Actions ONP 2.19 LOSS OF FEEDWATER SYSTEM 2.19.1 SymEtoms 2.19.2 Automatic Actions 2.19.3 Immediate Operator Actions 2.19.4 Subsequent 0Eerator Actions ONP 2.20 LOSS OF FEEDWATER 2.20.l SymEtoms 2.20.2 Automatic Actions 2.20.3 Immediate 0Eerator Action 2.20.3.1 One-Pump Operation 2.20.3.2 Two-Pump Operation 2.20.3.3 Slow-Decreasing Water Level 2.20.3.4 Subsequent Operator Actions

?.20.3.5 Feedwater Control Valve Failure 2.. 20 .3 .5 .1 Symptoms 2.20.3.5.2 Automatic Actions 2.20.3.5.3 Immediate Operator Actions 2.20.3.5.4 Subsequent Operator Actions ONP 2.21 CONDITIONS REQUIRING LIQUID POISON INJECTION

2. 21.1 SyrnEtoms 12/18/81 ONP - vii Rev 23 br0781-2066a123-20

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I' VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS

2. 21. 2 Automatic Actions
2. 21. 3 Immediate Operator Actions
2. 21.4 Subsequent Operator Actions 2.21.4.1 .To Shut Down Poison System 2.21.4.2 Removal of Liquid Poison From Nuclear Steam Supply System ONP 2.22 LOSS OF LIQUID POISON SYSTEM 2.22.l Symptoms
2. 22 .1.1 Poison System Control Circuits Failure
2. 22 .1. 2 Poison Tank Low Temperature
2. 22 .1. 3 Poison Air Supply Low Pressure
2. 22 .1.4 Poison' Tank Low Level
2. 22 .1.5 Poison Tank Shutoff Valve Failure
2. 22 .1. 6 Poison System Recirculating Control Valve Failure
2. 22 .1. 7 Improper Poison Solution Concentration 2.22.2 Automatic Actions 2.22.3 Immediate Operator Actions 2.22.3.1 Poison System Control Circuits Failure 2.22.3.2 Poison Tank Low Temperature 2.22.3.3 Poison Air Supply Low Pressure 2.22.3.4 Poison Tank Low Level 2.22.3.5 Poison Tank Shutoff Valve Failure 2.22.3.6 Poison System Recirculating Control Valve Failure 2.22.3.7 Improper Poison Solution Concentration 2.22.4 Subsequent Operator Actions 2.22.4.1 Poison System Control Circuiis Failure 2.22.4.2 Poison Tank Low Temperature 2.22.4.3 Poison Air Supply Low Pressure 2.22.4.4 Poison Tank Low Level 2.22.4.5 Poison Tank Shutoff Valve Failure 2.22.4.6 Poison System Recirculating Control Valve Failure 2.22.4.7 Improper Poison Solution Concentration ONP. 2.23 MALFUNCTION OF PRESSURE CONTROL SYSTEM (IPR AND BYPASS VALVE) 2.23.1 IPR Malfunction Opens Turbine Admission Valves
2. 23 .1.1 Symptoms
2. 23 .1. 2 Automatic Actions
2. 23 .1. 3 Immediate Operator Actions
2. 23 .1. 4 Subsequent Operator Actions 2.23.2 IPR Malfunction Closes Turbine Admission Valves 2.23.2.1 Symptoms 12/18/81 ONP - viii Rev 23 br0781-2066al23-20

VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS

2. 25 .1 Symptoms 2.25.2 Automatic Actions 2.25.3 Immediate Operator Action 2.25.4 Subsequent Operator Actions ONP 2.26 LOSS OF SERVICE WATER 2.26.1 Total Loss of Service Water 2.26.1.1 Symptoms 2.26.1.2 Automatic Actions 2.26.1.3 Immediate Actions
2. 26 .1. 4 Subsequent Action 2.26.2 Loss of One Service Water Pump 2.26.2.1 Symptoms 2.26.2.2 Automatic Actions 2.26.2.3 Immediate Operator Action 2.26.2.4 Subsequent Operator Actions 12/18/81 ONP - ix Rev 23 br0781-2066al23-20

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VOLUME 3:

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OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.26.3 Plugging of Basket Strainers and High Differential Pressure Across Traveling Screens 2.26.3.l Symptoms 2.26.3.2 Automatic Actions 2.26.3.3 Immediate Action 2.26.3.4 Subsequent Operator Action ONP 2.27 LOSS OF REACTOR RECIRCULATION FLOW 2.27.1 Symptoms 2.27.2 Automatic Actions 2.27.3 Immediate Operator Actions 2.27.3.l One Pump Trip 2.27.3.2 Two Pumps Trip 2.27.4 Subsequent Operator Actions 2.27.4.1 One Pump Trip 2.27.4.2 Two Pumps Trip ONP 2.28 ABNORMAL WATER QUALITY 2.28.1 Technical Specifications Limits (Reference 4.1.2b) 2.28.2 Plant Operating Limits 2.28.3 Symptoms 2.28.3.1 For High Conductivity 2.28.3.2 For Abnormal pH 2.28.3.3 High Chloride Ion Value 2.28.3.4 High Equilibrium Halogen Radioactivity Value 2.28.3.5 High Boron Content 2.28.4 Automatic Actions 2.28.5 Immediate Operator Actions 2.28.5.1 Immediate Operator Actions to Plant Operating Limits 2.28.6 Subsequent Operator Action 2.28.6.1 Conditions Requiring Plant Shutdown 2.28.6.2 Conditions Not Requiring Plant Shutdown ONP 2.29 LOSS OF CLEAN-UP DEMINERALIZER SYSTEM.

2.29.1 Clean-Up Pump Stoppage

2. 29 .1.1 Symptoms 2.29.1.2 Automatic Action
2. 29 .1. 3 Immediate Action
2. 29 .1.4 Subsequent Action 2.29.2 Depleted Resin Bed or High Differential Pressure Across Resin Bed 2.29.2.1 Symptoms 12/18/81 ONP - x Rev 23 br0781-2066a123-20

VOLUME 3:

e OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.29.2.2 Automatic Action 2.29.2.3 Immediate Action 2.29.2.4 Subsequent Action ONP 2.30* LOSS OF REACTOR COOLING WATER SYSTEM 2.30.1 Total Loss of Reactor Cooling Water System

2. 30 .1.1 Symptoms
2. 30 .1. 2 Automatic Actions
2. 30 .1. 3 Immediate Action
2. 30 .1. 4 Subsequent Action 2.30.2 Loss of One Reactor Cooling Water Pump 2.30.2.1 Symptoms 2.30.2.2 Automatic Action 2.30.2.3 Immediate Action 2.30.2.4 Subsequent Action ONP 2.31 REACTOR SCRAMS
2. 31. 1 Symptoms
2. 31. 2 Automatic Actions 2.31.3 Immediate Operator Actions 2.31.4 Subsequent Operator Action ONP. 2.32 LOW AND HIGH DRUM LEVELS 2.32.1 Symptoms
2. 32 .1.1 Low Drum Level
2. 32 .1. 2 High Drum Level 2.32.2 Automatic Actions 2.32.2.1 Low Drum Level 2.32.2.2 High Drum Level 2.32.3 Immediate Operator Actions 2.32.3.1 Low Drum Level 2.32.3.2 High Drum Level 2.32.4 Subsequent Operator Actions 2.32.4.1 Low Drum Level 2.32.4.2 High Drum Level ONP 2.33 ABNORMAL RELEASE OF RADIOACTIVITY IN LIQUIDS 2.33.1 Symptoms 2.33.2 Automatic Operations 2.33.3 Immediate Operator Actions 2.33.4 Subsequent Operator Actions ONP 2.34 LOSS OF SHUTDOWN COOLING SYSTEM 2.34.1 Symptoms 12/18/81 ONP - xi Rev 23 br0781-2066a123-20

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VOLUME 3:

OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.34.2 Automatic Actions 2.34.3 Immediate Operator Actions 2.34.4 Subsequent Operator Actions ONP 2.35 LOSS OF MOTOR GENERATOR SETS 2.35.1 Loss of Generator Regulation

2. 35 .1.1 Symptoms
2. 35 .1. 2 Automatic Actions
2. 35 .1. 3 Immediate Operator Action
2. 35 .1. 4 Subsequent Action 2.35.2 Loss of Voltage to the Motor Generator Set Prime Mover 2.35.2.1 Symptoms 2.35.2.2 Automatic Actions 2.35.2.3 Immediate Operator Action 2.35.2.4 Subsequent Actions ONP 2.36 LOSS OF STATION POWER 2.36.1 Plant at Power 2.36.1.1 Symptoms 2.36.1.2 Automatic Actions 2.36.1.3 Immediate Operator Actions
2. 36. 1. 4 Subsequent Operator Action 2.36.2 Plant Is Shut Down 2.36.2.1 Symptoms 2.36.2.2 Automatic Actions 2.36.2.3 Immediate Operator Actions 2.36.2.4 Subsequent Operator Actions 2.36.3 Partial Loss of Station Power - Plant at Power - Loss of 480-V Motor Control Bus lA 2.36.3.1 Symptoms 2.36.3.2 Automatic Actions 2.36.3.3 Immediate Operator Actions 2.36.3.4 Subsequent Operator Actions 2.36.4 Partial Loss of Station Power - Plant at Power - Loss of 480-V Motor Control Bus 2A 2.36.4.1 Symptoms 2.36.4.2 Automatic Actions 2.36.4.3 Immediate Operator Actions 2.36.4.4 Subsequent Operator Actions 2.36.5 Partial Loss of Station Power - Plant at Power - Loss of 480-V Motor Control Bus 2B 2.36.5.1 Symptoms 2.36.5.2 Automatic Actions 2.36.5.3 Immediate Operator Actions 2.36.5.4 Subsequent Operator Actions 12/18/81 ONP - xii Rev 23 br0781-2066al23-20

VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS ONP 2.37 RDS SYSTEM 2.37.1 One (1) Isolation Valve (CV-4180, -4181, -4182 or

-4183) Failed in "Closed" Position 2.37.1.1 Symptoms 2.37.1.2 Automatic Actions 2.37.1.3 Immediate Operator Actions 2.37.1.4 Subsequent Operator Actions 2.37.2 Depressurizing Valve (SV-4984, -4985, -4986 or

-4987) Leakage Downstream 2.37.2.1 Symptoms 2.37.2.2 Automatic Actions 2.37.2.3 Immediate Operator Actions 2.37.2.4 Subsequent Operator Actions 2.37.3 Isolation Valve (CV-4180, -4181, -4182 or

-4183) Leaking Internally Downstream 2.37.3.1 Symptoms 2.37.3.2 Automatic Actions 2.37.3.3 Immediate Operator Actions 2.37.3.4 Subsequent Operator Action 2.37.4 Air Leak on Instrument Air Supply System to Isolation Valves CB-4180, -4181, -4182, -4183 and Bypass Isolation Valve CV-4184 2.37.4.1 Symptoms 2.37.4.2 Automatic Actions 2.37.4.3 Immediate Operator Actions 2.37.4.4 Subsequent Operator Actions 2.37.5 One (1) Depressurization Valve (SV-4984, -4985,

-4986 or -4987) Failed in "Closed Position 2.37.5.1 Symptoms 2.37.5.2 Automatic Actions 2.37.5.3 Immediate Operator Action 2.37.5.4 Subsequent Operator Action 2.37.6 Loss of One (1) Uninterruptible Power Supply 2.37.6.1 Symptoms 2.37.6.2 Automatic Action 2.37.6.3 Immediate Operator Actions 2.37.6.4 Subsequent Operator Actions 2.37.7 Loss of RDS Containment Electrical Penetration Seal Pressure 2.37.7.1 Symptoms 2.37.7.2 Automatic Actions 2.37.7.3 Immediate Operator Actions 2.37.7.4 Subsequent Operator Actions ONP 2.38 LOSS OF FUEL POOL WATER LEVEL OR COOLING WATER 2.38.1 Symptoms 2.38.2 Automatic Actions 12/18/81 GNP - xiii Rev 23 br0781-2066al23-20

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VOLUME 3: OPERATING PROCEDURES - SYSTEM ONP - TABLE OF CONTENTS 2.38.3 Immediate Operator Actions 2.38.4 Subsequent Operator Actions 12/18/81 ONP - xiv Rev 23 br0781-2066al23-20

VOLUME 3: OPERATING PROCEDURES - EMERGENCY EMP - TABLE OF CONTENTS EMP - EMERGENCY PROCEDURES Index EMF 3.0 - EMERGENCY PROCEDURES EMF 3.1 - LOSS OF DC POWER SYSTEM 3 .1.1 Sudden Loss of DC Power System 3.1.1.1 Symptoms 3.1.1.2 Automatic Action 3.1.1.3 Immediate Operator Actions 3.1.1.4 Subsequent Operator Action 3 .1. 2 Gradual Loss of DC Power System 3.1.2.1 Symptoms 3.1.2.2 Automatic Actions 3.1.2.3 Immediate Operator Action 3.1.2.4 Subsequent Operator Actions EMF 3.2 LOSS OF NEUTRON FLUX INDICATION 3.2.1 Loss of Single Start-Up Channel During an Approach to Critical or During a Refueling Operation 3.2.1.1 Symptoms 3.2.1.2 Automatic Actions 3.2.1.3 Immediate Operator Actions 3.2.1.4 Subsequent Action 3.2.2 Loss of Intermediate Range Monitor(s)

Prior to Reaching 4% Position on 2/3 Picoammeter Range Switches 3.2.2.1 Symptoms 3.2.2.2 Automatic Action 3.2.2.3 Immediate Operator Actions 3.2.2.4 Subsequent Action 3.2.3 Loss of Power Range Monitors (Channels 1, 2 and 3) 3.2.3.l Symptoms 3.2.3.2 Automatic Action 3.2.3.3 Immediate Operator Actions 3.2.3.4 Subsequent Action 3.2.4 Loss of All Neutron Instrumentation or Infor-mation From All Instrumentation Is Unreliable 3.2.4.1 Symptoms 3.2.4.2 Automatic Action 3.2.4.3 Immediate Operator Action 3.2.4.4 Subsequent Action 12/18/81 EMF - i Rev 23 br0781-2105a123-20

VOLUME 3: OPERATING PRO.URES - EMERGENCY EMP - TABLE OF CONTENTS EMF 3.3 LOSS OF REACTOR COOLANT 3.3.1 Minor Loss of Reactor Coolant 1 Inside Containment 3.3.1.1 Symptoms 3.3.1.2 Automatic Action 3.3.1.3 Immediate Operator Actions 3.3.1.4 Subsequent Operator Actions 3.3.2 Major Loss of Reactor Coolant, Inside Containment 3.3.2.1 Symptoms 3.3.2.2 Automatic Actions 3.3.2.3 Immediate Operator Actions 3.3.2.4 Subsequent Operator Actions 3.3.3 Major Loss of Reactor Coolant 1 Outside Containment 3.3.3.1 Symptoms 3.3.3.2 Automatic Actions 3.3.3.3 Immediate Operator Actions 3.3.3.4 Subsequent Operator Actions 3.3.4 Loss of Coolant Accident in Conjunction With Loss of Off-Site Power EMF 3.4 FUEL HANDLING ACCIDENTS 3.4.1 Symptoms 3.4.2 Automatic Actions 3.4.3 Immediate Operator Action 3.4.4 Subsequent Operator Actions EMF 3. SA ATWS 3.5A.1 Symptoms 3.SA.2 Automatic Actions 3.5A.3 Immediate Operator Action 3.SA.4 Subsequent Operator Action EMF 3.7 EARTHQUAKE 3.7.1 Symptoms 3.7.2 Automatic Operations 3.7.3 Immediate Operator Action 3.7.4 Subsequent Operator Actions EMP 3.8 TORNADO 3.8.1 Symptoms 3.8.2 Automatic Operations 3.8.3 Immediate Operator Actions 12/18/81 EMP - i i Rev 23 br0781-2105a123-20

VOLUME 3:

e OPERATING PROCEDURES - EMERGENCY EMP - TABLE OF CONTENTS 3.8.4 Subsequent Operator Actions EMP 3.9 FLOODING 3.9.1 Symptoms 3.9.2 Automatic Operations 3.9.3 Immediate Operator Actions*

3.9.4 Subsequent Operator Action 12/18/81 EMP - iii Rev 23 br0781-2105al23-20

1

' *~VO*LUME 9A -

IMPLEMENTING PROCEDURES BIG ROCK POINT NUCLEAR PLANT SITE EMERGENCY PLAN TABLE OF CONTENTS (Contd)

EPIP Number Title P. Senior Engineer Q. Training Coordinator or Instructor R. Property Protection Supervisor

s. Security Shift Leader T. Security Officer
u. Technical Engineer
v. Administrative Supervisor or Technician
w. Plant Superintendent ~ec~etary/Health Physics Clerk/Technical Clerk X. Public Affairs Director or Personnel Director Y. Reactor Engineer Z. Licensed Training Instructor or Training Instructor AA. Chemical and Radiation Protection Technician BB. Telephone Switchboard Operator CC. General Health Physicist 5 Post-Accident Monitoring Procedures A. Estimation of Off-Site Dose B. Procedure To Determine High Stack Gas Releases C. Airborne Iodine Monitoring Under Accident Conditions - In Plant D. Procedure To Determine Extent of Core Damage (for 0% to 100%

Core Meltdown)

E. Procedure To Determine Extent of Core Damage (for Less Than 10%

Core Meltdown) 04/02/82 ii Rev 18 pr1181-2187a103

. VOLUME 9A IMPLEMENTING PROCEDURES BIG ROCK POINT NUCLEAR PLANT SITE EMERGENCY PLAN TABLE OF CONTENTS (Contd)

EPIP Number Title F. Environmental Monitoring G. Airborne Iodine Monitoring Under Accident Conditions Off Plant Site H. On Site (Out-of-Plant) Radiological Surveys 6 Supplemental Procedures A. Personnel Accountability/Search and Rescue B. Personnel Monitoring Evacuation and Reassembly C. Reentry/Recovery D. Emergency Equipment and Supplies: Inventory, Maintenance and Calibration E. First Aid and Medical Care F. Communication Methods G. Time-Distance-Dose Predictions Based on Percent Core Meltdown H. Emergency Dosimetry I. Training and Drills 7 General Office Nuclear Emergency Implementing Procedures A. General Office Nuclear Emergency Implementing Procedures 04/02/82 iii. Rev 18 pr1181-2187 a103

ATTACHMENT C PALISADES PLANT Training Prevention/Mitigation of Core Damage (16 Hours) and Listing of Emergency and Off-Normal Procedures for Which Training is Conducted (40 Hours) nu0682-0010bl42

NUCLEAR SEI\VICES DEPAR'l'!vfENT LESSON PLAN TITLE: PREVENTION/MI'rIGATION OF CORE DAMAGE INDEX PAGE I. OBJECTIVES 1 II. REFERENCES 1 III. PRERE~,UISITES 1 IV. PRESENTATION:

A. Intro 1 B. Prevention 2 C. Operation 3 D. Safety Functions 5 E. Inadequate Core Cooling Defined 7

2. Due to DNE 8
3. Due to Loss of Heat Sink 8 l~. Recovery from Loss of Heat Sink 10
5. Due to Loss of Coolant 10
6. Corrective Action for ICC from LOCA 12 7, Core Hec:citicality 13
8. Syr.iptoms Summarized 14 F. PWR Events Leading to ICC 14
1. Events & Methods of Analysis 1!~
2. Events Causing Anproach to Dirn at Power 14
3. Approach to DNE.l from Core Anomaly 16 4, Accidents with Potential fm.* Core Uncovery 17 a.. Instrument Response Capabilities . 17-26
b. LOCA with Potentia.i for ICC 27-35
c. Loss of* Heat Sink with Fotential for rec 35-43
d. Zero Power Events with Potential for ICC 44-46

PRODUCTION AND TRANSMISSION NUCLEAR SERVICES DEPART.MEilT LESSON PLAN TITLE: PREVENTION/MITIGATION OF CORE DAMAGE INDEX (Cont'd) PAGE

5. Patterns of Relevant Instrtunent Responses 46
a. Core Fluid Level 47
b. Heat Sink 47
c. Summary of Instrtunent Response Patterns 48 G. BWR Events Leading to ICC 51
l. Common Symptoms 51
2. Adequate Core Cooling 51
3. Range of Level Indication During Accident Conditions 52
4. Water Level 52
5. Level Response During Accidents 53
6. Indication of Operational ECCS 56
1. Other Indications of Core Condition 5'7
8. Summary of Di verse Methods of Monitoring Core Cooling in BWR's. 61 V. LESSON SUMMATION 62 A. Not Plant Specific 62 B. Operator's Role 62
c. . Safety Functions 62 D. Symptoms of ICC 63 E. Corrective Actions 63 F. *Natural Circulation 63 G. Questions Answered 63 VI. rn:~:eIFICATION OF PROCEDURES 63 VII. c:;~!?L:TION EX.~1 Attachment A 63

SECTION INDEX OFF NORMAL PROCEDURES (ONP's)

ONP 1 Loss Of Load ONP 2 Partial Loss Of Primary Coolant Flow ONP 3 Loss Of Feedwater ONP 4 Containment Isolation ONP 5 Control Rod Drop ONP 6 Excessive Control Rod Withdrawal ONP 7 Control Rod Trip Failure ONP 8 Uncontrolled Primary Coolant System Boron Dilution ONP 9 Excessive Load Increase ONP 10 Excessive Feedwater Increase ONP 11 Fuel Cladding Failure ONP 12 Acts Of Nature ONP 13 Reactor Regulator Failure ONP 14 Loss Of Condenser Vacuum -z ONP 15 Loss of Flux Indication ~

0 ONP 16 Inability To Drive Control Rod  :::0 ONP 17 Doss Of Shutdown Cooling s:

)>

--t ONP 18 Pressurizer Pressure Control Malfunctions

-0 ONP 19 Expected Transients z

ONP 20 Diesel Generator Manual Control

()

ONP 21 Natural Circulation 0

-0 ONP 22 Post Accident Hydrogen Handling -<

ONP 23 Primary Coolant Leak ONP 24.1 Loss of Preferred AC Bus v 10 II

.I.

ONP 24.2 Loss of Preferred AC Bus y 20 ONP 24. 3 Loss of Preferred AC Bus y 30 IONP 24.4 Loss of Pref erred AC Bus y 40 loNP 24.5 Loss of Instrument AC Bus y 01 i Rev 1

PALISAD.!!:t3 l-' LANT SECTION INDEX u'ERGEr!CY OPERATING PROCEDURES (EOP Is)

EOP 1 Reactor Trip EOP 2 Loss of AC Power EOP 3 Loss of Service Water EOP 4 Loss of Component Cooling EOP 5 Loss of Instrument Air EOP 6 Main Steam Line Break/Main Feedwater Line Break. -

Inside Containment EOP 7 Main Steam Line Break/Main Feedwater Line Break. -

Outside Containment EOP 8.1 Loss of Coolant Accident EOP 8.2 Steam Generator Tube Rupture EOP 9 Fuel Handling Accident EOP 10 Control Room Evacuation EOP 11 Loss of Containment Integrity i

I .,,z \

EOP 12 0 Abnormal Release of Radioactivity I

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i Rev 0

SITE EMERGENCY PLAN D-1 PALISADES PLANT Rev 0 APPENDIX D EMERGENCY IMPLEMENTATION PROCEDURES EI Activation of Emergency Plan Upon recognition that abnormal plant or site conditions exist, this procedure will be used to determine the appropriate Emergency Action Level(s) and to assure that all mandatory and subsequent actions are carried out.

EI Palisades Plant Actions/Notifications During an Emergency This procedure lists mandatory and subsequent notifications and actions for each level of emergency.

EI Communications and Notification This procedure details the notification format and provides call lists of off-site agencies. The primary and alternate communications lines are also described.

EI-4.1 - Activation of Technical Support Center This procedure describes the activation, staffing, physical facilities, equipment and operations of the TSC.

EI-4.2 - Activation of the. On-Site Operations Support Center This procedure describes the activation, staffing, physical facilities, equipment and operations of the OSC.

EI-4.3 - Activation of the Emergency Operations Facility This procedure describes the activation, staffing, physical facilities, equipment and operations of the EOF - South Haven Conference Center.

EI Reentry/Recovery This procedure provides guidelines for entry into the affected area of the plant after the emergency condition has been stabilized. It also provides guidelines for the initial recovery operation prior to the establishment of the Long-Term Recovery Organization.

EI Estimate of Off-Site Dose This procedure provides a method of estimating off-site integrated doses to the whole body and to the child thyroid and relating. those projected doses to the EPA PAGs.

EI Post-Accident Sampling This procedure provides methods and precautions for sampling and analyzing reactor coolant, sampling and analysis of containment air, and a method of determining airborne iodine concentrations in areas within the plant.

mi0381-0005h-89

SITE EMERGENCY PLAN D-2 PALISADES PI.ANT Rev 0 EI On-Site Radiological Monitoring This prncedure provides guidelines for post-accident radiological monitoring on site.

EI Off-Site Radiological Monitoring This procedure provides guidelines for past-accident radiological monitoring off site.

EI Environmental Assessment This procedure provides guidelines for post-accident collection and replace-ment of environmental TLDs, obtaining data from air monitoring stations, collection and asses~ment of waterborne effluents, and obtaining.

water/milk/vegetation samples.

EI Determination of Extent of Core Damage This procedure provides a method of estimating the degree of core damage during accident conditions.

EI-12 -.Personnel Accountability To provide guidelines and assign responsibility for personnel assembly and accountability.

EI Evacuation, Reassembly This procedure provides site evacuation procedures and the subsequent reassembly of personnel.

EI Radiological Medical Care This procedure provides guidelines on personnel emergency radiation expo~ure limits, personnel decontamination procedures, the use of thyroid blocking agents and the methods of transporting contaminated/injured victims to hospitals.

EI Training and Drills This procedure establishes training requirements for plant personnel and details the requirements for drills and exercises.

mi038 l-0005.h-89

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