ML18047A429

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 General Offices: 1945 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-6 -BIG ROCK POINT PLANT -DOCKET 50-255 -LICENSE DPR-20 -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 David J VandeWalle Nuclear Licensing Administrator 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.

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

. 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

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.. 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. Q 4. 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.

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 nu0682-0010b142 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)

. 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 v* VOLUME 3: OPERATING PROCEDURES

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

Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Loss of Condensate Pump (With Two-Pump Operation)

Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Action Condensate Demineralizer Failure Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Failure of Makeup Valve Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Failure of Reject Valve Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Action Failure of Fill Valve ONP -i br0781-2066a123-20 Rev 23 __ I

. . i.

• VOLUME 3: OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS ONP 2.4 ONP 2.5 ONP 2.6 ONP 2.7 12/18/81 2.3.6.1 2.3.6.2 2.3.6.3 2.3.6.4 Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Action LOSS OF CONTAINMENT INTEGRITY 2.4.1 2.4.2 2.4.3 2.4.4 Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Actions ABNORMAL RADIOACTIVE RELEASES IN CONTAINMENT BUILDING AND EMERGENCY ENTRY 2.5.1 2.5.2 2.5.3 2.5.4 Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions LOSS OF CONTROL ROD DRIVE POSITION INDICATION 2.6.1 2.6.1.1 2.6.1.2 2.6.1.3 2.6.1.4 2.6.2 2.6.2.1 2.6.2.2 2.6.2.3 2.6.2.4 2.6.3 2.6.4 2.6.4.1 2.6.4.2 2.6.4.3 2.6.4.4 Loss of Control Rod Drive Position Indication (Individual Position)

Symptoms Automatic Actions Immediate Operator Action Subsequent Action Loss of Control Rod Position (Entire Control Rod Drive) Symptoms Automatic Action Immediate Operator Action Subsequent Action Loss of Numerical Position or Color Position for Fully Inserted or Full Withdrawn Position Loss of Position Indication

-A-2 Thru C-6 or D-1 Thru F-5 Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions MISPOSITIONED CONTROL RODS (INCLUDING ROD DROPS) 2.7.1 2.7.1.1 2.7.1.2 Rod Withdrawal Out-of-Sequence Symptoms Immediate Actions ONP -ii br0781-2066a123-20 Rev 23

,-' . VOLIDIE 3: ONP 2.8 ONP 2.9 OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS 2.7.1.3 2.7.2 2.7.2.1 2.7.2.2 2.7.3 2.7.3.1 2.7.3.2 2.7.3.3 2.7.3.4 2.7.4 2.7.4.1 2.7.4.2 2.7.4.3 2.7.4.4 Subsequent Action Rod Insertion Out-Of-Sequence Symptoms Subsequent Actions An Uncoupled Rod Which Drops After the Drive is Withdrawn Symptoms Automatic Actions Immediate Operator Actions Subsequent Actions Suspected Uncoupled Control Rod During Power Operations Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions SINGLE ROD INSERT FAILURE 2.8.1 2.8.2 2.8.3 2.8.4 Symptoms Automatic Operations Immediate Operator Actions Subsequent Operator Action MULTIPLE ROD INSERT FAILURE 2.9.2.1 2.9.2.2 2.9.2.3 2.9.3.1 2.9.3.2 2.9.3.3 2.9.3.4 Symptoms Automatic Actions Immediate Operator Actions Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Actions ONP 2.10 LOSS OF CONDENSER COOLING WATER SYSTEM 12/18/81 2.10.1 2.10.2 2.10.3 2.10.3.1 2.10.3.2 2.10.3.3 2.10.3.4 2.10.3.5 2.10.4 2.10.4.1 br0781-2066a123-20 Symptoms Automatic Actions Immediate Operator Actions For Condenser Circulating Water Pumps Overload For Circulating Water Pump Trip -One Pump Operating For Circulating Water Pump Trip -Two Pumps Operating For Condenser Low Vacuum Alarm For Condenser Low Vacuum Scram Subsequent Operator Action For Circulating Water Pump Overload ONP -iii Rev 23 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 2.11.1.1 2.11.1.2 2.11.1.3 2.11.1.4 2.11.2 2.11.2.1 2.11.2.2 2.11.2.3 2.11.2.4 2 .11. 3 2.11.3.1 2.11.3.2 2.11.3.3 2.11.3.4 2 .11. 4 2.11.4.1 2.11.4.2 2.11.4.3 2.11.4.4 2.11.5 2.11.5.1 2.11.5.2 2.11.5.3 2.11.5.4 Loss of Water From the Well Water System Symptoms Automatic Operations Immediate Operator Actions Subsequent Operator Action Failure of Demineralizer Water Feed Pump Symptoms Automatic Operations Immediate Operator Actions Subsequent Operator Action Failure of Controls Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Action Failure of Sand Filters Symptoms Automatic Operations Immediate Operator Actions Subsequent Operator Action Failure of Demineralizer on High Conductivity or Total Flow Symptoms Automatic Operations Immediate Operator Actions Subsequent Operator Action ONP 2.12 LOSS OF WELL WATER SYSTEM 12/18/81 2.12.1 2 .12 .1.1 2 .12 .1. 2 2 .12 .1. 3 2.12.1.4 2.12.2 2:12.2.1 2.12.2.2 2.12.2.3 2.12.2.4 2.12.3 br0781-2066a123-20 Loss of Well Pump Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Action Loss of Domestic Water Pump Symptoms Automatic Operations Immediate Operator Action ?ubsequent Operator Action Failure of the Domestic Accumulator ONP -iv Rev 23

' . VOLUME 3: OPERATING PROCEDURES

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

-SYSTEM ONP -TABLE OF CONTENTS 2.16.4.4 2.16.5 2.16.5.1 2.16.5.2 2.16.5.3 2.16.6 2.16.6.1 2.16.6.2 2.16.6.3 2.16.6.4 2.16.7 2.16.7.1 2.16.7.2 2.16.7.3 2.16.7.4 2.16.8 2.16.8.l 2.16.8.2 2.16.8.3 2.16.8.4 2.16.9 2.16.9.1 2.16.9.2 2.16.9.3 2.16.9.4 2.16 .10 2 .16 .10 .1 2 .16 .10. 2 2 .16 .10. 3 2.16 .10 .4 Subsequent Operator Action Loss of Flow or High AP on Strainer Symptoms Immediate Operator Action Subsequent Operator Action Malfunction of the Accumulator Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Actions Loss of Heat or Smoke Detectors Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Loss of Sprinkler System at the Containment Penetration (Exterior)

Cable Spreading Area Under Control Room or Recirc Pump Sump Area Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Loss of Fire Hose Station Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Loss of Penetration Fire Barriers Protecting Safety-Related Areas Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action ATTACHMENT 2.16 A ONP 2.17 ABNORMAL OFF-GAS OR STACK-GAS 2.17.1 2.17.1.1 2.17.1.2 2.17.1.3 2.17.1.4 2.17.2 2.17.2.1 2.17.2.2 2.17.2.3 2.17.2.4 Abnormal Off-Gas or Stack-Gas

'Release Symptoms Automatic Operations*

Immediate Operator Action Subsequent Operator Action The Off-Gas Monitor Loses Sensitivity Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Action ONP 2.18 LOSS OF TRANSMISSION SYSTEM 12/18/81 ONP -vi br0781-2066a123-20 Rev 23 e VOLUME 3: 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 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 2.19.2 2.19.3 2.19.4 SymEtoms Automatic Actions Immediate Operator Actions Subsequent 0Eerator Actions ONP 2.20 LOSS OF FEEDWATER 2.20.l 2.20.2 2.20.3 2.20.3.1 2.20.3.2 2.20.3.3 2.20.3.4 ?.20.3.5 2 .. 20 .3 .5 .1 2.20.3.5.2 2.20.3.5.3 2.20.3.5.4 SymEtoms Automatic Actions Immediate 0Eerator Action One-Pump Operation Two-Pump Operation Slow-Decreasing Water Level Subsequent Operator Actions Feedwater Control Valve Failure Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions ONP 2.21 CONDITIONS REQUIRING LIQUID POISON INJECTION

2. 21.1 SyrnEtoms 12/18/81 ONP -vii br0781-2066a123-20 System Rev 23 I' .J'. ( VOLUME 3: OPERATING PROCEDURES

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

• VOLUME 3: OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS 2.23.2.2 2.23.2.3 2.23.2.4 2.23.3 2.23.3.1 2.23.3.2 2.23.3.3 2.23.3.4 2.23.4 2.23.4.1 2.23.4.2 Automatic Actions Immediate Operator Actions Subsequent Operator Actions Turbine BYPass Valve Malfunction Opens Turbine BYPass Valve Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions Turbine Bypass Valve Malfunction Closes Turbine Bypass Valve Symptoms Immediate Operator Actions ONP 2.24 LOSS OF CONDENSER VACUUM 2.24.1 2.24.2 2.24.3 2.24.4 2.24.5 2.24.6 2.24.7 Symptoms Automatic Actions With Reactor Pressure Below 450 Psig Automatic Actions With Reactor Pressure Above 450 Psig Immediate Operator Action on Gradual Loss of Condenser Vacuum Subsequent Operator Action on Gradual Loss of Condenser Vacuum Immediate Operator Action on Rapid Loss of Condenser Vacuum Subsequent Operator Action on Rapid Loss of Condenser Vacuum ONP 2.25 EMERGENCY SHUTDOWN 2. 25 .1 2.25.2 2.25.3 2.25.4 Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Actions ONP 2.26 LOSS OF SERVICE WATER 12/18/81 2.26.1 2.26.1.1 2.26.1.2 2.26.1.3 2. 26 .1. 4 2.26.2 2.26.2.1 2.26.2.2 2.26.2.3 2.26.2.4 br0781-2066al23-20 Total Loss of Service Water Symptoms Automatic Actions Immediate Actions Subsequent Action Loss of One Service Water Pump Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Actions ONP -ix Rev 23

,. -VOLUME 3: OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS 2.26.3 2.26.3.l 2.26.3.2 2.26.3.3 2.26.3.4 Plugging of Basket Strainers and High Differential Pressure Across Traveling Screens Symptoms Automatic Actions Immediate Action Subsequent Operator Action ONP 2.27 LOSS OF REACTOR RECIRCULATION FLOW 2.27.1 2.27.2 2.27.3 2.27.3.l 2.27.3.2 2.27.4 2.27.4.1 2.27.4.2 Symptoms Automatic Actions Immediate Operator Actions One Pump Trip Two Pumps Trip Subsequent Operator Actions One Pump Trip Two Pumps Trip ONP 2.28 ABNORMAL WATER QUALITY 2.28.1 2.28.2 2.28.3 2.28.3.1 2.28.3.2 2.28.3.3 2.28.3.4 2.28.3.5 2.28.4 2.28.5 2.28.5.1 2.28.6 2.28.6.1 2.28.6.2 Technical Specifications Limits (Reference 4.1.2b) Plant Operating Limits Symptoms For High Conductivity For Abnormal pH High Chloride Ion Value High Equilibrium Halogen Radioactivity Value High Boron Content Automatic Actions Immediate Operator Actions Immediate Operator Actions to Plant Operating Limits Subsequent Operator Action Conditions Requiring Plant Shutdown Conditions Not Requiring Plant Shutdown ONP 2.29 LOSS OF CLEAN-UP DEMINERALIZER SYSTEM. 12/18/81 2.29.1 2. 29 .1.1 2.29.1.2 2. 29 .1. 3 2. 29 .1.4 2.29.2 2.29.2.1 br0781-2066a123-20 Clean-Up Pump Stoppage Symptoms Automatic Action Immediate Action Subsequent Action Depleted Resin Bed or High Differential Pressure Across Resin Bed Symptoms ONP -x Rev 23 VOLUME 3: e OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS 2.29.2.2 2.29.2.3 2.29.2.4 Automatic Action Immediate Action Subsequent Action ONP 2.30* LOSS OF REACTOR COOLING WATER SYSTEM 2.30.1 2. 30 .1.1 2. 30 .1. 2 2. 30 .1. 3 2. 30 .1. 4 2.30.2 2.30.2.1 2.30.2.2 2.30.2.3 2.30.2.4 Total Loss of Reactor Cooling Water System Symptoms Automatic Actions Immediate Action Subsequent Action Loss of One Reactor Cooling Water Pump Symptoms Automatic Action Immediate Action Subsequent Action ONP 2.31 REACTOR SCRAMS 2. 31. 1 2. 31. 2 2.31.3 2.31.4 Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Action ONP. 2.32 LOW AND HIGH DRUM LEVELS 2.32.1 2. 32 .1.1 2. 32 .1. 2 2.32.2 2.32.2.1 2.32.2.2 2.32.3 2.32.3.1 2.32.3.2 2.32.4 2.32.4.1 2.32.4.2 Symptoms Low Drum Level High Drum Level Automatic Actions Low Drum Level High Drum Level Immediate Operator Actions Low Drum Level High Drum Level Subsequent Operator Actions Low Drum Level High Drum Level ONP 2.33 ABNORMAL RELEASE OF RADIOACTIVITY IN LIQUIDS 2.33.1 2.33.2 2.33.3 2.33.4 Symptoms Automatic Operations Immediate Operator Actions Subsequent Operator Actions ONP 2.34 LOSS OF SHUTDOWN COOLING SYSTEM 2.34.1 Symptoms 12/18/81 ONP -xi br0781-2066a123-20 Rev 23

..,. *,_, ... ) . -VOLUME 3: OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS 2.34.2 2.34.3 2.34.4 Automatic Actions Immediate Operator Actions Subsequent Operator Actions ONP 2.35 LOSS OF MOTOR GENERATOR SETS ONP 2.36 12/18/81 2.35.1 2. 35 .1.1 2. 35 .1. 2 2. 35 .1. 3 2. 35 .1. 4 2.35.2 2.35.2.1 2.35.2.2 2.35.2.3 2.35.2.4 LOSS OF 2.36.1 2.36.1.1 2.36.1.2 2.36.1.3 2. 36. 1. 4 2.36.2 2.36.2.1 2.36.2.2 2.36.2.3 2.36.2.4 2.36.3 2.36.3.1 2.36.3.2 2.36.3.3 2.36.3.4 2.36.4 2.36.4.1 2.36.4.2 2.36.4.3 2.36.4.4 2.36.5 2.36.5.1 2.36.5.2 2.36.5.3 2.36.5.4 br0781-2066al23-20 Loss of Generator Regulation Symptoms Automatic Actions Immediate Operator Action Subsequent Action Loss of Voltage to the Motor Set Prime Mover Symptoms Automatic Actions Immediate Operator Action Subsequent Actions STATION POWER Plant at Power Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Action Plant Is Shut Down Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions Generator Partial Loss of Station Power -Plant at Power -Loss of 480-V Motor Control Bus lA Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions Partial Loss of Station Power -Plant at Power -Loss of 480-V Motor Control Bus 2A Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions Partial Loss of Station Power -Plant at Power -Loss of 480-V Motor Control Bus 2B Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions ONP -xii Rev 23 VOLUME 3: OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS ONP 2.37 RDS SYSTEM 2.37.1 2.37.1.1 2.37.1.2 2.37.1.3 2.37.1.4 2.37.2 2.37.2.1 2.37.2.2 2.37.2.3 2.37.2.4 2.37.3 2.37.3.1 2.37.3.2 2.37.3.3 2.37.3.4 2.37.4 2.37.4.1 2.37.4.2 2.37.4.3 2.37.4.4 2.37.5 2.37.5.1 2.37.5.2 2.37.5.3 2.37.5.4 2.37.6 2.37.6.1 2.37.6.2 2.37.6.3 2.37.6.4 2.37.7 2.37.7.1 2.37.7.2 2.37.7.3 2.37.7.4 One (1) Isolation Valve (CV-4180, -4181, -4182 or -4183) Failed in "Closed" Position Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions Depressurizing Valve (SV-4984, -4985, -4986 or -4987) Leakage Downstream Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions Isolation Valve (CV-4180, -4181, -4182 or -4183) Leaking Internally Downstream Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Action Air Leak on Instrument Air Supply System to Isolation Valves CB-4180, -4181, -4182, -4183 and Bypass Isolation Valve CV-4184 Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions One (1) Depressurization Valve (SV-4984, -4985, -4986 or -4987) Failed in "Closed Position Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action Loss of One (1) Uninterruptible Power Supply Symptoms Automatic Action Immediate Operator Actions Subsequent Operator Actions Loss of RDS Containment Electrical Penetration Seal Pressure Symptoms Automatic Actions Immediate Operator Actions Subsequent Operator Actions ONP 2.38 LOSS OF FUEL POOL WATER LEVEL OR COOLING WATER 12/18/81 2.38.1 2.38.2 br0781-2066al23-20 Symptoms Automatic Actions GNP -xiii Rev 23

. . . . VOLUME 3: OPERATING PROCEDURES

-SYSTEM ONP -TABLE OF CONTENTS 12/18/81 2.38.3 2.38.4 br0781-2066al23-20 Immediate Operator Actions Subsequent Operator Actions ONP -xiv Rev 23 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 3.1.1.1 3.1.1.2 3.1.1.3 3.1.1.4 3 .1. 2 3.1.2.1 3.1.2.2 3.1.2.3 3.1.2.4 Sudden Loss of DC Power System Symptoms Automatic Action Immediate Operator Actions Subsequent Operator Action Gradual Loss of DC Power System Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Actions EMF 3.2 LOSS OF NEUTRON FLUX INDICATION 12/18/81 3.2.1 3.2.1.1 3.2.1.2 3.2.1.3 3.2.1.4 3.2.2 3.2.2.1 3.2.2.2 3.2.2.3 3.2.2.4 3.2.3 3.2.3.l 3.2.3.2 3.2.3.3 3.2.3.4 3.2.4 3.2.4.1 3.2.4.2 3.2.4.3 3.2.4.4 br0781-2105a123-20 Loss of Single Start-Up Channel During an Approach to Critical or During a Refueling Operation Symptoms Automatic Actions Immediate Operator Actions Subsequent Action Loss of Intermediate Range Monitor(s)

Prior to Reaching 4% Position on 2/3 Picoammeter Range Switches Symptoms Automatic Action Immediate Operator Actions Subsequent Action Loss of Power Range Monitors (Channels 1, 2 and 3) Symptoms Automatic Action Immediate Operator Actions Subsequent Action Loss of All Neutron Instrumentation or mation From All Instrumentation Is Unreliable Symptoms Automatic Action Immediate Operator Action Subsequent Action EMF -i Rev 23 VOLUME 3: EMF 3.3 OPERATING PRO.URES -EMERGENCY EMP -TABLE OF CONTENTS LOSS OF REACTOR COOLANT 3.3.1 Minor Loss of Reactor Coolant 1 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, 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 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 Inside Inside Outside 3.3.4 Loss of Coolant Accident in Conjunction With Loss of Off-Site Power EMF 3.4 FUEL HANDLING ACCIDENTS 3.4.1 3.4.2 3.4.3 3.4.4 EMF 3. SA ATWS 3.5A.1 3.SA.2 3.5A.3 3.SA.4 Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Actions Symptoms Automatic Actions Immediate Operator Action Subsequent Operator Action EMF 3.7 EARTHQUAKE EMP 3.8 12/18/81 3.7.1 3.7.2 3.7.3 3.7.4 TORNADO 3.8.1 3.8.2 3.8.3 br0781-2105a123-20 Symptoms Automatic Operations Immediate Operator Action Subsequent Operator Actions Symptoms Automatic Operations Immediate Operator Actions EMP -ii Rev 23 VOLUME 3: EMP 3.9 12/18/81 e OPERATING PROCEDURES

-EMERGENCY EMP -TABLE OF CONTENTS 3.8.4 FLOODING 3.9.1 3.9.2 3.9.3 3.9.4 Subsequent Operator Actions Symptoms Automatic Operations Immediate Operator Actions* Subsequent Operator Action EMP -iii br0781-2105al23-20 Rev 23 1' 9 A -IMPLEMENTING PROCEDURES BIG ROCK POINT NUCLEAR PLANT SITE EMERGENCY PLAN EPIP Number P. Q. R. s. T. u. v. w. TABLE OF CONTENTS (Contd) Title Senior Engineer Training Coordinator or Instructor Property Protection Supervisor Security Shift Leader Security Officer Technical Engineer Administrative Supervisor or Technician Plant Superintendent 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 04/02/82 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) ii Rev 18 pr1181-2187a103

. VOLUME 9A IMPLEMENTING PROCEDURES BIG ROCK POINT NUCLEAR PLANT SITE EMERGENCY PLAN TABLE OF CONTENTS (Contd) EPIP Number F. Title 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 nu0682-0010bl42 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)

NUCLEAR SEI\VICES DEPAR'l'!vfENT LESSON PLAN TITLE: PREVENTION/MI'rIGATION OF CORE DAMAGE INDEX I. OBJECTIVES II. REFERENCES III.

IV. PRESENTATION:

A. Intro B. Prevention C. Operation D. Safety Functions E. Inadequate Core Cooling 2. 3. 5. Defined Due to DNE Due to Loss of Heat Sink Recovery from Loss of Heat Sink Due to Loss of Coolant 6. Corrective Action for ICC from LOCA 7, Core Hec:citicality

8. Syr.iptoms Summarized F. PWR Events Leading to ICC 1. Events & Methods of Analysis 2. Events Causing Anproach to Dirn at Power 3. Approach to DNE.l from Core Anomaly 4, Accidents with Potential fm.* Core Uncovery a.. Instrument Response Capabilities

b. LOCA with Potentia.i for ICC c. Loss of* Heat Sink with Fotential for rec d. Zero Power Events with Potential for ICC PAGE 1 1 1 1 2 3 5 7 8 8 10 10 12 13 14 14 14 16 17 . 17-26 27-35 35-43 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.

OF PROCEDURES 63 VII.

Attachment A 63 SECTION INDEX OFF NORMAL PROCEDURES (ONP's) ONP 1 ONP 2 ONP 3 ONP 4 ONP 5 ONP 6 ONP 7 ONP 8 ONP 9 ONP 10 ONP 11 ONP 12 ONP 13 ONP 14 ONP 15 ONP 16 ONP 17 ONP 18 ONP 19 ONP 20 ONP 21 ONP 22 ONP 23 I ONP 24.1 ONP 24.2 I ONP 24. 3 IONP 24.4 loNP 24.5 Loss Of Load Partial Loss Of Primary Coolant Flow Loss Of Feedwater Containment Isolation Control Rod Drop Excessive Control Rod Withdrawal Control Rod Trip Failure Uncontrolled Primary Coolant System Boron Dilution Excessive Load Increase Excessive Feedwater Increase Fuel Cladding Failure Acts Of Nature Reactor Regulator Failure Loss Of Condenser Vacuum Loss of Flux Indication Inability To Drive Control Rod Doss Of Shutdown Cooling Pressurizer Pressure Control Malfunctions Expected Transients Diesel Generator Manual Control Natural Circulation Post Accident Hydrogen Handling Primary Coolant Leak Loss of Preferred AC Bus v 10 .I. Loss of Preferred AC Bus y 20 Loss of Preferred AC Bus y 30 Loss of Pref erred AC Bus y 40 Loss of Instrument AC Bus y 01 i -z 0 :::0 s: )> --t -0 z () 0 < Rev 1 P ALISAD.!!:t3 l-' LANT SECTION INDEX u'ERGEr!CY OPERATING PROCEDURES (EOP Is) EOP 1 EOP 2 EOP 3 EOP 4 EOP 5 EOP 6 EOP 7 EOP 8.1 EOP 8.2 EOP 9 EOP 10 EOP 11 EOP 12 Reactor Trip Loss of AC Power Loss of Service Water Loss of Component Cooling Loss of Instrument Air Main Steam Line Break/Main Feedwater Line Break. -Inside Containment Main Steam Line Break/Main Feedwater Line Break. -Outside Containment Loss of Coolant Accident Steam Generator Tube Rupture Fuel Handling Accident Control Room Evacuation Loss of Containment Integrity Abnormal Release of Radioactivity

,---*-i I I I z .,, 0 :::0 )> -j \ I \ l I I .l , l I Iv __ -<_ .... e-

\ti\\ i Rev 0

.. , SITE EMERGENCY PLAN PALISADES PLANT Rev 0 APPENDIX D D-1 EMERGENCY IMPLEMENTATION PROCEDURES EI-1 -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-2 -Palisades Plant Actions/Notifications During an Emergency This procedure lists mandatory and subsequent notifications and actions for each level of emergency.

EI-3 -Communications and Notification This procedure details the notification format and provides call lists of 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-5 -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-6 -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-7 -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 PALISADES PI.ANT Rev 0 EI-8 -On-Site Radiological Monitoring D-2 This prncedure provides guidelines for post-accident radiological monitoring on site. EI-9 -Off-Site Radiological Monitoring This procedure provides guidelines for past-accident radiological monitoring off site. EI-10 -Environmental Assessment This procedure provides guidelines for post-accident collection and ment of environmental TLDs, obtaining data from air monitoring stations, collection and of waterborne effluents, and obtaining.

water/milk/vegetation samples. EI-11 -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-13 -Evacuation, Reassembly This procedure provides site evacuation procedures and the subsequent reassembly of personnel.

EI-14 -Radiological Medical Care This procedure provides guidelines on personnel emergency radiation limits, personnel decontamination procedures, the use of thyroid blocking agents and the methods of transporting contaminated/injured victims to hospitals.

EI-15 -Training and Drills This procedure establishes training requirements for plant personnel and details the requirements for drills and exercises.

mi038 l-0005.h-89