ML020810209
| ML020810209 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/05/2002 |
| From: | Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML020810209 (134) | |
Text
Arkansas Nuclear One - Administrative Services Document Control Tuesday, March 05, 2002 Document Update Notification COPYHOLDER NO: 103 TO: NRC - WASHINGTON ADDRESS: OS-DOC CNTRL DESK MAIL STOP OPI 17 WASHINGTON DC 20555-DC DOCUMENTNO: OP-1903.010 TITLE: EMERGENCY ACTION LEVEL CLASSIFICATION REVISION NO. 036-04-0 CHANGE NO: PC-04 SUBJECT. PERMANENT CHANGE (PC) is checked, please sign, date, andreturn within 5 days.
D ANO-1 Docket 50-313 SO ANO-2 Docket 50-368 Signature Date SIGNATURE CONFIRMS UPDATE HAS BEEN MADE RETURN TO: . J ATTN: DOCUMENT CONTROL ý\ 0 ARKANSAS NUCLEAR ONE 1448 SR 333 RUSSELLVILLE, AR 72801
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: EMERGENCY ACTION LEVEL DOCUMENT NO. CHANGE NO.
CLASSIFICATION 1903.010 036-04-0 WORK PLAN EXP. DATE TC EXP. DATE N/A N/A SET # \ O "* SAFETY-RELATED IPTE O-)YES E-NO []YES ONO TEMP ALT OIYES ONO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/interruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME I 00i0 m o FORM TITLE: FORM NO. CHANGE NO.
VERIFICATION COVER SHEET 1000.006A 050-00-0
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE Page 1 TITLE:EMERGENCY ACTION LEVEL CLASSIFICATION DOCUMENT NO. CHANGE NO.
1 1903.010 036-04-0 AFFECTED UNIT: 0PROCEDURE ElELECTRONIC DOCUMENT SAFETY-RELATED 0 UNIT 1 0 UNIT 2 [] WORK PLAN, EXP. DATE0 YES ENO TYPE OF CHANGE:
El NEW 0 PC ETC El DELETION
[] REVISION El EZ EXP. DATE:
DOES THIS DOCUMENT:
- 1. Supersede or replace another procedure? E- YES [NO (IfYES, complete 1000.0068 for deleted procedure.) (OCAN058107)
- 2. Alter or delete an existing regulatory commitment? El YES [NO (IfYES, coordinate with Licensing before implementing.) (0CNA128509)(0CAN049803)
- 3. Require a 50.59 review per LI-101? (See also 1000.006, Attachment 15) 0 YES El NO (if 50.59 evaluation, OSRC review required.)
- 4. Cause the MTCLto be untrue? (See Step 8.5 for details.) EYES [NO (If YES, complete 1000.009A) (1CAN108904, OCAN099001, 0CNA128509, OCAN049803)
- 5. Create an Intent Change? EYES [NO (If YES, Standard Approval Process required.)
- 6. Implement or change IPTE requirements? E3 YES [NO (IfYES, complete 1000.143A. OSRC review required.)
- 7. Implement or change a Temporary Alteration? E3 YES 0 NO (If YES, then OSRC review required.)
Was the Master Electronic File used as the source document? ED YES ENO INTERIM APPROVAL PROCESS STANDARD APPROVAL PROCESS ORIGINATOR SIGNATURE: (Includes review of Att. 13) DATE: ORIGINATOR SIGNATURE: (Includes review of Aft. 13) DATE: //*-.-/o z Print and Sign name: PHONE #: Print and Sign name: .,f r ._--"- PHONE #: , 5ý SUPERVISOR APPROVAL: DATE: INDSLP"NDENT REVIEWER: DATE:
SRO UNIT ONE :** DATE: ENGINEERINý I DbATE.
SRO UNIT TWO:** DATE: QUALITY: Ai/A DATE:
Interim approval allowed for non-intent changes requiring no UNIT SURVEILLANCE COORDINATOR (0CNA049803): DATE:
50.59 evaluation that are stopping work in progress. __,/_
Standard Approval required for intent changes or changes SECT LDER: DATE:
requiring a 50.59 evaluation. Z-,/& -o Z.
- ifchange not required to support work in progress, QUfALI1Y ASSURANCE: DATE:
Department Head must sign. _____________________________
- If both units are affected by change, both SRO signatures OTHER SECTION LEADERS: DATE:
are required. (SRO signature required for safety related & S2So procedures only.) OT DATE:
0314ER SECTION LEAD9,y DATE:
OTHER SECTION LEADERS: DATE:
OSR!Z IRMANFECHNICAL REVIEWER: (0CNA049312) DATE: OTHER SECTION LEADERS: DATE:
FINArAPPROVAL: Date: OTHER SECTION LEADERS: DATE:
REQUIRED EFFECTIVE DATE: OTHER SECTION LEADERS: DATE:
FORM TITLE: FORM NO. CHANGE NO.
PROCEDURE/WORK PLAN APPROVAL REQUEST 1000.006B 051-00-0
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE:Emergency Action Level Classification DOCUMENT NO. CHANGE NO.
1903.010 036-04-0
- PROCEDURE -WORK PLAN, EXP. DATE PAGE 1 OF I El ELECTRONIC DOCUMENT TYPE OF CHANGE
[] NEW 0 PC El TC El DELETION 5- REVISION 0l EZ EXP. DATE:
AFFECTED SECTION: DESCRIPTION OF CHANGE: (For each change made, include sufficient detail to describe (Include step # if reason for the change.)
applicable)
Table of Contents Added Improved Technical Specifications (ITS) note. Also renumbered the pages due to added Page 1 Of 129) definitions.
Section 3 Added step 3.3.8, to reference added definitions.
step 3.3.8 Section 4 Added definition 4.1 and a definition under step 4.10. Also rearranged all definitions to put in Step 4.1 alphabetical order. /4 Changed references on EAL 1.7 of Attachment 3, and EAL 1.6 & 1.7 of Attachment 4 due to step 1.6 & 1.7 rearranging the definitions. Added ITS to step 1 of Criteria section, also a bold ITS to the right of the Criteria Section to EAL 2.1, Criteria identify the ITS Section (page 25 of 129) Stated the NUE Criterion and added a second criterion. The second criterion is an EAL 7.1, Criteria enhancement after 09/11/01, and is based on a NRC draft change to NUREG-0654.
Section (page 56 of 129) Stated the NUE Criterion and added a second criterion. The second criterion is an EAL 7.1, Criteria enhancement after 09/11/01, and is based on a NRC draft change to NUREG-0654.
Section (page 109 of 129) Added note to clarify the differences in the failed fuel graphs in 1903.010 and 1903.011.
(page 126 of 129) Added note to clarify the differences in the failed fuel graphs in 1903.010 and 1903.011.
(page 127 of 129)
FORM TITLE: FORM NO. - CHANGE NO.
DESCRIPTION OF CHANGEI 1000.006C 050-00-0
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 1 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 NOTE This procedure contains Improved Technical Specifications (ITS) content in the following format:
[ITS Example Content ITS]
This content is not valid until after the implementation of Improved Technical Specifications.
TABLE OF CONTENTS SECTIO2NS PAGE NO.
1.0 Purpose ....................................... . - . . . . . . . . . . . . . . . . . . . 2 2.0 S co p e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S.. . . . . . . . . . . . . . . . . . . . . . 2 3.0 References ................................... S.. . . . . . . . . . . . . . . . . . . . ". . 2 4.0 Definitions ..................................
5.0 Responsibility and Authority ................. S.. . . . . . . . . . . . . . . . . . . . . . 9 6.0 Instructions .. ...............................
7.0 Attachments and Forms ........................ S.. . . . . . . . . . . . . . . . . . . . . . 12 7.1 Attachment 1 - Unit 1 Index of EALs S.. . . . . . . . . .I . . . . . . . . . . . . 13 7.2 Attachment 2 - Unit 2 Index of EALs S.. . . . . . . . . . . . . . . . . . . . . . 16 7.3 Attachment 3 - Unit 1 Emergency Actio)n Levels .............. 19 7.4 Attachment 4 - Unit 2 Emergencv Actio*n Levels . . . . . . . . .. . . . 74 7.5 Attachment 5 Unit 1 Containment Radiation EAL Plot ....... 127 7.6 Attachment 6 Unit 2 Containment Radiation EAL Plot ....... 128 7.7 Attachment 7 Unit 1 Fuel Cladding Failure Radiation Plot .129 7.8 Attachment 8 Unit 2 Fuel Cladding Failure Radiation Plot .130
"1.0 PURPOSE of plant for detection and classification This procedure establishes criteria Classes.
events into the four standard Emergency 2.0 SCOPE Units I and 2 in all modes; it does not This procedure is applicable to or systems operations requirements, procedures include specific plant casualty only.
processes but rather provides administrative
3.0 REFERENCES
3.1 REFERENCES
USED IN PROCEDURE PREPARATION:
3.1.1 ANO Emergency Plan 3.1.2 ANO's EAL Bases Document NUREG-0654/FEMA-REP-l, Rev. 1 3.1.3 3.1.4 10 CFR 50 to Appendix 1 3.1.5 NRC Branch Position on Acceptable Deviations to NUREG-0654/FEMA-REP-I, July 11, 1994 THIS PROCEDURE:
3.2 REFERENCES
USED IN CONJUNCTION WITH Actions" 3.2.1 1000.104, "Condition Reporting and Corrective 3.2.2 1903.011, "Emergency Response/Notifications" Room" 3.2.3 1903.064, "Emergency Response Facility - Control "Emergency Response Facility - Technical Support 3.2.4 1903.065, Center (TSC)"
- operational 3.2.5 1903.066, "Emergency Response Facility Support Center (OSC)"
1903.067, "Emergency Response Facility - Emergency 3.2.6 Operations Facility (EOF)"
3.2.7 1203.025, "Natural Emergencies" 3.2.8 2203.008, "Natural Emergencies" 3.2.9 1202.XXX, "Emergency Operating Procedures" 2202.XXX, "Emergency Operating Procedures" 3.2.10 and 3.2.11 1404.016, "Post Earthquake Data acquisition Measurement" Method" 3.2.12 1904.002, "Offsite Dose Projections-RDACS
PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 3 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 3.2.13 NRC Position Paper on "Timeliness of Classification of Emergency Conditions" dated August 17, 1995 3.2.14 1607.001, "Reactor Coolant System Sampling" 3.2.15 2607.001, "Unit 2 Reactor Coolant System Sampling" 3.3 RELATED ANO PROCEDURES:
3.3.1 1043.042, "Response to Security Contingencies" 3.3.2 1502.004, Attachment H 3.3.3 1903.023, "Personnel Emergency" 3.3.4 ANO Security Plan/Security Procedures 3.3.5 1015.007, "Fire Brigade Organization and Responsibilities" 3.3.6 1903.042, "Duties of the Emergency Medical Team" 3.3 .7 1903.043, "Duties of the Emergency Radiation Team" 3.3.8 1302.022, "Core Damage Assessment" 3.4 REGULATORY CORRESPONDENCE CONTAINING NRC COMMITMENTS WHICH ARE IMPLEMENTED IN THIS PROCEDURE ARE DENOTED IN LEFT HAND MARGIN:
3.4.1 0CAN068320 (P-10766) - Section 4.3 3.4.2 OCNA08005 (P-16725) Allow for 1% fuel cladding failure to be determined by radiation dose readings. Step 4.16.1.A.2 and 4.16.1.B.2, Unit 1 EALs 1.2 and 1.3, Unit 2 EALs 1.2 and 1.3, Attachments 7 and 8.
4.0 DEFINITIONS 4.1 Core Damage - A failure of fuel cladding integrity to the extent that any of the following happen:
4.1.1 Fission product activity in the coolant exceeds the limits in the technical specifications.
4.1.2 Fuel is no longer in the original geometry.
4.1.3 A major portion of the core cannot be operated for its design cycle length.
4.2 Courtesy Call - A notification to the Arkansas Department of Health and follow-up notification to the NRC for conditions/events other than those constituting an Emergency Class as listed in procedure 1903.11, "Emergency Response/Notifications", Section 6.3.
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 4 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 4.3 Emergency Action Level - Alarms, instrument readings or visual sightings that have exceeded pre-determined limits which would categorize the situation into an initiating condition of one of the following four Emergency Classes:
Notification of Unusual Event Alert Site Area Emergency General Emergency 4.3.1 Notification of Unusual Event - Unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
4.3.2 Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
4.3.3 Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.
4.3.4 General Emergency Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off site for more than the immediate site area.
(OCAN068320} 4.4 Emergency Direction and Control - Overall direction of facility response which must include the non-delegable responsibilities for the decision to notify and to recommend protective actions to Arkansas Department of Health personnel and other authorities responsible for offsite emergency measures. With activation of the BOF, the EOF Director typically assumes the responsibility for Emergency Direction and Control. The management of on-site facility activities to mitigate accident consequences remains with the TSC Director in the Technical Support Center. The Shift Manager retains responsibility for the Control Room and plant systems operation.
4.5 Emergency Operations Facility (EOF) - A nearsite emergency response facility located approximately 0.65 miles northeast of the reactor buildings (the ANO Training Center).
4.6 Emergency Planning Zone (EPZ) - The EPZ considered by this procedure is the inhalation zone and is that area within approximately a 10 mile radius of ANO.
PROC.IWORK PLAN NO. PROCEDUREMWORK PLAN TITLE: PAGE: 5 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 4.7 Emergency Response Organization (ERO) - The organization which is composed of the Initial Response Staff (IRS), the EOF staff, the TSC staff, the OSC staff, and the Emergency Team members. It has the capability to provide manpower and other resources necessary for immediate and long-term response to an emergency situation.
4.8 EPA Protective Action Guideline (PAG) Exposure Levels - The projected dose to reference man, or other defined individual, from an unplanned release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended (i.e., 1 Rem TEDE or S Rem Child Thyroid (CDE)).
4.9 Exclusion Area: That area surrounding ANO within a minimum radius of 0.65 miles of the reactor buildings, but outside the protected area and controlled to the extent necessary by ANO during periods of emergency.
4.10 FISSION PRODUCT BARRIER FAILURE 4.10.1 Fuel Cladding Failure - Condition where the fuel rod cladding becomes defective and cannot contain the fission gases that have accumulated between the fuel pellet and the fuel rod cladding (commonly referred to as the gap).
A. Unit I Greater than 1% fuel cladding failure as indicated by ANY of the following:
Nuclear Chemistry analysis of RCS sample yields >
400 uCi/gm specific 1-131.
{OCNA08005) 2. Radiation levels that indicate >1% fuel cladding failure per Unit 1 Fuel Cladding Failure Radiation Plot (Att 7).
- 4. Containment Radiation Levels correspond to a Site Area Emergency from Containment Radiation EAL Plot (Attachment 5).
- 5. Engineering assessment of core damage indicates
>1% fuel cladding failure.
B. Unit 2 - Greater than 1% fuel cladding failure as indicated by ANY of the following:
- 1. Nuclear Chemistry analysis of RCS sample yields >
378 uCi/gm specific 1-131.
{OCNA08005} 2. Radiation levels that indicate >1% fuel cladding failure per Unit 2 Fuel Cladding Failure Radiation Plot (Att 8).]
- 3. Containment Radiation Levels correspond to a Site Area Emergency from Containment Radiation EAL Plot (Attachment 6).
PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 6 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 (4.10.1 cont.) 4. Engineering assessment of core damage indicates
> 1% fuel cladding failure.
4.10.2 RCS Boundary Failure A. Unit I - RCS leakage greater than normal makeup capacity (50 gpm).
B. Unit 2 - RCS leakage greater than 44 gpm (capacity of a single Charging Pump).
4.10.3 Containment Integrity Failure A. Abnormally high Containment High Range Radiation Monitor readings (RE-8060 or 8061 for Unit 1; 2RY 8925-1 or 2RY-8925-2 for Unit 2) and indications of radiological effluents outside of the Reactor Building that are not attributable to any other source.
B. In the judgement of the SM/TSC Director/EOF Director, a breach of the Reactor Building exists. The variety of possible Reactor Building integrity failure scenarios precludes the development of an all inclusive list. In the absence of the conditions described in 4.10.3.A above, the SM/TSC Director/EOF Director must judge the potential for an offsite release to occur based on a current status of Reactor Building isolation systems and structural integrity.
4.10.4 Inability to Monitor a Fission Product Barrier A. Following the failure of two fission product barriers, the inability to monitor the third barrier is to be regarded as equivalent to a failure of that barrier.
4.11 FISSION PRODUCT BARRIER CHALLENGE 4.11.1 Challenge to Fuel Cladding: any event or condition which in the judgement of the SM/TSC Director/EOF Director presents the potential for greater than 1% fuel cladding failure; for example:
A. RCS temperature and pressure indicates superheated conditions.
B. Indications of the core being uncovered.
C. Exceeding safety limits (e.g. DNBR or Local Power Distribution) 4.11.2 Challenge to RCS Boundary: any event or condition which, in the judgement of the SM/TSC Director/EOF Director could result in RCS leakage in excess of normal makeup capacity (i.e., 50 gpm for Unit 1 or 44 gpm for Unit 2); for example:
A. RCS pressure > 2450 psig and not decreasing.
B. Two out of three seal stages failed on any RCP (U-1).
on any RCP (U-2).
(4.11.2 cont.) C. Three out of four seal stages failed in RCS leakage D. Failure of any component resulting than Tech. Spec. limits and approaching normal greater 1 or (44 gpm) for make up capacity; (50 gpm) for Unit Unit 2.
Integrity: any event or 4.11.3 Challenge to Containment Building the SM/TSC Director/
condition which in the judgement of increases the potential for EOF Director significantly for example:
failure of containment integrity; spray A. Containment pressure > Reactor Building and increasing with no available RB actuation setpoint spray or cooling.
in containment > 3.5%.
B. Hydrogen concentrations which C. Occurrence of system or component failure the capability to maintain containment degrades integrity as defined by Technical Specifications.
products trapped within the 4.12 FUEL OVERHEAT - Condition in which fission are released at an accelerated rate due to increasing fuel pellet typically range from 1600 OF temperature. Fuel overheating tempertures to 3600 OF cladding temperature.
organization composed of 4.13 Initial Response Staff (IRS) - The emergency be able to respond to the site in plant personnel which must Table B-i of the Emergency Plan.
accordance with MU capacity is defined as the 4.14 Normal Makeup (MU) Capacity - Normal the RCS through the MU line with maximum expected water addition to the letdown line isolated. This amount will vary with RC pressure.
4.15 Offsite - Those areas not covered by Section 4.13.
4.16 Onsite - The area within the Exclusion Area Boundary.
response center within 4.17 Operational Support Center (OSC) - Emergency where support is coordinated for the the ANO Maintenance Facility following functions:
Onsite Radiological Monitoring Maintenance Nuclear Chemistry Emergency Medical Support Fire Fighting Support for repair and damage control The OSC also serves as the briefing area Facility.
teams and is located in the Maintenance
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 8 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 4.18 PLANT TRANSIENT 4.18.1 Any unplanned reactor trip from criticality.
4.18.2 A planned reactor trip in which the expected post-trip response did not occur.
4.18.3 Any event resulting in an automatic ESAS (Unit 1) or ESF (Unit 2) actuation or any event requiring manual initiation of these systems where automatic initiation would likely have occurred.
4.18.4 Any turbine-generator power change in excess of 100 MWe in less than one (1) minute other than a momentary spike due to a grid disturbance or a manually initiated runback.
4.18.5 Any unplanned main turbine or main feedwater pump turbine trip which results in a significant plant transient (change in excess of 100 MWe).
4.19 Protected Area: The area encompassed by physical barriers (i.e., the security fence) and to which access is controlled.
4.20 Technical Support Center (TSC) - The location within the ANO Administration Building equipped with instrumentation and communication systems and facilities useful in monitoring the course of an accident; this center is located in the 3rd Floor of the ANO Administration Building.
5.0 RESPONSIBILITY AND AUTHORITY 5.1 The responsibility for event classification is assigned to the individual with responsibility for Emergency Direction and Control (i.e., The Shift Manager, TSC Director, or EOF Director).
5.2 The Control Room Supervisor (CRS) will assume Emergency Direction and Control responsibilities whenever the SM is not available to assume this responsibility (e.g. the SM becomes incapacitated and a replacement has not yet arrived).
5.3 Any individual who observes an initiating condition which warrants an emergency class declaration, as described in Attachments 3 and 4, shall immediately notify the person with current responsibility for Emergency Direction and Control (i.e. SM/TSC Director/EOF Director).
PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 9 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 6.0 INSTRUCTIONS NOTE On emergencies that effect both units such as earthquakes, tornado's, etc.,
the unit with the highest Emergency Action Level Classification should be the one that is declaring the emergency.
6.1 CLASSIFYING EMERGENCIES:
NOTE NRC guidelines recommend that once indications are available to ANO staff that an EAL has been exceeded, a 15 minute goal is a reasonable period of time for assessing and classifying an emergency.
6.1.1 When indications of abnormal occurrences are received by the Control Room staff, the SM/TSC Director/EOF Director shall:
A. Verify the indications of the off-normal event or reported sighting.
B. Ensure that the immediate actions (e.g., use of Emergency and Abnormal Operating Procedures) are taken for the safe and proper operation of the plant.
C. Compare the abnormal conditions with those listed in the "Index Of Emergency Action Levels" (Blue Tabs - Unit 1; Green Tabs - Unit 2).
D. Turn to the appropriate tab which corresponds to the condition picked from the Index Of EALs.
NOTE Unit I EALs - Blue Tabs Unit 2 EALs - Green Tabs E. Assess the information available from valid indications or reports, then:
- 1. Compare information to criteria given for EBA,
- 2. Review any Related EALs to determine if the abnormal conditions meet those criteria, and
- 3. Declare the emergency classification that is indicated. If it appears that different classifications could be made for the current plant conditions, the highest classification indicated should be the one that is declared.
PROCJWORK PLAN NO. PROCEDUREiWORK PLAN TITLE: PAGE: 10 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 NOTE The emergency action levels described in this procedure are not intended to be used during maintenance and/or testing situations where abnormal temperature, pressure, equipment status, etc-, is expected. In addition, each EAL contains information on the mode(s) of operation during which it is applicable.
F. If the indications or reports do not match the given EALs, then refer to the Miscellaneous Tab and using appropriate judgement, determine if the plant status warrants an emergency declaration.
6.1.2 Due to the speed in which events sometimes progress and the duty of the plant operators to take immediate corrective actions, an event may occur which was classifiable as an emergency, however, prior to offsite notifications the corrective actions taken may have removed the conditions that would have resulted in an emergency declaration. In this situation, it is not necessary to make an actual declaration of the emergency class, but an ENS notification to the NRC within one hour of the discovery of the undeclared event will provide an acceptable alternative. A courtesy call shall be made to ADH. Subsequent activation of response organization should be based upon the current plant conditions.
6.1.3 If no emergency declaration is required, then refer to procedure 1903.011, "Emergency Response/Notifications",
Section 6.3 to determine if the event warrants a "For Information Only" notification to Entergy Management, NRC Resident Inspector and/or the Arkansas Department of Health.
6.1.4 Upon declaration of an emergency classification implement procedure, 1903.011, "Emergency Response Notifications", to ensure that immediate notification requirements are met and the proper Emergency Plan response is taken.
6.1.5 Upgrade the emergency classification if plant conditions degrade per steps 6.1.1.A through F.
6.1.6 Downgrade the emergency classification when plant conditions have improved and step 6.2 is applicable.
6.2 DOWNGRADING THE EMERGENCY CLASSIFICATION:
6.2.1 Assess the current plant conditions, then perform the following:
A. Compare the abnormal conditions with those listed in the "Index Of Emergency Action Levels" (Blue Tabs - Unit 1; Green Tabs - Unit 2).
B. Turn to the appropriate tab which corresponds to the condition picked from the Index Of EALs.
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 11 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 C. Assess the information available from valid indications or reports, compare it to the given EALs.
Obtain concurrence from NRC and State officials that downgrading is appropriate (if their emergency response organizations have been activated as a result of this event). Downgrade to the emergency classification that is indicated.
D. If the indications or reports do not match the given EALs, then refer to the Miscellaneous Tab and using appropriate judgement, determine if the plant status warrants downgrading the emergency classification.
6.2.2 Perform notifications to downgrade the emergency classification if appropriate per procedure 1903.011, "Emergency Response/Notifications".
6.2.3 If no emergency classification appears necessary, then terminate the emergency per step 6.3.
6.2.4 If the emergency classification is still required, repeat steps 6.2.1 through 6.2.3 whenever plant conditions again appear to have improved.
6.3 TERMINATING THE EMERGENCY:
6.3.1 Compare the existing plant conditions with the following:
A. Plant conditions no longer meet the emergency action level criteria AND it appears unlikely that current conditions will degrade further requiring reinstitution of an emergency classification.
B. Non-routine releases of radioactive material to the environment are under control or terminated.
C. Any fire, flood, earthquake', or similar emergency condition is controlled or has ceased.
D. All specified corrective actions have occurred OR the plant has been placed in the appropriate operational mode.
E. All required notifications have been completed.
F. NRC and State officials are in agreement that termination or transition to the recovery phase is appropriate (if their emergency response organizations have been activated as a result of this event).
6.3.2 If the conditions of 6.3.1 A-F are met, terminate the emergency or proceed to the recovery phase.
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 12 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 7.0 ATTACHMENTS AND FORMS 7.1 Attachment 1 - Unit 1 Index of EALs 7.2 Attachment 2 - Unit 2 Index of EALs 7.3 Attachment 3 - Unit 1 Emergency Action Levels 7.4 Attachment 4 - Unit 2 Emergency Action Levels 7.5 Attachment 5 - Unit 1 Containment Radiation EAL Plot 7.6 Attachment 6 - Unit 2 Containment Radiation EAL Plot 7.7 Attachment 7 - Unit 1 Fuel Cladding Failure Radiation Plot 7.8 Attachment 8 - Unit 2 Fuel Cladding Failure Radiation Plot
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 13 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 1 UNIT 1 INDEX OF EALS NOTE Once available plant parameters reach an Emergency Action Level (EAL),
classifications should be made within 15 minutes.
1.0 PRIMARY SYSTEM EVENTS 1.1 RCS Activity Indicates >0.1% Fuel Cladding Failure ... .. ..... NUE 1.2 RCS Activity Indicates > 1% Fuel Cladding Failure .... ...... ALERT 1.3 Core Damage Indicated with an Inadequate Core Cooling Condition ........ ..................................... ...... SAE 1.4 Containment Radiation Reading which Indicates LOCA and >1%
Fuel Cladding Failure ................................. .. ..... SAE 1.5 Containment Radiation Reading which Indicates LOCA and
>50% Fuel Overheat ..... ............................... ...... GE 1.6 Core Melt ..... ...................................... ...... GE 1.7 Loss of or challenge to all 3 Fission Product Barriers ...... GE 2.0 RCS LEAKAGE RCS Leakage > T.S. Limits requiring a plant S/D or C/D ..... NUE 2.2 RCS Leakage > Normal Makeup Capacity (50 gpm) .............. ALERT 2.3 RCS Leakage > Normal Makeup Capacity (50 gpm) with >1.0%
Fuel Cladding Failure Conditions ........................... SAE 2.4 RCS Leakage > HPI Capacity ................................. SAE 3.0 SECONDARY SYSTEM EVENTS 3.1 Uncontrolled OTSG Depressurization Resulting in MSLI Actuation .................................................. NUE 3.2 OTSG Tube Leak > Tech Spec limits .......................... NUE 3.3 OTSG Tube Leak >10gpm Concurrent with an On-going Steam Releaseor loss of offsite power ........................... ALERT 3.4 OTSG Tube Rupture with Primary to Secondary Leakage >
Normal Makeup Capacity (50 gpm) with ongoing steam release or loss-of offsite power ................................... SAE 3.5 OTSG Tube Leak >1 gpm with >1% Fuel Cladding Failure and on-going Steam Release ..................................... SAE 4.0 ELECTRICAL POWER FAILURES 4.1 Degraded Power ............................................. NUE 4.2 Station Blackout ........................................... ALERT 4.3 Blackout for more than 15 minutes .......................... SAE 4.4 Loss of All Vital DC Power ................................. ALERT 4.5 Loss of All Vital DC Power for more than 15 minutes ........ SAE
ATTACHMENT 1 UNIT 1 INDEX OF EALS NOTE Level (EAL),
IOnce available plant parameters reach an Emergency Action within 15 minutes.
classifications should be made 5.0 RADIOLOGICAL EFFLUENTS or .15 mRem/hr 5.1 Radiological Effluents >.05 mRem/hr TEDE Radiological Site Boundary or Liquid Child Thyroid CDE at NUE exceed ODCM Limitations ..........................
Effluents or 1.5 mRem/hr 5.2 Radiological Effluents >.5 mRem/hr TEDE Thyroid CDE at Site Boundary or Liquid Radiological Child ALERT Effluents exceed 10 times ODCM Limitations Effluents >50 mRem/hr TEDE or 150 mRem/hr Radiological SAE Child Thyroid CDE at the Site Boundary Effluents >250 mRem/hr TEDE or 500 mRem/hr 5.4 Radiological GE Boundary ......................
Child Thyroid CDE at the Site ALERT 5.5 Levels .............................
High Radiation/Airborne SAE 5.6 Spent Fuel Accident ........................................
6.0 SAFETY SYSTEM FUNCTION when required to 6.1 Deviation from T.S. action statements deviations pursuant to shutdown or cooldown or ............... NUE 10CFR50.54(x) .. ... ............................
Automatic Trip ................... ALERT 6.2 RPS Failure to Complete an SAE 6.3 RPS Failure to Complete a Manual Trip NUE 6.4 Loss of Dose Assessment Capabilities NUE 6.5 Loss of Communications ..................................... ALERT 6.6 Loss of Control Room Annunciators ..........................
Transient in 6.7 Loss of Control Room Annunciators with SAE Progresss . .................................................. ALERT 6.8 Control Room Evacuation ....................................
of shutdown systems 6.9 Control Room Evacuation and control SA not established in 15 minutes ..............................
ALERT 6.10 Loss of Decay Heat Removal Systems ......................... SAE 6.11 Degraded Hot Shutdown Capability ...........................
PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 15 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT .
UNIT 1 INDEX OF EALS NOTE Once available plant parameters reach an Emergency Action Level (EAL),
classifications should be made within 15 minutes.
7.0 HAZARDS TO STATION OPERATION 7.1 Security Threat or Attempted Entry or Attempted Sabotage . . .NUE 7.2 Ongoing Security Threat within Protected Area Security Fence . ...................................................... ALERT 7.3 Ongoing Security Threat Within Plant Building ............... SAE 7.4 Ongoing Security Threat Within CR or Vital Area ............ GE 7.5 Fire or Explosion Onsite ................................... NUE 7.6 Fire or Explosion Onsite Affecting One Train of ANY ES Systems .................................................... ALERT 7.7 Fire or Explosion Onsite Affecting Both Trains of ANY ES Sy stem s .... ................................................ SAE 7.8 Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flammable Gas Release ....... ............................................. NUE 7.9 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ANY ES Systems ................................ ALERT 7.10 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ANY ES Systems .............................. SAE 8.0 NATURAL EVENTS 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake ... NUE 8.2 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake ................................................. ALERT 8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake ................................................. SAE 9.0 MISCELLANEOUS EVENTS 9.1 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local Authorities ................................................ NUE 9.2 Plant Conditions Exist that Warrant Activation of the TSC .. ALERT 9.3 Plant Conditions Exist that Warrant Activation of the Emergency Response Facilities .............................. SAE 9.4 Plant Conditions Exist That Make Release of Large Amount of Radioactivity Possible .................................. GE
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 16 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 2 UNIT 2 INDEX OF EALS NOTE Once available plant parameters reach an Emergency Action Level (EAL),
classifications should be made within 15 minutes.
!.0 PRIMARY SYSTEM EVENTS 1.1 RCS Activity Indicates >0.1% Fuel Cladding Failure .......... NUE 1.2 RCS Activity Indicates >1.0% Fuel Cladding Failure .......... ALERT 1.3 Core Damage Indicated with an Inadequate Core Cooling Condition .................................................. SAE 1.4 Containment Radiation Indicates LOCA and >1% Fuel Cladding Failure . ................................................... SAE 1.5 Containment Radiation Indicates LOCA and >50% Fuel Ov erheat . .................................................. GE 1.6 Core Melt with Containment Integrity Lost or Challenged .... GE 1.7 Loss of or challenge to all 3 Fission Product Barriers ..... GE 2.0 RCS LEAKAGE 2.1 RCS Leakage > Tech Spec Limits requiring a Plant S/D or C/ D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... NUE 2.2 RCS Leakage > 44 gpm ................................... .... ALERT 2.3 RCS Leakage > 44 gpm with ICC Conditions ............... .... SAE 3.0 SECONDARY SYSTEM EVENTS 3.1 Uncontrolled S/G Depressurization Resulting in MSIS Actuation .......... ........................................ NUE 3.2 S/G Tube Leak > Tech. Spec. Limits ......................... NUE 3.3 S/G Tube Leak >10gpm with an Ongoing Steam Release ......... ALERT 3.4 S/G Tube Rupture >44 gpm With an Ongoing Steam Release and RCS Activity > 1.0 pCi/gm, but < 378 pci/gm (1% fuel cladding failure) .......................................... SAE 4.0 ELECTRICAL POWER FAILURES 4.1 Degraded Power ..................................... *NUE 4.2 Station Blackout ................................... .ALERT 4.3 Loss of All Vital DC ............................... ALERT 4.4 Blackout > 15 minutes .............................. *SAE 4.5 Loss of All Vital DC for > 15 minutes .............. SAE
PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 17 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 2 UNIT 2 INDEX OF EALS NOTE Once available plant parameters reach an Emergency Action Level (EAL) classifications should be made within 15 minutes.
5.0 RADIOLOGICAL EFFLUENTS 5.1 Radiological Effluents >.05 mrem/hr TEDE or .15 Child Thyroid CDE at Site Boundary or Liquid Radiological Effluents exceed ODCM Limitations .......................... NUE S.2 Radiological Effluents >.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE at Site Boundary or Liquid Radiological Effluents exceed 10 times ODCM Limitations ................. ALERT 5.3 Radiological Effluents >50 mrem/hr TEDE or 150 mrem/hr Child Thyroid CDE at the Site Boundary ...................... SAE 5.4 Radiological Effluents >250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE at the Site Boundary ..................... GE 5.5 High Radiation/Airborne Levels ............................. ALERT 5.6 Spent Fuel Accident ........................................ SAE 6.0 SAFETY SYSTEM FUNCTION 6.1 Deviation from T.S. action statements when required to shutdown or cooldown or deviations pursuant to 10CFR50 .54 (X ) . ............................................. NUE 6.2 RPS Failure to Complete an Automatic Trip .................. ALERT 6.3 RPS Failure to Complete a Manual Trip ...................... SAE 6.4 Loss of Dose Assessment Capabilities ....................... NUE 6.5 Loss of Communications ..................................... NUE 6.6 Control Room Evacuation .................................... ALERT 6.7 Control Room Evacuation and control of shutdown systems not established in 15 minutes .............................. SAE 6.8 Loss of Decay Heat Removal Systems ......................... ALERT 6.9 Loss of Both S/Gs as a Heat Removal Method ................. SAE 6.10 Loss of Control Room Annunciators .......................... ALERT 6.11 Loss of Control Room Annunciators with a Transient in Prog ress .................................................. . SAE
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 18 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 2 UNIT 2 INDEX OF EALS NOTE lOnce available plant parameters reach an Emergency Action Level (EAL),
1classifications should be made within 15 minutes.
7.0 HAZARDS TO STATION OPERATION 7.1 Security Threat or Attempted Entry or Attempted Sabotage ... NUE 7.2 Ongoing Security Threat Within Protected Area Security Fen ce ... ... .... ............... .... ... ... .. ... ... .. ...... .. . ALERT 7.3 Ongoing Security Threat Within Plant Buildings ............. SAE 7.4 Ongoing Security Threat Within CR or Vital Area ............ GE 7.5 Fire or Explosion Onsite ................................... NUE 7.6 Fire or Explosion Onsite Affecting One Train of ESF Sy stems .................................................... ALERT 7.7 Fire or Explosion Onsite Affecting Both Trains of ESF Sy stem s . ................................................... SAE 7.8 Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flammable Gas ........ NUE 7.9 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ESF Systems . .................................. ALERT 7.10 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ESF Systems .................................... SAE 8.0 NATURAL EVENTS 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake ... NUE 8.2 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake ................................................. ALERT 8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake ................................................. SAE 9.0 MISCELLANEOUS EVENTS 9.1 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local Authorities ................................................ NUE 9.2 Plant Conditions Exist that Warrant Activation of the TSC .. ALERT 9.3 Plant Conditions Exist that Warrant Activation of the Emergency Response Facility ................................ SAE 9.4 Plant Conditions Exist That Make Release of Large Amount of Radioactivity Possible .................................. GE
ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.1 CONDITION
>0.1% fuel cladding failure RCS Activity indicates EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All TAB RELATED EALS:
1 indicates >1% fuel cladding failure 5 RCS Activity 6
High Radiation / Airborne Levels of Plant S/D or C/D due to T.S. L.C.O.
Initiation
PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 20 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.2 CONDITION
RCS Activity indicates >1% fuel cladding failure EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
I. Greater than 1% fuel cladding failure is indicated by Either of the following:
A. Nuclear Chemistry analysis of RCS sample yields:
- 1. >400 pCi/gm specific 1-13!
OR (OCNA08005} 2. Radiation levels that indicate >1% fuel cladding failure per Unit 1 Fuel Cladding Failure Radiation Plot (Att 7)
OR B. Failed Fuel Iodine monitor (RE 1237S) indicates >8.2 x l05 CPM.
RELATED EALS: TAB RCS Activity indicates >0.1% fuel cladding failure 1 Containment Radiation indicates LOCA and >1% fuel cladding failure I Loss of or Challenge to 3 Fission Product Barriers I Core Damage indicated with an ICC Condition I High Radiation/Airborne Levels 5 Initiation of Plant S/D or C/D due to T.S. L.C.O. 6
ATTACHMENT 3 UNIT i PRIMARY SYSTEM EVENTS
1.3 CONDITION
Core Cooling Condition Core Damage Indicated with an Inadequate EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
as evidenced by CETS indicating
- 1. Inadequate core cooling capacity exists of Figure 4 of EOP 1202.013.
superheated conditions of Region 3 AND is indicated by EITHER of the
- 2. Greater than 1% fuel cladding failure following:
yields:
A. Nuclear Chemistry analysis of RCS sample
- 1. >400 pCi/gm specific 1-131 OR indicate >1% fuel cladding failure
- 2. Radiation levels that (ocNAo80o5}
Plot (Att 7) per Unit 1 Fuel Cladding Failure Radiation OR (RE 1237S) indicates >8.2 x 10' CPM.
B. Failed Fuel Iodine process monitor TAB RELATED EALS:
1 Containment Radiation High/Very High Core Melt 1 Barriers Loss of or challenge to 3 Fission Product 2 RCS Leakage
PROC.WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 22 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT I PRIMARY SYSTEM EVENTS 1-4 CONDITION:
Containment Radiation reading which indicates LOCA and >1% fuel cladding failure EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Containment Radiation Levels correspond to a Site Area Emergency as Determined from the Containment Radiation EAL Plot (Att 5)
AND
- 2. LOCA occurring within the containment building RELATED EALS: TAB Containment Radiation indicates LOCA and > 50% fuel overheat 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 Radiological Effluents 5
PROC./WORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 23 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.5 CONDITION
Containment Radiation readings which indicate LOCA and >50% fuel overheat EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
- 1. Containment Radiation Levels correspond to a General Emergency as determined from the Containment Radiation EAL Plot (Att 5)
AND
- 2. LOCA occurring within the Containment Building RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers I Radiological Effluents 5 Core Melt 1
PROC.JWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 24 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.6 CONDITION
Core Melt EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
-. CETs indicate superheat conditions of Region 4 of Figure 4 of EOP 1202.013.
RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation High/Very High I Radiological Effluents 5
PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 25 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS
1.7 CONDITION
Loss of or challenge to all 3 Fission Product Barriers EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
- 1. Either of the following conditions exist:
A. Fuel Cladding Failure (refer to section 4.10.1)
- 5. Challenge to Fuel Cladding (refer to section 4.11.1)
AND
- 2. Either of the following conditions exist:
A. RCS boundary failure (refer to section 4.10.2)
B. Challenge to RCS boundary (refer to section 4.11.2)
AND
- 3. Either of the following conditions exist:
A. Containment Integrity failure (refer to section 4.10.3)
B. Challenge to Containment Integrity (refer to section 4.11.3)
RELATED EALS: TAB Containment Radiation High/Very High 1 Core Melt I Radiological Effluents 5 Natural Events 8
PROC./WORK PLAN NO. PROCEDURE,,ORK PLAN TITLE: PAGE: 26 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE
2.1 CONDITION
RCS Leakage > Tech. Spec. limits requiring a Plant S/D or C/D CRITERIA:
ITS RCS Leakage exceeds T.S. 3.1.6 [ITS T.S. 3.4.13 ITS] requirements necessitating a Plant S/D or C/D AND
- 2. A plant S/D or C/D has been initiated/commenced.
RELATED EALS: TAB RCS Leakage > Normal Makeup Capacity (50 gpm)
Initiation of Plant S/D or C/D due to TS LCO OTSG Tube Leak
PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 27 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE
2.2 CONDITION
RCS Leakage > Normal Makeup Capacity (50 gpm)
EMERGENCY CLASSIFICATION:
Alert MODES Above CSD CRITERIA:
- 1. An RCS leak necessitates EITHER of the following:
A. Need to open the BWST suction for the operating makeup pump due to a decreasing makeup tank level.
OR "B. Full or partial HPI is needed to maintain the RCS Pressure or Pressurizer Level RELATED EALS: TAB RCS Leakage > Normal Makeup Capacity with Fuel Cladding Failure 2 Conditions 2 RCS Leakage > HPI Capacity I Containment Radiation High/Very High 1 Core Damage Indicated with an ICC Condition .
Loss of or Challenge to 3 Fission Product Barriers 5 Radiological Effluents I Core Melt
ATTACHMENT 3 UNIT 1 RCS LEAKAGE 2 .3 CONDITION:
(so gpm) with >1.02 Fuel Cladding Failure RCS Leakage > Normal Makeup Capacity Conditions EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
(50 gpm) (EAL 2.2) with >1.0%
Fuel Cladding Failure NOTE gpm)
EAL 2.2 RCS Leakage > Normal Makeup Capacity (50 EAL 1.2 RCS Activity Indicates >1% fuel cladding failure TAB RELATED EALS:
1 and fuel failure Containment Radiation indicates LOCA 1 Core Damage Indicated with an ICC Condition 1
Barriers Loss of or Challenge to 3 Fission Product 5 Radiological Effluents 1 Core Melt
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 29 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE 2.4 EMERGENCY CLASSIFICATION:
CRITERIA:
A. Full available HPI being injected into the core AND B. RCS Pressure/Pressurizer Level continues to decrease or RCS Subcooling margin remains inadequate with no indication of recovery.
RELATED EALS: TAB Containment Radiation High/Very High 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1
PAGE: 30 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:
CHANGE: 036-04-0 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.1 EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD RELATED EALS:
OTSG Tube Leak Radiological Effluents
PROCJWORK PLAN NO. PROCEDURE)WORK PLAN TITLE: PAGE: 31 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.2 CONDITION
OTSG Tube Leakage > Tech. Spec. Limits EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD CRITERIA:
I. RCS Leak rate of > 150 gallons per day (.104 gpm), coincident with one or more of the following:
a)Main Steam line N-16 alarm(s) b)Steam Line High Range RAD Monitors Increase (RI-2681 or 2682) c)Condenser off gas process monitor count rate increase d)Nuclear Chemistry sample indicating Primary-Secondary tube leak RELATED EALS: TAB OTSG Tube Leak 3 RCS Leakage 2 Radiological Effluents 5
PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 32 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.3 EMERGENCY CLASSIFICATION:
CRITERIA:
RCS Leakrate increase of >I0 gpm., coincident with one of more of the following:
- a. Main Steam line N-16 alarms(s)
- b. Condenser Off Gas Process Monitor count rate increase
- c. Steam Line High Range Rad Monitors increase (RI-2681 or RI-2682)
- d. Nuclear Chemistry sample indicating primary-secondary tube leak AND
- 2. ANY of the following occur:
A. Loss of offsite power B. Steam release to the environment indicated by:
- 1. Main Steam Safety Valve(s) maintaining OTSG pressure
- 2. Use of ADV(s) to control OTSG pressure
- 3. P7A is in use and continued operation required to maintain OTSG levels
- 4. Steam line break outside containment RELATED EALS: TAB OTSG Tube Rupture >50 gpm with ongoing steam release 3 OTSG Tube Leak with fuel cladding failure 3 RCS Leakage 2 Radiological Effluents 5 High Radiation/Airborne Levels S Electrical Power Failures 4 Loss of or Challenge to 3 Fission Product Barriers 1
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 33 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.4 CONDITION
OTSG Tube Rupture with primary to secondary leakage >normal makeup capacity (50 gpm) with ongoing steam release or loss of offsite power.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
- i. OTSG Tube Rupture as indicated by BOTH of the following:
A. RCS Leakage > Normal Makeup Capacity (So gpm)
B. Coincident with one or more of the following:
a)Main Steam line N-16 alarm(s) b)Steam Line High Range RAD Monitors Increase (RI-2681 or 2682) c)Condenser off gas process monitor count rate increase d)Nuclear Chemistry sample indicating Primary-Secondary tube leak AND
- 2. ANY of the following occur:
A. Loss of offsite power B. Steam release to the environment indicated by:
- 1. Main Steam Safety Valve(s) maintaining OTSG pressure
- 2. Use of ADV(s) to control OTSG pressure
- 3. P7A is in use and continued operation required to maintain OTSG levels
- 4. Steam line break outside containment RELATED EALS: TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Electrical Power Failures 4
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 34 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS
3.5 CONDITION
OTSG Tube Leak >1 gpm with >1% fuel cladding failure with ongoing steam release EMERGENCY CLASSIFICATION:
Size Area Emergency MODES Above CSD CRITERIA:
Caution As Primary-to-Secondary leakage approaches 50 gpm, consider transitioning to EAL 1.7.
- i. OTSG Leakrate increase of >1 gpm, coincident with one or more of the following:
a) Main Steam line N-16 alarm(s) b) Steam Line High Range RAD Monitors Increase (RI-2681 or 2682) c) Condenser off gas process monitor count rate increase d) Nuclear Chemistry sample indicating Primary-Secondary tube leak AND
- 2. Greater than 1% fuel cladding failure indicated in the RCS (EAL 1.2)
AND
- 3. ANY of the following occur:
A. Loss of offsite power B. Steam release to the environment indicated by:
- 1. Main Steam Safety Valve(s) maintaining OTSG pressure
- 2. Use of ADV(s) to control OTSG pressure
- 3. P7A is in use and continued operation required to maintain OTSG levels
- 4. Steam line break outside containment RELATED EALS: TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers I Electrical Power Failures 4
PROC.JWORK PLAN NO. PROCEDUREfWORK PLAN TITLE: PAGE: 35 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES
4.1 CONDITION
Degraded Power EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
Only Diesel Generator (Station Blackout Diesel or Emergency Diesel) power is available to 4160V Buses (A3 and/or A4).
AND
- 2. No voltage indicated on 6.9 KV AND 4.16 KV nonvital buses (HI, H2, Al, and A2)
RELATED EALS: TAB Blackout 4 OTSG Tube Leak 3
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 36 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES
4.2 CONDITION
Station Blackout EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. All 4160V buses de-energized.
RELATED EALS: TAB Blackout more than 15 minutes 4 Loss of Control Room Annunciators 6
PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 37 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES
4.3 CONDITION
Blackout for more than 15 minutes.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
All 4160V buses de-energized for greater than 15 minutes.
RELATED EALS: TAB Electrical Power Failures 4 Loss of Control Room Annunciators 6 Core Melt 1
PROC./WORK PLAN NO. PROCEDUREfWORK PLAN TITLE: PAGE: 38 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT I ELECTRICAL POWER FAILURES
4.4 CONDITION
Loss of All Vital DC Power EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
Loss of voltage on ALL of the following busses A. D01 and D02 B. RAI and RA2 C. DIl and D21 RELATED EALS: TAB Loss of All Vital DC Power for more than 15 minutes 4 Loss of Control Room Annunciators 6
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 39 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES
4.5 CONDITION
Loss of All Vital DC Power for more than 15 minutes EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Loss of voltage on ALL of the following busses A. D01 and D02
- 9. RAI and RA2 C. D11 and D21 AND
- 2. DC power is not restored within 15 minutes RELATED EALS: TAB Electrical Power Failures 4 Loss of Control Room Annunciators 6
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 40 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.1 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to 0.05 mrem/hr TEDE or 0.15 mrem/hr Child Thyroid CDE or Liquid radiological effluents exceed ODCM Limitations.
EMERGENCY CLASSIFICATION:
CRITERIA:
!. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 0.05 mrem/hr TEDE or 0.15 mrem/hr Child Thyroid CDE.
OR B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds 0.05 mrem/hr TEDE or 0.15 mrem/hr Child Thyroid CDE.
OR C. Liquid radiological effluents exceed ODCM Limitations.
RELATED EALS:
Radiological Effluents High Radiation/Airborne Levels OTSG Tube Leak
PROCJWORK PLAN NO. PROCEDUREAWORK PLAN TITLE: PAGE: 41 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.2 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE or Liquid radiological effluents exceed 10 times ODCM Limitations.
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
-. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS method, indicates greater than or equal to 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE.
OR B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE.
OR C. Liquid radiological effluents exceed 10 times ODCM Limitations.
RELATED EALS: TAB Radiological Effluents 5 OTSG Tube Leak 3 Containment Radiation High 1
PROCJWORK PLAN NO. PROCEDURE!WORK PLAN TITLE: PAGE: 42 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.3 CONDITION
Radiological Effluents are greater than or equal to 50 mrem/hr TEDE or 150 mrem/hr Child Thyroid CDE at the Site Boundary.
CRITERIA:
Radiological Release which exceeds ANY of the following limits A. Projected dose rates at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 50 mrem/hr TEDE or 150 mrem/hr Child Thyroid CDE.
OR B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 50 mrem/hr TEDE or 150 mrem/hr Child Thyroid CDE.
RELATED EALS: TAB Radiological Effluents 5 Containment Radiation High / Very High 1 Loss of or Challenge to 3 Fission Product Barriers I Core Melt 1
PROCJWORK PLAN NO. PROCEDURETWORK PLAN TITLE: PAGE: 43 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.4 CONDITION
Radiological Effluents are greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE at the Site Boundary.
EMERGENCY CLASSIFICATION:
CRITERIA:
-. Radiological Release which exceeds ANY of the following limits A. Projected dose rates at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE.
OR B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE.
RELATED EALS:
Core Melt Loss of or Challenge to 3 Fission Product Barriers Containment Radiation High / Very High
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 44 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS
5.5 CONDITION
High Radiation/Airborne Levels EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
The loss of control of radioactive material results in ANY of the following:
A. Containment radiation indicates >2R/hr S. Area Radiation levels in controlled access (excluding containment) increase by 1 Rem/hr at 2 or more locations.
C. General area radiation levels outside of radiologically controlled areas increase by 10 mRem/hr.
D. Airborne levels as follows:
"* Auxiliary Building >100 DAC (General Area)
"* Turbine Building >10 DAC NOTE: "Loss of Control" shall be defined as: ANY radioactive material outside its normal system boundries. (For Example: spent resin spill, RCS liquid spill, spent fuel accident resulting in gaseous release, etc.)
RELATED EALS: TAB Radiological Effluents 5 Containment Radiation High 1 Spent Fuel Accident 5 RCS Leakage 2
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 45 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
1I The loss of water OR damage to a spent fuel assembly occurs in the Rx core (head removed), refueling canal, spent fuel pool, cask loading pit, fuel tilt pit or any plant area involved in the movement or storage of spent fuel.
AND
- 2. Radiation levels increase to 10 R/hr on Area Radiation Monitors or 10 Rem/hr HP Survey Report.
RELATED EALS:
Radiological Effluents High Radiation/Airborne Levels Miscellaneous Events
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TrTLE: PAGE: 46 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.1 CONDITION
Deviation from T.S. action statements when required to shutdown or cooldown or deviations pursuant to 10CFRSO.54(x)
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES Above CSD CRITERIA:
- 1. EITHER of the following conditions exist:
A. Inability to reach required mode within Tech. Spec. limits.
B. Deviation from Tech Specs authorized pursuant to 10CFR50.54(x)
RELATED EALS: TAB RCS Leakage 2 OTSG Tube Leak 3 RCS Activity High I
PROC.NVORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 47 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.2 CONDITION
Reactor Protection System Failure to Complete an Automatic Trip EMERGENCY CLASSIFICATION:
Alert MODES Hot Stdy-Pwr Ops CRITERIA:
- 1. A valid RPS trip setpoint is exceeded on ANY TWO RPS channels and the RPS fails to initiate and complete an automatic trip that brings the reactor subcritical.
AND
- 2. Subsequent efforts to manually trip the Reactor from the Control Room and bring it subcritical are successful.
RELATED EALS: TAB RPS Failure to Complete a Manual Trip 6 Core Melt 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers 1
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 48 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.3 CONDITION
Reactor Protection System Failure to Complete an Manual Trip EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Hot Stdy-Pwr Ops CRITERIA:
- 1. A valid RPS trip setpoint is exceeded on ANY TWO RPS channels and the RPS fails to initiate and complete an automatic trip that brings the reactor subcritical.
AND
- 2. Failure of manual trip function occurs. (Failure to trip the Reactor in the Control Room; i.e., must leave Control Room to trip the Reactor.)
RELATED EALS:
Loss of or Challenge to 3 Fission Product Boundaries Core Melt Core Damage Indicated with an ICC Condition
PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 49 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.4 CONDITION
Loss of Dose Assessment Capabilities EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. The following conditions exist in the Low Level Radwaste Building:
A. SPING is inoperable AND B. Compacting is in progress AND C. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 2. Reactor Building Purge System or Penetration Ventilation System is not isolable, and the applicable SPING is inoperable.
- 3. All of the following conditions exist for any source of gaseous effluents in the Auxiliary Building or Spent Fuel Storage Building ventilation systems.
A. Applicable SPING is inoperable AND B. Inability to obtain and analyze local grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> RELATED EALS: TAB None
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 50 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.5 CONDITION
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Complete loss of ANY TWO of the following:
A. Plant telephone systems (Commercial Telephones and microwave)
B. Station Radio C. Emergency Notification System
PROC.MWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 51 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.6 CONDITION
Loss of Control Room Annunciators EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Loss of both AC and DC power to >50% of control room annunciators.
RELATED EALS: TAB
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 52 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.7 CRITERIA
- 1. Loss of both AC and DC power to >50% of control room annunciators.
AND
- 2. A plant transient is initiated or in progress. (See section 4.18 of this procedure for the definition of a Plant Transient.)
PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 53 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.8 CONDITION
Control Room Evacuation EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Control Room evacuation is expected to occur OR has already occurred.
RELATED EALS: TAB Control Room Evacuation and control of shutdown systems not 6 established in 15 minutes Fire or explosion onsite affecting both trains of ay ES Systems 7
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 54 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION
6.9 CRITERIA
- 1. Control Room evacuation has occurred AND control of shutdown systems is not established from local stations within 15 minutes.
RELATED EALS:
Core Damage Indicated with an ICC Condition Loss of Decay Heat Removal Systems Core Melt
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 55 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.10 EMERGENCY CLASSIFICATION:
Alert MODES CSD-Refueling S/D CRITERIA:
- i. Loss of Decay Heat Removal capabilities shall be identified as ANY of the following:
A. RCS indicates saturated conditions "B. Loss of both Decay Heat trains for >1 hr and OTSGs are not available for decay heat removal (NA if Fuel Transfer Canal is flooded)
C. HPI is required for cooling the reactor core.
RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 High Radiation/Airborne Levels 5 Core Melt 1
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 56 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.11 CONDITION:
Degraded Hot Shutdown Capability EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
- 1. Degraded HSD capability shall be identified as ANY of the following:
A. Loss of ALL steam removal capability on BOTH OTSGs. (e.g., Loss of ALL Turbine Bypass Valves, Atmospheric Dump Valves, and Main Steam Safety Valves)
B. Loss of ALL feedwater supply capability on BOTH OTSGs. (e.g., Loss of BOTH Main Feedwater Trains and BOTH EFW trains)
C. BOTH HPI Trains are inoperable and they are required for cooling the reactor core.
RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 Containment Radiation Very High 1 Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 57 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.1 CONDITION
Security threat onsite but outside the Protected Area Security Fence (e.g.,
attempted entry or sabotage which has been stopped outside the security fence)
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Security threat onsite but outside the Protected Area Security Fence (e.g.,
attempted entry or sabotage which has been stopped outside the security fence).
or
- 2. A Credible site-specific security threat notification.
RELATED EALS: TAB Ongoing security Threat Inside Protected Area Fence but outside 7 plant buildings
PAGE: 58 of 130 PROC.IWORK PLAN N
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EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 1903.010 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.2 CONDITION
of Protected Area Security Fence but outside Ongoing security threat within the plant buildings RELATED EALS:
but not in Control Ongoing security threat within plant buildings Room or vital areas.
ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.3 CONDITION
the Control Room or plant buildings but not within Ongoing security threat within vital areas EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All
PROCJWORK PLAN N
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7.4 CONDITION
Ongoing security threat within the Control Room or vital areas j
CRITERIA:
same as the Condition stated above.
RELATED EALS: TAB None
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 61 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.5 CONDITION
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. Fire within the Protected Area Security Fence which is not extinguished within 10 minutes.
- 2. Explosion causing facility damage.
RELATED EALS: TAB Fire or Explosion Onsite Affecting One Train of an ES System 7
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 62 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.6 CONDITION
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- i. Fire or explosion onsite AND
- 2. A potential or actual loss of a single train of ANY ES system as a result of the fire or explosion RELATED EALS: TAB Fire or Explosion Onsite Affecting Both Trains of ANY ES System 7 Control Room Evacuation 6
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 63 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.7 EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Fire or explosion onsite AND
- 2. A potential or actual loss of Both trains of ANY ES system as a result of the fire or explosion RELATED EALS: TAB Control Room Evacuation and control of shutdown systems not 6 established in 15 minutes
PROCJWORK PLAN NO. PROCEDUREANORK PLAN TITLE: PAGE: 64 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION
7.8 CONDITION
Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine Failure, Toxic or Flammable Gas Release EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. ANY of the following:
A. Aircraft crash onsite.
B. Unusual Aircraft activity over the facility.
C. Train derailment onsite.
D. Turbine rotating component failure causing rapid plant shutdown.
E. Toxic or flammable gas release which limits or restricts access to areas required for security or safe operation of the plant.
RELATED EALS: TAB Fire or Explosion Onsite 7 Security Threat 7 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One 7 Train of ANY ES System
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 65 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT I HAZARDS TO STATION OPERATION
7.9 CONDITION
Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ANY ES Systems EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following:
A. Aircraft crash onsite.
B. Missiles/Projectiles from any source C. Toxic or flammable gas release AND
- 2. A potential OR actual loss of a single train of ANY ES system RELATED EALS: TAB Fire or Explosion Onsite Affecting One Train of an ES System 7 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both 7 Trains of ANY ES System
PROC.JWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 66 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.10 EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. ANY of the following:
A. Aircraft crash onsite.
B. Missiles/Projectiles from any source C. Toxic or flammable gas release AND
PROC.NWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 67 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 NATURAL EVENTS 8.1 EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
- 1. ANY of the following:
A. Tornado observed on the ground within the Exclusion Area B. Flood - Lake level >3401 elev. and rising, with forecasted
"-. lake level >350' elev.
C. Low Level - Lake level <337' elev. AND forecasted by U.S.
Army Corp of Engineers to reach 335' elev.
D. Earthquake - VERIFIED earthquake accompanied by .01g alarm.
RELATED EALS: TAB Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, 8 Earthquake:
PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 68 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 NATURAL EVENTS 8.2 EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following:
A. Tornado striking vital facility structures (e.g. housing ES related equipment)
B. High Winds - Sustained winds of >60 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).
C. Flood - Flood waters >350' elev. and are forecasted by U.S.
Army Corp of Engineers to reach or exceed 354' elev.
D. Low Level - Lake level <335' elev E. Earthquake - VERIFIED earthquake accompanied by .1g alarm.
or Any natural event resulting in the potential or actual loss of ONE train of ANY ES system.
RELATED EALS:
Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake Loss of or challenge to all 3 Fission Product Barriers
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 69 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 NATURAL EVENTS
8.3 CONDITION
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES Above CSD CRITERIA:
- 1. ANY of the following:
A. High Winds - Sustained winds of >67 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).
B. Flood - Flood Water Level is >361' elev.
C. Low Level Lake level <335' elev. and Emergency Cooling Pond not available D. VERIFIED Earthquake >0.2g E. Tornado, high wind, flood, low lake level or earthquake resulting in the potential or actual loss of BOTH trains of ANY ES system.
PROC.)WORK PLAN NO. PROCEDUREFWORK PLAN TITLE: PAGE: 70 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS
9.1 CONDITION
other plant conditions exist that warrant increased awareness on the part of the operating staff and state and/or local offsite authorities or involve other than normal controlled shutdown.
EMERGENCY CLASSIFICATION:
CRITERIA:
An event has occurred and the following conditions exist:
- 1. This event is not covered by any other EAL AND
- 2. This event does not challenge or cause the loss of a fission product barrier AND
- 3. In the judgement of the SM/TSC Director/EOF Director this event requires an increased awareness by the ANO staff and offsite authorities.
RELATED EALS: TAB
ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS
9.2 CONDITION
activation of the Technical that warrant precautionary Other plant conditions exist Facility and other Center and placing the near-site Emergency Operations Support key emergency personnel on standby.
RELATED EALS:
of the Emergency that Warrant Activation Plant Conditions Exist Response Centers.
PROC.fNORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 72 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS
9.3 CONDITION
Other plant conditions exist that warrant activation of the emergency response facilities and monitoring teams or a precautionary notification to the public near the site.
CRITERIA:
The following conditions must exist
- 1. This event is not covered by any other EAL.
AND
- 2. The event must cause ANY of the following:
A. Challenge two fission product barriers B. Failure of one fission product barrier and a challenge to another C. Failure of Two fission product barriers RELATED EALS: TAB Plant Conditions Exist that Make Release of Large Amounts of Radioactivity Possible
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 73 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS
9.4 CONDITION
Plant Conditions Exist That Make Release of Large Amounts of Radioactivity Possible EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
The following conditions must exist:
- 1. This event is not covered by any other EAL AND
- 2. Events have occurred that make a release of large amounts of radioactivity in a short period of time possible.
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 74 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS 1.i~
CONDITION:
RCS Activity indicates >0.1% fuel cladding failure EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-5 CRITERIA:
- i. Greater than 0.1% fuel cladding failure as indicated by EITHER of the following:
A. Selected isotope activity (1-131) >5.5E5 CPM (2RR4806 on 2C14 or 2RITS 4806B on 2C22)
B. Specific 1-131 sample results >37.8 pCi/gm RELATED EALS: TAB RCS Activity 1 T.S. L.C.O.'s 6 General Area Radiation/Airborne 5
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 75 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS
1.2 CONDITION
RCS Activity indicates >1.0% fuel cladding failure EMERGENCY CLASSIFICATION:
Alert MODES 1-5 CRITERIA:
I. Greater than 1% fuel cladding failure as indicated by either of the following:
{ocNAo8005) 2. Radiation levels that indicate >1% fuel cladding failure per Unit 2 Fuel Cladding Failure Radiation Plot (Att 8)
RELATED EALS: TAB General Area Radiation/Airborne 5 Containment Radiation 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Damage/ICC 1
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 76 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS
1.3 CONDITION
CRITERIA:
I. Greater than 1% fuel cladding failure as indicated by either of the following:
{OC2NA08005} 2. Radiation levels that indicate >1% fuel cladding failure per Unit 2 Fuel Cladding Failure Radiation Plot (Att 8)
AND
- 2. Inadequate core cooling capacity exists as indicated by ANY of the following:
A. Th RTD and average CET temperature indicates >10 0 F superheat AND RVLMS LVL 7 or Lower indicates Dry.
B. Th RTD and average CET temperature indicates >10 0 F superheat with both RVLMS Channels inoperable AND RCS temperatures increasing.
C. CET Temperatures indicate greater than 7000F.
RELATED EALS: TAB Decay Heat Removal 6 Containment Radiation 1 Core Melt 1 RCS Leakage 2
PROC.WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 77 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS
1.4 CONDITION
Containment Radiation readings which indicate LOCA and >1% fuel cladding failure EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
i, Containment Radiation Levels correspond to a Site Area Emergency as determined from the containment radiation EAL plot (Att 6)
AND
- 2. LOCA occurring within the Containment Building RELATED EALS: TAB Containment Radiation 1 Loss of or challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 78 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS
1.5 CONDITION
EMERGENCY CLASSIFICATION:
CRITERIA:
- 1. Containment Radiation Levels correspond to a General Emergency as determined from the containment radiation EAL plot (Att 6)
AND
- 2. LOCA occurring within the Containment Building RELATED EALS: TAB Loss of or challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 79 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS
1.6 CONDITION
EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
- 1. ANY of the following events occur A. Small or Large LOCA and a complete failure of ALL ECCS systems occurs.
B. Loss of ALL feedwater AND S/G Level in both S/G's is <70" (Wide Range)
-. AND a complete failure of ALL ECCS Systems occurs.
C. Anticipated transient without a Rx trip AND
- 2. Containment Integrity is lost OR challenged as defined by 4.10.3 or 4.11.3 (Definitions)
RELATED EALS: TAB Loss of or challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 80 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS 1.7 EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
Either of the following conditions exist:
A. Fuel Cladding Failure (refer to section 4.10.1)
B. Challenge to Fuel Cladding (refer to section 4.11.1)
AND
- 2. Either of the following conditions exist:
A. RCS boundary failure (refer to section 4.10.2)
B. Challenge to RCS boundary (refer to section 4.11.2)
AND
- 3. Either of the following condition exist A. Containment Integrity failure (refer to section 4.10.3)
B. Challenge to Containment Integrity (refer to section 4.11.3)
RELATED EALS: TAB Containment Radiation 1 Core Melt 1 Radiological Effluents 5 Natural Events 8
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 81 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 RCS LEAKAGE
2.1 CONDITION
RCS Leakage > Tech. Spec. Limits requiring a plant S/D or C/D EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
- 1. RCS Leakage exceeds ANY of the following limits: (T.S. 3.4.6.2)
A. RCS pressure boundary leakage >0 B. Unidentified RCS Leakage >1 gpm C. Identified RCS Leakage >10 gpm D. RCS Pressure Isolation Valves Leakage > T.S. Table 3.4.6.-l limits AND
- 2. A Plant S/D or C/D has been initiated/commenced RELATED EALS: TAB RCS Leakage . 2 T.S. L.C.O.'s 6 Primary to Secondary Leakage 3 General Area Radiation/Airborne 5
PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 82 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 RCS LEAKAGE 2.2 EMERGENCY CLASSIFICATION:
Alert MODES 1-4 CRITERIA:
- 1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump).
RELATED EALS: TAB RCS Leakage 2 General Area Radiation/Airborne 5 Containment Radiation 1 Decay Heat Removal 6 Primary to Secondary Leakage 3
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 83 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 RCS LEAKAGE
2.3 CONDITION
CRITERIA:
- 1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump).
AND
- 2. Inadequate Core Cooling conditions exist as indicated by ANY of the following:
A. Th RTD and average CET temperature indicates >10 0 F superheat AND RVLMS LVL 7 or Lower indicates Dry.
B. Th RTD and average CET temperature indicates >10 0 F superheat with both RVLMS Channels inoperable AND RCS temperature increasing.
C. CET Temperatures indicate greater than 7000F.
RELATED EALS: TAB Core Damage/ICC 1 Radiological Effluents 5 Containment Radiation 1 Core Melt 1 Loss of or challenge to 3 Fission Product Barriers 1 Primary to Secondary Leakage 3
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 84 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS
3.1 CONDITION
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
- 1. Any actuation of MSIS due to uncontrolled Steam Generator depressurization.
RELATED EALS: TAB Primary to Secondary Leakage 3 Radiological Effluents 5
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 85 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS 3.2 EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-4 CRITERIA:
I. Primary to Secondary Leakage exceeds EITHER of the following limits A. Total leakage through both S/G's is > 300 gallons per day (0.2083 gpm)
OR B. Leakage to 1 S/G is > 150 gallons per day (0.1042 gpm)
RELATED EALS: TAB RCS Leakage 2 Primary to Secondary Leakage 3 Radiological Effluents 5
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 86 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS 3.3 EMERGENCY CLASSIFICATION:
Alert MODES 1-4 CRITERIA:
- 1. S/G tube leak >10 gpm with a Steam Release in Progress as indicated by ANY of the following:
A. Main Steam Safety Valves maintaining S/G Pressure B. SDBCS Atmospheric Dump Valves in Use C. Steam Line Break Outside of Containment D. 2P7A is in use and continued operation is required to maintain S/G levels.
RELATED EALS: TAB Primary to Secondary Leakage 3 RCS Leakage 2 General Area Radiation/Airborne 5 Radiological Effluents 5 Electrical Power 4
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 87 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS
3.4 CONDITION
Steam Generator Tube Rupture >44 gpm With an Ongoing Steam Release and RCS Activity > 1.0 pCi/gm, but < 378 pCi/gm (1% fuel cladding failure).
CRITERIA:
- 1. S/G tube leak >44 gpm with a Steam Release in Progress as indicated by ANY of the following:
A. Main Steam Safety Valve(s) maintaining S/G Pressure B. SDBCS Atmospheric Dump Valve(s) in Use C. Steam Line Break Outside of Containment D. 2P7A is in use and continued operation is required to maintain S/G levels.
AND
- 2. RCS Activity > 1.0 gCi/gm (T.S. 3.4.8), but < 378 pCi/gm (1% fuel cladding failure).
CAUTION As fuel cladding failure approaches 1% (378 pCi/gm 1-131) EAL 1.7 may apply.
RELATED EALS: TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1 Electrical Power 4
PROCJWORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 88 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES
4.1 CONDITION
EMERGENCY CLASSIFICATION:
CRITERIA:
- 1. Temporary Loss of Normal Control Room Lighting AND
- 2. No voltage indicated on Both 4.16 KV nonvital busses (2AI & 2A2)
AND
- 3. At least one Emergency Diesel or Station Blackout Diesel started and supplying a vital bus (2A3 or 2A4)
RELATED EALS: TAB Electrical Power 4 MSIS 3 Primary to Secondary Leak 3
PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 89 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.2 EMERGENCY CLASSIFICATION:
Alert MODES All Modes CRITERIA:
- 1. Loss of all Control Room Lighting except emergency DC Lights AND
- 2. No voltage indicated on Both 4.16 KV nonvital busses. (2A1 and 2A2)
AND
- 3. No voltage indicated on Both 4.16 KV vital busses (2A3 and 2A4)
RELATED EALS: TAB Electrical Power 4 Communications, Dose Assessment 6 Primary to Secondary Leak 3 Decay Heat Removal 6 Core Melt 1
PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 90 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES
4.3 CONDITION
EMERGENCY CLASSIFICATION:
Alert MODES 1-4 CRITERIA:
- 1. Loss of All of the following busses has occurred:
A. 2D01 and 2D02 B. 2RA1 and 2RA2 C. 2D21 and 2D23 D. 2D22 and 2D24 RELATED EALS: TAB Electrical Power Communications, Dose Assessment
ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES
4.4 CONDITION
Blackout >15 minutes.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Blackout has occurred as indicated by ALL of the following:
DC lights A. Loss of all Control Room lighting except emergency KV nonvital busses (2A1 and 2A2)
B. No voltage indicated on Both 4.16 (2A3 or 2A4)
C. Neither Vital 4.16 KV Buss energized AND for >15 minutes
- 2. The Blackout Condition exists TAB RELATED EALS:
6 Decay Heat Removal 4 Electrical Power 3 Primary to Secondary Leakage 5 Core Melt 5 Radiological Effluents
ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES
4.5 IONDITION
Loss of ALL Vital DC for >15 minutes EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
I of DC Busses has occurred:
Loss of both of the following trains RED TRAIN GREEN TRAIN 2D01 2D02 2RA1 2RA2 2D21 2D22 2D23 2D24 AND within 15 minutes
- 2. Power is not restored to at least one train TAB RELATED EALS:
6 Communications, Dose Assessment 6 Decay Heat Removal I Core Melt 5 Radiological Effluents
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.1 CONDITION
over one hour, is at the Site Boundary, averaged Projected or measured activity Child Thyroid CDE or mrem/hr TEDE or 0.15 mrem/hr greater than or equal to 0.05 exceed ODCM Limitations.
Liquid radiological effluents EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
following limits
- 1. Radiological Release which exceeds ANY of the by the RDACS A. Projected activity at the Site Boundary, as calculated equal to 0.05 mrem/hr TEDE or 0.15 method, indicate greater than or mrem/hr Child Thyroid CDE.
OR at the Site Boundary which, B. Offsite monitoring teams report activity or one hour, exceeds 0.05 mrem/hr TEDE when averaged over the previous 0.15 mrem/hr Child Thyroid CDE.
C. Liquid radiological effluents exceed TAB RELATED EALS:
5 Radiological Effluents 5
General Area Radiation/Airborne 3 Primary to Secondary Leak
PROC.)WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 94 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.2 CONDITION
Projected or measured activity at the Site Boundary, averaged over one hour, is greater than or equal to 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE or Liquid radiological effluents exceed 10 times ODCM Limitations.
EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE.
OR B. Offsite monitoring teams report activity at the Site Boundary which, when averaged over the previous one hour, exceeds 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE.
OR C. Liquid radiological effluents exceed 10 times ODCM Limitations.
RELATED EALS: TAB Radiological Effluents 5 Primary to Secondary Leak 3 Containment Radiation 1
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.3 CONDITION
or 150 mrem/hr than or equal to 50 mrem/hr TEDE Radiological Effluents are greater Child Thyroid CDE at the Site Boundary.
CRITERIA:
limits
- 1. Radiological Release which exceeds ANY of the following as calculated by the RDACS A. Projected dose rates at the Site Boundary, or equal to 50 mrem/hr TEDE or 150 method, indicate greater than mRem/hr Child Thyroid CDE.
OR rates at the Site Boundary are B. Offsite monitoring teams report dose or 150 mrem/hr Child Thyroid greater than or equal to 50 mrem/hr TEDE CDE.
PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 96 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.4 CONDITION
Radiological Effluents are greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE at the Site Boundary.
EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
I. Radiological Release which exceeds ANY of the following limits A. Projected dose rates at the Site Boundary, as calculated by the RDACS method, indicate greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE.
OR B. Offsite monitoring teams report dose rates at the Site Boundary are greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE.
RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 1
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.5 CONDITION
High Radiation/Airborne Levels EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
material results in ANY of the following:
The loss of control of radioactive A. Containment radiation indicates >2R/hr (excluding containment)
B. Area Radiation levels in controlled access locations.
increase by 1 Rem/hr at 2 or more of radiologically controlled C. General area radiation levels outside areas increase by 10 mRem/hr.
D. Airborne levels as follows:
"* Auxiliary Building >100 DAC (General Area)
"* Turbine Building >10 DAC as: Ay Radioactive material NOTE: "Loss of Control" Shall be defined outside its normal system boundaries.
RCS liquid spill, Spent fuel accident (For Example: Spent resin spill, resulting in gaseous release, etc.)
ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS
5.6 'ONDITION
Spent Fuel Accident EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
spent fuel assembly occurs in the
- 1. The loss of water OR damage to a cask Rx core (head removed), refueling canal, spent fuel pool, involved in the loading pit, fuel tilt pit or any plant area movement or storage of spent fuel.
AND or R/hr by Area Radiation Monitors
- 2. Radiation levels increase to 10 10 Rem/hr HP survey report.
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.1 CONDITION
shutdown or cooldown or statements when required to Deviation from T.S. action (x) deviations pursuant to 10CFR5O.54 EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES 1-44 RELATED EALS:
RCS Leakage Primary to Secondary Leakage RCS Activity
PROCJWORK PLAN NO. PROCEDUREWORK PLAN TITLE: PAGE: 100 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.2 EMERGENCY CLASSIFICATION:
CRITERIA:
- 1. A valid RPS trip setpoint is exceeded AND
- 2. Ten (10) or more CEAs fail to insert as result of the automatic trip AND
- 3. CEAs are inserted either by manual trip or DSS.
RELATED EALS: TAB RPS Failure 6 Core Melt I Core Damage/ICC I
PAGE: 101 of 130 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:
CHANGE: 036-04-0 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.3 CRITERIA
- 1. A valid RPS trip setpoint is exceeded AND to insert after the RPS, DSS and manual trip
- 2. Ten (10) or more CEAs fail CEAs due to (Example: 2B7 & 2B8 feeder breakers opened to insert a failure of automatic and manual RPS trips.)
TAB RELATED EALS:
1 Barriers Loss of or Challenge to 3 Fission Product 1 Core Melt Core Damage/ICC
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.4 CONDITION
Loss of Dose Assessment Capabilities EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
in the Low Level Radwaste Building:
- 1. The following conditions exist A. SPING is inoperable B. Compacting is in progress samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Inability to obtain and analyze local grab OR applicable is not isolable and both the
- 2. Reactor Building Purge penetration inoperable.
Monitor are SPING and the Process Radiation OR effluents in exist for any source of gaseous
- 3. All of the following conditions Storage Extension Building, or Spent Fuel the Auxiliary Building, Auxiliary Building ventilation systems.
A. Applicable SPING is inoperable is inoperable B. Applicable Process Radiation Monitor samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Inability to obtain and analyze local grab TAB RELATED EALS:
6 Communications, Dose Assessment
PAGE: 103 of 130 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:
EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 1903.010 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.5 CRITERIA
- 1. Complete loss of ANY TWO of the following:
A. Plant telephone systems (Commercial telephones and microwave)
B. Station Radio C. Emergency Notification System TAB RELATED EALS:
None
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.6 )NDITION
,ontrol Room Evacuation 4ERGENCY CLASSIFICATION:
Alert MODES All RITERIA:
- i. Control Room evacuation is expected to occur OR has already occur TAB RELATED EALS:
6 Control Room Evacuation
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.7 CONDITION
in 15 of shutdown systems not established Control Room Evacuation and control minutes.
TAB RELATED EALS:
1 6
rCore Damage/ICC Decay Heat Removal 1 Core Melt
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.8 CRITERIA
the shall be identified as ANY of
- 1. Loss of Decay Heat Removal capabilities following:
A. RCS indicates saturated conditions for >1 hr and S/G's not available B. Loss of both shutdown cooling trains Transfer Canal >23 ft) for decay heat removal (NA if Fuel the core C. HPSI injection required for cooling TAB RELATED EALS:
5 RELATED EALS : 1 en Feltent 5
Core Damage/ICC 1 Barriers 5 Loss of or Challenge to 3 Fission Product 1 High Radiation/Airborne Core Melt
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION
6.9 CRITERIA
- 1. ALL of the following conditions exist:
S/G level in BOTH S/Gs is <70" A.
AND B. ECCS Vent System is utilized
PAGE: 108 of 130 PROCJWORK PLAN N
O. PROCEDURE
IWORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.10 TAB RELATED EALS:
6 a Transient in progress 4 Loss of Control Room Annunciators with Electrical Power
ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6 .11
PAGE: 110 of 130 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION
7.1 CONDITION
Area Security Fence (e.g.
Security threat onsite but outside the Protected outside the security fence).
attempted entry or sabotage which has been stopped EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
Area Security Fence (e.g.,
- 1. Security threat onsite but outside the Protected outside the security fence).
attempted entry or sabotage which has been stopped or
- 2. A credible site-specific security threat notification.
7 Security Threat
PAGE: 111 of 130 PROC.WORK PLAN N
O. PROCEDURE
MWORK PLAN TITLE:
036-04-0 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE:
ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION
7.2 CONDITION
Area Security Fence but outside of Ongoing security threat within the Protected plant buildings.
CRITERIA:
Same as the Condition stated above.
TAB RELATED EALS:
7 Security Threat Fire or Explosion
ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION
7.3 CONDITION
Control Room or threat within plant buildings but not within the Ongoing security vital areas.
TAB RELATED EALS:
7 7
Security Threat Fire/Explosion
ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.4
PAGE: 114 of 130 PROC./WORK PLAN NO. PROCEDUREWORK PLAN TITLE:
EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 1903.010 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION
7.5 CONDITION
Fire or Explosion Onsite EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
Fence which is not extinguished
- i. Fire within the Protected Area Security within 10 minutes.
- 2. Explosion causing facility damage.
TAB RELATED EALS:
7 Fire or Explosion 7 Security Threat
ATTACHMENT 4 UNIT 2 OPERATION HAZARDS TO STATION 7.6
ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION
7.7 'ONDITION
Both Trains of ESF Systems Fire or Explosion Onsite affecting "EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
- 1. Fire or explosion onsite AND of trains of ANY ESF system as a result
- 2. A potential or actual loss of Both the fire or explosion.
TAB RELATED EALS:
6 Communications, Dose Assessment 6 Control Room Evacuation______
PAGE:. 117 of 130 PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION
7.8 CONDITION
Train Derailment, Turbine failure, Toxic Aircraft Crash, Unusual Aircraft Activity, or Flammable Gas EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
I. ANY of the following A. Aircraft crash onsite B. Unusual Aircraft activity over the facility C. Train derailment onsite shutdown D. Turbine rotating component failure causing rapid plant access to E. Toxic or flammable gas release which limits or restricts of the plant.
areas required for security or safe operation TAB RELATED EALS:
7 Fire or Explosion 7
Security Threat 3
MSIS 7 Other Hazards
PAGE: 118 of 130 PROCJWORK PLAN NO. PROCEDUREMWORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.9 EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following A. Aircraft crash onsite B. Missiles/Projectiles from any source C. Toxic or flammable gas release AND
- 2. A potential OR actual loss of a single train of ANY ESF system RELATED EALS: TAB Fire or Explosion 7 Other Hazards 7
PROC.NORK PLAN NO. PROCEDUREIWORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 CHPAGE: 119 of 130 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.10 CONDITION:
Redundant ESF Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains CRITERIA:
- 1. ANY of the following CRITERIA:
- i. A. Aircraft crash onsite B. Missiles/Projectiles from any source C. Toxic or flammable gas release AND of ANY ESF system
- 2. A potential OR actual loss of BOTH trains
PAGE: 120 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 NATURAL EVENTS 8.1 UOND+/-'I"+/-U*:
CONDITION:
Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake CRITERI A :
- 1. ANY of the following A. Tornado observed on the ground within the Exclusion Area B. Flood - Lake level >340' elev. and rising with forecasted lake level
>350' elev.
Low Level - Lake level <337' AND forecasted by U.S. Army Corp of C.
Engineers to reach 335' D. Earthquake - VERIFIED earthquake accompanied by .01g alarm.
TAB RELATED EALS:
8 Natural Events
PAGE: 121 of 130 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION HANGE. 036-04-0 ATTACHMENT 4 UNIT 2 NATURAL EVENTS
8.2 CONDITION
Flood, Loss of Dardanelle Reservoir, Earthquake Tornado, High Winds, EMERGENCY CLASSIFICATION:
Alert MODES All CRITERIA:
- 1. ANY of the following facility structures (e.g. housing ES related A. Tornado striking vital equipment) average as reported B. High Winds - Sustained winds of >72 mph (10 minute by RDACS from either the 10 or 57 meter instruments).
U.S. Army Corp of C. Flood - Flood waters >350' and are forecasted by Engineers to reach or exceed 354' D. Low Level Lake level <335' elevation Earthquake - VERIFIED Earthquake accompanied by .1g alarm.
E.
OR Any natural event resulting in the potential or actual loss of ONE train of ANY ES system TAB RELATED EALS:
8 Natural Events 3 Fission Product Barriers 1 Loss of or challenge to all
I '10 4f 12 l O Af*ko I !1 ill IdU PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:
EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 1903.010 ATTACHMENT 4 UNIT 2 NATURAL EVENTS
8.3 CONDITION
Flood, Loss of Dardanelle Reservoir, Earthquake Tornado, High Winds, EMERGENCY CLASSIFICATION:
Site Area Emergency CRITERIA:
- 1. ANY of the following average as reported A. High Winds - Sustained winds of >80 mph (10 minute by RDACS from either the 10 or 57 meter instruments).
B. Flood - Flood Water Level is >361, elev.
C. Low Level - Lake level <335' elev. and Emergency Cooling Pond not available.
D. VERIFIED Earthquake >0.2g resulting in E. Tornado, high wind, flood, low lake level or earthquake actual loss of BOTH trains of ANY ESF system.
the potential or TAB RELATED EALS:
1 Loss of or challenge to all 3 Fission Product Barriers
ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS
9.1 CONDITION
the part of the warrant increased awareness on Other plant conditions exist that authorities or involve other than operating staff and state and/or local offsite normal controlled shutdown.
EMERGENCY CLASSIFICATION:
Notification of Unusual Event MODES All CRITERIA:
conditions exist:
An event has occurred and the following
- 1. This event is not covered by any other EAL AND cause the loss of a fission product barrier
- 2. This event does not challenge or AND Director/EOF Director this event requires an
- 3. In the judgement of the SM/TSC authorities.
and offsite increased awareness by the ANO Staff TAB RELATED EALS:
1 RCS Activity 2 RCS Leakage 3 Primary to Secondary Leak 5 Radiological Effluents 6 T.S. L.C.O.'s 6 Assessment Loss of Indications/Communications/Dose
PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 124 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-04-0 CHANGE:
ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS 9.2
- UL*IIJ.I. +/-Iui* ;
UIN L) _L I _LULN :
Technical Other plant conditions exist that warrant precautionary activation of the placing the near-site Emergency Operations Facility and other Support Center and key emergency personnel on standby.
ArO(M('V CT. cTTC'TTrThr*
Alert MODES All CRITERIA:
The following conditions must exist
- 1. This event is not covered by any other EAL AND
- 2. This event must either challenge or cause the loss of a fission product barrier.
RELATED EALS: TAB RCS Activity 1 RCS Leakage 2 Primary to Secondary Leak 3 Radiological Effluents 5 Decay Heat Removal 6
PAGE: 125 of 130 PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:
1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS
9.3 CONDITION
response Other plant conditions exist that warrant activation of emergency and monitoring teams or a precautionary notification to the public near facilities the site.
EMERGENCY CLASSIFICATION:
Site Area Emergency MODES All CRITERIA:
The following conditions must exist
- i. This event is not covered by any other EAL AND
- 2. This event may cause ANY of the following:
A. Challenge to two fission product barriers B. Failure of one fission product barrier and a challenge to another C. Failure of 2 fission product barriers TAB RELATED EALS:
1 Core Damage/ICC 1
Containment Radiation 6
Radiological Effluents 2
RCS Leakage 3
Primary to Secondary Leak
PROC.NVORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 126 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-04-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS
9.4 CONDITION
EMERGENCY CLASSIFICATION:
General Emergency MODES All CRITERIA:
The following conditions must exist
- 1. This event is not covered by any other EAL AND
- 2. Events have occurred that make a release of large amounts of radioactivity in a short period of time possible.
RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5
ATTACHMENT S UNIT 1 NOTE:
Attachment 7 (WITH Spray), SAE equals 1%
This graph corresponds with 1903.011 and GE equals 50% Fuel Overheat.
Clad Failure CONTAINMENT RADIATION EAL PLOT 1E+06 1E+05.
4 2
4 4 I GENERAL 2 1 I - t l, - - - ,i- L EMERGENCY 1E+04 I I i i i i i i RJHR 4 2
IE+031 I I I I I I I I I I 4:
2.
- 11--
1E+02
- 4. 7-- SITE 2
1E+01 I I I I 1 16 1 18 L 20 TZ22 14EMERGENCY 24 0 2 4 6 8I 10 12 14 0
TIME IN HOUR INSTRUCTIONS CAUTION containment temperature transient, should be considered significant valid.
readings of a In the absence temperature transient, monitor
- monitor F* nthe event of a significant containment 4 duration (Ref.IN 5, Supplement 1) readings may be erratic for a short A. Determine the containment radiation level.
days, use the reading from RE-8060 or
- 1. If the plant has been operating at 100% for the past 30 RE-8061.
for the past 30 days, determine the
- 2. If the plant has been operating at less than 100% power radiaiton level as follows:
X 100%
Rad level = Reading from RE-8060 or RE-8061 estimated ave. power for the past 30 days B. Determine the time after shutdown (in hours).
C. Find the intersection of the values from A and B on the graph.
D. Determine the emergency class.
two curves
- 1. SITE AREA EMERGENCY - intersection is between the curve the upper
- 2. GENERAL EMERGENCY - intersection is above
ATTACHMENT 6 UNIT 2 NOTE:
Attachment 8 (WITH Spray), SAE equals 1%
This graph corresponds with 1903.011 and GE equals 50% Fuel Overheat.
Clad Failure CONTAINMENT RADIATION EAL PLOT 1E÷06 4
1E+05 2 _GENERAL EMERGENCY I E+04* ...
IE+04 R-R 4 2
1 E+03 .
4 2.
1E+024 : SITE AREA IE+01 tEMERGENCY 620 22 24 6 8 10 12 4 0 2 4 TIME IN HOUR INSTRUCTIONS I
I n CAUTION be considered valid. transient, monnit'or readings a should temperature containmenttemperature transient, monitor containment Inn the event of of asignificant significant
- In the absence (Ref.IN-97-45, Supplement 1) readings may be erratic for a short duration A. Determine the containment radiation level.
use the reading from 2RY-8925-1 or
- 1. If the plant has been operating at 100% for the past 30 days, 2RY-8925-2.
for the past 30 days, determine the
- 2. If the plant has been operating at less than 100% power radiaiton level as follows:
X 100%
Rad level = Reading from 2RY-8925-1 or 2RY-8925-2 estimated ave. power for the past 30 days B. Determine the time after shutdown (in hours).
C. Find the intersection of the values from A and B on the graph.
D. Determine the emergency class. two curves
- 1. SITE AREA EMERGENCY - intersection is between the curve GENERAL EMERGENCY - intersection is above the upper 2.
Attachment 7 (OCNA08005)
Unit 1 Fuel Cladding Failure Radiation Plot mRem/hr at SA-229 2000
~
.~ ~........ _.....
1500 wIL g~ 1000 500 m - -
- - - - - - - m - - - - - - -
0 I I I I I 3 6 12 24 48 96 192 0 0.5 1 Instructions for obtaining the dose rates Time (hours since shutdown) resides in the Chemistry sample procedure. .- 5% Fuel Cladding Failure 1% Fuel Cladding Failure
Attachment 8 (OCNA08005)
Unit 2 Fuel Cladding Failure Radiation Plot mRem/hr at 2TCD- 19 3500 3000 2500
.,, 2000 S 1500 _
1000 500 -.-.-.
0 6 12 24 48 96 192 0 0.5 1 3 Instructions for obtaining the dose rate Time (hours since shutdown) resides in the Chemistry sampling 1% Fuel Cladding Failure
-'5% Fuel Cladding Failure - - -
procedure