ML032180018

Change 037-02-0 to OP-1903.010, Emergency Action Level Classification

ML032180018
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/31/2003
From:	Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032180018 (134)

Text

Arkansas Nuclear One - Administrative Services Document Control Thursday, July 31, 2003 Document Update Notification COPYHOLDER NO: 103 TO: ANO-NRC (EMERGENCY RESPONSE COORD.) - WASHINGTON ADDRESS: OS-DOC CNTRL DESK MAIL STOP OP1-17 WASHINGTON DC 20555-DC DOCUMENTNO: OP-1903.010 TITLE: EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE NO: 037-02-0 ADDITIONAL INFO:

7 If this box is checked, please sign, date, andreturn within 5 days.

]i ANO-1 Docket 50-313 ThlS ANO-2 Docket 50-368 Signature Date SIGNATURE CONFIRMS UPDATE HAS BEEN MADE RETURN TO:

ATTN: DOCUMENT CONTROL-(N-ADMIN-24)

ARKANSAS NUCLEAR ONE 1448 SR 333 RUSSELLVILLE, AR 72801

I ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: EMERGENCY ACTION LEVEL DOCUMENT NO. CHANGE NO.

CLASSIFICATION 1903.010 037-02-0 WORK PLAN EXP. DATE TC EXP. DATE N/A N/A SEUT#4 I¶)2SAFETY-RELATED IPTE OYES EINO [YES 0N0 TEMP ALT

_EYES ONO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionfinterruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Nomnal Job Briefing Cl-nz:e ~aI .. dn;a~nmant Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: jFORM NO. ICHANGE NO.

I , 050-00-0 VERIFICATION COVER SHEET VERIFICATION COVER SHEET JI 1000.006A 1000.OOBA j 050-00-0

ENTERGY OPERATIONS INCORPORATED I ARKANSAS NUCLEAR ONE 4

Pane 1 TITLE:EMERGENCY ACTION LEVEL CLASSIFICATION DOCUMENT -NO. CHANGE NO.

I 1903.010 I 037-02-0 AFFECTED UNIT: 0 PROCEDURE 0 ELECTRONIC DOCUMENT SAFETY-RELATED 0 UNIT I UNIT2 E WORKPLAN, EXP. DATE 0 YES 0 NO TYPE OF CHANGE:

0 NEW 0 PC 0 TC 0 DELETION D REVISION D EZ EXP. DATE:_ _

DOES THIS DOCUMENT:

1. Supersede or replace another procedure? - YES ONO (If YES, complete 1000.006B for deleted procedure.) (DCAN058107)

2. Alter or delete an existing regulatory commitment? 0 YES O NO (If YES, coordinate with Licensing before implementing.) (OCNA128509)(0CAN049803)

3. Require a 50.59 review per LI-101? (See also 1000.006, Attachment 15) 0 YES 0 NO (if 50.59 evaluation, OSRC review required.)

4. Cause the MTCL to be untrue? (See Step 8.5 for details.) 0 YES O NO (If YES, complete 1000.009A) (1CAN108904, OCAN099001, OCNA128509, OCAN049803)

5. Create an Intent Change? ElYES 1 NO (If YES, Standard Approval Process required.)

6. Implement or change IPTE requirements? l YES ONO (If YES, complete 1000.143A OSRC review required.)

7. Implement or change a Temporary Alteration? E0 YES - NO (if YES, then OSRC review required.)

Was the Master Electronic File used as the source document? -1 YES D NO INTERIM APPROVAL PROCESS STANDARD APPROVAL PROCESS v ORIGINATOR SIGNATURE: (Includes review of Att. 13) DAT ORIGINATOR SIGN7A E: (Inch s review of Att. 13) DATE: Gaff 41A Print and Sign name: ZPH NE U: Print and Sign name: Roger Freem PHONE U:99 Y SUPERVISOR APPROVAL:

• DATE: INDEPENDENT REVIEWER DATE:

SRO UNIT ONE :- DATE: ENGINEERING: DATE; SRO UN O: DATE: QUALITY: DATE:

- nterim approval allowed for non-ntent 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 _ N LEADED DATE-requiring a 50.59 evaluation. , - U2'//

• If change not required to support work in progress, QUALITY ASSURANCE: 4 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 la jiW G A - 7//°A° )

procedures only.) OT KEkDERS: 1AJE:

. . ~~~~~~~~~~~~~~~~~OATE  :

.OTWR SECIV AE M: DATE:

OSRC CHAIRMAN/TECHNICAL REVIEW CNA049312) DATE: OTHER SECTION LEADERS: DATE:

FINAL APPROVA(7, Date: OTHER SECTION LEADERS: DATE:

REQUIRED EFFEiVE  : 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 DOCUMENT NO. CHANGE NO.

CLASSIFICATION 1903.010 037-02-0 OPROCEDURE OWORK PLAN, EXP. DATE PAGE I OFF O ELECTRONIC DOCUMENT TYPE OF CHANGE:

o NEW E0 PC E TC El DELETION O REVISION 0 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) Added note OIf RX Is critical, use Time 0" to graph to give the operators guidance for usage of Page 129 of 130 the graph. Added note 'If RX Is critical, use Time 0 to graph to give the operators guidance for usage of Page 130 of 130 the graph.

FORM TITLE: FORM NO. CHANGE NO.

DESCRIPTION OF CHANGE 1000.006C 050-00-0

PROCJWORK PLAN NO. PROCEDURENVORK PLAN TITLE: PAGE: 1 of 130 :

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 TABLE OF CONTENTS SECTIONS PAGE NO.

1.0 Purpose ....................................... 2 2.0 Scope ........................................ 2 3.0 References ........................................ 2 4.0 Definitions ....................................... 3 5.0 Responsibility and Authority . . 8 6.0 Instructions ....................................... 9 7.0 Attachments and Forms .................. I ...12 7.1 Attachment 1 - Unit 1 Index of EALs .13 7.2 Attachment 2 - Unit 2 Index of EALs .16 7.3 Attachment 3 - Unit 1 Emergency Action Levels .19 7.4 Attachment 4 - Unit 2 Emergency Action 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

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 2 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 1.0 PURPOSE This procedure establishes criteria for detection and classification of plant events into the four standard Emergency-Classes.

2.0 SCOPE This procedure is applicable to Units l and 2 in all modes; it does not include specific plant casualty procedures or systems operations requirements, but- rather provides administrative processes only.

3.1 REFERENCES

USED IN PROCEDURE PREPARATION:

3.1.1 ANO Emergency Plan 3.1.2 ANO's EAL Bases Document 3.1.3 NUREG-0654/FEMA-REP-l, Rev. 1 3.1.4 10 CFR 50 3.1.5 NRC Branch Position on Acceptable Deviations to Appendix 1 to NUREG-0654/FEMA-REP-1, July 11, 1994

- 3.1.6 0CNA080005 - Allow for 1% fuel cladding failure to be determined by radiation dose readings. Step 4.10.1.A.2, 4.10.1.B.2, Attachment 3 EALs 1.2 and 1.3, Attachemnt 4 EALs 1.2 and 1.3, Attachment 7 and 8.

3.1.7 NEI 99 Methodology for Development of Emergency Action Levels,

3.2 REFERENCES

USED IN CONJUNCTION WITH THIS PROCEDURE:

3.2.1 1000.104, "Condition Reporting and Corrective Actions" 3.2.2 1903.011, "Emergency Response/Notifications" 3.2.3 1903.064, "Emergency Response Facility - Control Room" 3.2.4 1903.065, "Emergency Response Facility - Technical Support Center (TSC)"

3.2.5 1903.066, "Emergency Response Facility - Operational Support Center (OSC)"

3.2.6 1903.067, "Emergency Response Facility - Emergency 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" 3.2.10 2202.XXX, "Emergency Operating Procedures"

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 3 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 3.2.11 1404.016, "Post Earthquake Data acquisition and Measurement" 3.2.12 1904.002, "Offsite Dose Projections-RDACS Method" 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 OCAN068320 (P-10766) - Section 4.3 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. PROCEDURENWORK PLAN TITLE: PAGE: 4 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

- . . CHANGE: 037-02-0 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.

fOCAN0683201 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 EOF, 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.

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 5 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 5 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 Claddina 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 1 - Greater than 1% fuel cladding failure as indicated by ANY of the following:

1. Nuclear Chemistry analysis of RCS sample yields >

400 uCi/gm specific I-131.

2. Radiation levels that indicate >1% fuel cladding failure per Unit I Fuel Cladding Failure Radiation Plot (Att 7).

3. Failed Fuel Iodine process monitor (RE 1237S) indicates > 8.2 x 105 CPM.

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 I-131.

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).

PROCJWORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 6 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. . i . CHANGE: 037-02-0 (4.10.1 cont.)  : 4. Engineering assessment of core damage indicates

> 1% fuel cladding failure.

4.10.2 RCS Boundary Failure A. Unit 1 - 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).

PROCJNORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 7 of 130 .

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION .

CHANGE: 037-02-0 (4.11.2 cont.) C. Three out of four seal stages failed on any RCP (U-2).

D. Failure of any component resulting in RCS leakage greater than Tech. Spec. limits and approaching normal make up capacity; (50 gpm) for Unit 1 or (44 gpm) for Unit 2.

4.11.3 Challenge to Containment Building Integrity: any event or condition which in the judgement of the SM/TSC Director/

EOF Director significantly increases the potential for failure of containment integrity; for example:

A. Containment pressure > Reactor Building spray actuation setpoint and increasing with no available RB spray or cooling.

B. Hydrogen concentrations in containment > 3.5%.

C. Occurrence of system or component failure which degrades the capability to maintain containment integrity as defined by Technical Specifications.

4.12 Fuel Overheat - Condition in which fission products trapped within the fuel pellet are released at an accelerated rate due to increasing temperature. Fuel overheating tempertures typically range from 1600 0F to 3600 OF cladding temperature.

4.13 Initial Response Staff (IRS) - The emergency organization composed of plant personnel which must be able to respond to the site in accordance with Table B-1 of the Emergency Plan.

4.14 Normal Makeup (MU) Capacity Unit 1: Normal makeup capacity is defined as 50 gpm. 50 gpm approximates a leak size for which the ability to make additions to the makeup tank is no longer adequate to maintain makeup tank level.

Unit 2: Normal makeup capacity is defined as 44 gpm. 44 gpm is the capacity of a single charging pump.

4.15 Offsite - Those areas not covered by Section 4.13.

4.16 Onsite - The area within the Exclusion Area Boundary.

4.17 Operational Support Center (OSC) - Emergency response center within the ANO Maintenance Facility where support is coordinated for the following functions:

Onsite Radiological Monitoring Maintenance Nuclear Chemistry Emergency Medical Support Fire Fighting Support The OSC also serves as the briefing area for repair and damage control teams and is located in the Maintenance Facility.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 8 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 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 Reactor Coolant System (RCS) Leakage: Loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

4.21 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).

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 9 of 130 .

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 1 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 EAL,

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. PROCEDUREMwORK PLAN TITLE: PAGE: 10 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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. PROCEDURENVORK PLAN TITLE: PAGE: 11 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037-02-0 NOTE Unit 1 EALs - Blue Tabs Unit 2 EALs - Green Tabs 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. PROCEDUREJWORK PLAN TITLE: E: 12 f 130 l 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037402-0 7..0 ATTACHMENTS AND FORMS 7.1 Attachment 1 Unit Index of EALs 7.2 Attachment 2 Unit Index of EALs 7.3 Attachment 3 Unit Emergency Action Levels 7.4 Attachment 4 Unit Emergency Action Levels 7.5 Attachment 5 Unit Containment Radiation EAL Plot 7.6 Attachment 6 Unit Containment Radiation EAL Plot 7.7 Attachment 7 Unit Fuel Cladding Failure Radiation Plot 7.8 Attachment 8 Unit Fuel Cladding Failure Radiation Plot

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 13 of 130 I1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION I . CHANGE: 037.02-0 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 NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

2.0 RCS LEAKAGE 2.1 RCS Leakage ........... 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 ............ ...............

I 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 >l0gpm Concurrent with an On-going Steam Release,or 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

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 14 of 130 I1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 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. -

5.0 RADIOLOGICAL EFFLUENTS 5.1 Radiological Effluents >.05 mRem/hr TEDE or .15 mRem/hr Child Thyroid CDE at Site Boundary or Liquid Radiological Effluents exceed ODCM Limitations ........................... NUE 5.2 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 Loss of Control Room Annunciators . ALERT 6.7 Loss of Control Room Annunciators with Transient in Progress . SAE 6.8 Control Room Evacuation . ALERT 6.9 Control Room Evacuation and control of shutdown systems not established in 15 minutes . SAE 6.10 Loss of Decay Heat Removal Systems . ALERT 6.11 Degraded Hot Shutdown Capability . SAE

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 15 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 1 UNIT 1 INDEX OF EALS NOTE Once available plant parameters reach an Emergency Action Level (EAL),

classifications should be made within 15 mi'nutes.

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 Systems ... 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. PROCEDURENWORK PLAN TITLE: PAGE: 16 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 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.

1.0 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 Overheat ........................................ I............ 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 NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

2.0 RCS LEAKAGE 2.1 RCS Leakage ............................................... 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 >l0gpm 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) .... I...................................... 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

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 17 of 130 1903.010  : EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 ............. o.......... ...NUE 5.2 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 Progress .......... SAE

PROC.NJORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 18 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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.-..

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 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 Systems . .... ALERT 7.7 Fire or Explosion Onsite Affecting Both Trains of ESF Systems ......... 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

PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 19 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

, - ~~~~~~~~~~1.1 J

CONDITION:

RCS Activity indicates >0.1% fuel cladding failure EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

1. Greater than 0.1% fuel cladding failure as indicated by EITHER of the following:

A. Nuclear Chemistry analysis of RCS sample yields >40.0 p

pCi/gm specific I-131 OR B. Failed Fuel Iodine monitor (RE 1237S) indicates >3.3 x 105 CPM RELATED EALS: TAB RCS Activity indicates >1% fuel cladding failure 1 High Radiation / Airborne Levels 5 Initiation of Plant S/D or C/D due to T.S. L.C.O. 6

PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 20 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 03742-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.2 CONDITION

RCS Activity indicates >1% fuel cladding failure EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. 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 I-131 OR

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 105 CPM.

RELATED EALS: TAB RCS Activity indicates >0.1% fuel cladding failure 1 Containment Radiation indicates LOCA and >1% fuel cladding failure 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Damage indicated with an ICC Condition 1 High Radiation/Airborne Levels _

Initiation of Plant S/D or C/D due to T.S. L.C.O. 6

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 21 of 130 I 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.3 CONDITION

[Core Damage Indicated with an Inadequate Core Cooling Condition EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. Inadequate core cooling capacity exists as evidenced by CETS indicating superheated conditions of Region 3 of Figure 4 of EOP 1202.013.

AND

2. 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 I-131 OR

2. Radiation levels that indicate >1% fuel cladding failure per Unit 1 Fuel Cladding Failure Radiation Plot (Att 7)

OR B. Failed Fuel Iodine process monitor (RE 1237S) indicates >8.2 x 105 CPM.

RELATED EALS: TAB Containment Radiation High/Very High 1 Core Melt 1 Loss of or challenge to 3 Fission Product Barriers 1 RCS Leakage 2

PROCJWORK PLAN NO. PROCEDURE1WORK PLAN TITLE: PAGE: 22 of .130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 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

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TLE: - PAGE: 23 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 1 Radiological Effluents' 5 Core Melt

PROCWWORK PLAN NO.- PROCEDURENVORK PLAN TITLE: PAGE: 24 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1.6

]

CONDITION:

Core Melt EMERGENCY CLASSIFICATION:

General Emergency MODES All CRITERIA:

1. 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 1 Radiological Effluents 5

PROCWWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 25 of 130

. 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. . . . CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1.7 EMERGENCY CLASSIFICATION:

General Emergency MODES All CRITERIA:

1. 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 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 1 Radiological Effluents 5 Natural Events 8

PROCJWORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 26 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE

2.1 CONDITION

RCS Leakage ]

EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 CRITERIA:

NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

1. Unidentified or pressure boundary RCS leakage greater than 10 gpm.

OR

2. Identified RCS leakage greater than 25 gpm.

RELATED EALS: TAB RCS Leakage > Normal Makeup Capacity (50 gpm) 2 TS LCO's 6 OTSG Tube Leak 3

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 27 of 130 1903.010 - EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3

- UNIT 1 RCS LEAKAGE

2.2 CONDITION

RCS Leakage > Normal Makeup Capacity (50 gpm)

EMERGENCY CLASSIFICATION:

Alert MODES 1-4 CRITERIA:

NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

1. RCS Leakage is >50 gpm (Batch Controller capacity is exceeded).

RELATED EALS: TAB RCS Leakage > Normal M/U Capacity with Fuel Clad Failure Conditions 2 RCS Leakage > HPI Capacity 2 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

PROCJNORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 28 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE

2.3 CONDITION

RCS Leakage > Normal Makeup Capacity (50 gpm) with >1.0% Fuel Cladding Failure Conditions EMERGENCY CLASSIFICATION:

Site Area Emergency S MODES 1-4 CRITERIA:

NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

1. RCS Leakage is >50 gpm (Batch Controller capacity is exceeded) with >1.0%

Fuel Cladding Failure in the RCS (EAL 1.2)

NOTE EAL 2.2 RCS Leakage > Normal Makeup Capacity (50 gpm)

EAL 1.2 RCS Activity Indicates >1% fuel cladding failure RELATED EALS: TAB Containment Radiation indicates LOCA and fuel failure 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product. Barriers Radiological Effluents 5 Core Melt 1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 29 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE

2.4 CONDITION

RCS Leakage > HPI Capacity EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

NOTE RcS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

1. RCS Leakage > HPI Capacity as indicated by:

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

PROCJWORK PLAN NO. PROCEDURENVORK PLAN TITLE: PAGE: 30 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS

3.1 CONDITION

lUncontrolled OTSG Depressurization Resulting in MSLI Actuation J EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 CRITERIA:

1. Any manual or automatic actuation of MSLI due to uncontrolled OTSG depressurization.

RELATED EALS: TAB OTSG Tube Leak 3 Radiological Effluents ~5

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 31 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.2 CONDITION:.

OTSG Tube Leakage > Tech. Spec. Limits EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 CRITERIA:

1. 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

PROCJWORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 32 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION I CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.3

.EMERGENCY CLASSIFICATION:

Alert MODES 1-4 CRITERIA:

1. RCS Leakrate increase of >10 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 from either or both steam generator(s) indicated by:

1. Main Steam Safety Valve(s) maintaining OTSG pressure (other than for normal post trip response)

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 5 Electrical Power Failures 4 Loss of or Challenge to 3 Fission Product Barriers 1

PROCJWORKPLAN NO. PROCEDUREWORK PLAN TITLE: PAGE: 33 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 1-4 CRITERIA:

1. OTSG Tube Rupture as indicated by BOTH of the following:

A. RCS Leakage > Normal Makeup Capacity (50 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 from either or both steam generators) indicated by:

1. Main Steam Safety Valve(s) maintaining OTSG pressure (other than for normal post trip response)

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: 037-02-0 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:

Site Area Emergency MODES 1-4 CRITERIA:

1. 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 from either or both steam generator(s) indicated by:

1. Main Steam Safety Valve(s) maintaining OTSG pressure (other than for normal post trip response)

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:

I ~~~~~~~CAUTION If RCS leakage is > 50 gpm, EAL 1.7 will apply. If RCS leakage is degrading and approaching 50 gpm consider EAL 1.7.

TAB RCS Leakage 2 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 Electrical Power Failures 4

PROCJWORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 35 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.1 CONDITION

Degraded Power EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

1. 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 (H1, 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: 037-02-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES 4.2 J

CONDITION:

Station Blackout EMERGENCY CLASSIFICATION:

Alert MODES All I CRITERIA:

1. All 4160V buses de-energized.

RELATED EALS: TAB lBlackout more than 15 minutes l 4l Loss of Control Room Annunciators 6

PROCJWORK PLAN NO. PROCEDUREM'ORK PLAN TITLE: PAGE: 37 of 130a 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.3 CONDITION

[Blackout for more than 15 minutes.

EMERGENCY CLASSIFICATION:

.Site Area Emergency MODES All CRITERIA:

1. 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 I1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 38 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.4 CONDITION

Loss of All Vital DC Power EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. Loss of voltage on ALL of the following busses A. D01 and D02 B. RAI and RA2 C. D1l 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. PROCEDUREMORK PLAN TITLE: PAGE: 39 of 130 .

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.0240 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 B. RAl and RA2 C. Dll 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. PROCEDURENVORK PLAN TITLE: PAGE: 40 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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:

Notification of Unusual Event 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 0.05 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: TAB Radiological Effluents 5 High Radiation/Airborne Levels -5 OTSG Tube Leak 3

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 41 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

_ CHANGE: 037-02-0 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:

1. 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:

Radiological EffluentsI OTSG Tube Leak Containment Radiation High

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 42 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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.

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. 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 1 Core Melt- 1

PROCJWORK PLAN NO. PROCEDURENVORK PLAN TITLE: PAGE: 43 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION l CHANGE: 037-02-0 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:

General Emergency MODES All CRITERIA:

1. 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 mremfhr Child Thyroid CDE.

RELATED EALS: TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation High / Very High 1

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TLE: PAGE: 44 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS

5.5 CONDITION

High Radiation/Airborne Levels EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. The loss of control of radioactive material results in ANY of the following:

A. Containment radiation indicates >2R/hr B. 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

PROCWWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 45 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. . CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS

5.6 CONDITION

[Spent Fuel Accident EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. 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 Rfhr on Area Radiation Monitors or 10 Rem/hr HP Survey Report.

RELATED EALS: TAB Radiological Effluents .5 High Radiation/Airborne Levels 5 Miscellaneous Events 9

PROCWWORK PLAN NO. PROCEDUREJWORK PLAN ITLE: PAGE: 46 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 10CFR50.54(x)

EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 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 1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 47 of 130 l 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

- CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.2 CONDITION

Reactor Protection System Failure to Complete an Automatic Trip EMERGENCY CLASSIFICATION:

Alert MODES 1-2 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. DSS trip or 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. PROCEDUREIWORK PLAN TITLE: PAGE: 48 of 130 1903.010  : EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 1-2 CRITERIA:

1. A valid RPS trip setpoint is exceeded on ANY TWO RPS channels and the RPS or DSS 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: TAB Loss of or Challenge to 3 Fission.Product Boundaries 1 Core Melt 1 Core Damage Indicated with an ICC Condition 1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 49 of .130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037-02-0 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 />.

OR

2. Reactor Building Purge System or Penetration Ventilation System is not isolable, and the applicable SPING is inoperable.

OR

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. PROCEDUREI'NORK PLAN TITLE: PAGE. 50 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.024 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.5 CONDITION

Loss of Communications 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 RELATED EALS: TAB lNone..ll

PROCJWORK PLAN NO. PROCEDURESWORK PLAN TITLE: PAGE: 51 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 Loss of Control Room Annunicators with Transient in Progress 6

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 52 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.7 CONDITION

Loss of Control Room Annunciators with Transient in Progress EMERGENCY CLASSIFICATION:

[Site Area Emergency MODES All 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.)

RELATED EALS: TAB None ]

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 53 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 any ES Systems 7

PROCJWORK PLANNO. PROCEDURE/WORK PLAN TITLE: PAGE: 54 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.9

[

CONDITION:

Control Room Evacuation and control of shutdown systems not established in 15 minutes.

EMERGENCY CLASSIFICATION:

Site Area Emergency S MODES All CRITERIA:

. 1. Control Room evacuation has occurred AND control of shutdown systems is not established from local stations within 15 minutes.

RELATED EALS: TAB Core Damage Indicated with an ICC Condition 1 Loss of Decay Heat Removal Systems 6 Core Melt 1

PROCJWORK PLAN NO. PROCEDUREMWORK PLAN TITLE: PAGE: 55 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037-02-0 I

ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.10 EMERGENCY CLASSIFICATION:

Alert MODES 5-6 CRITERIA:

1. 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: 037.02-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.11 CONDITION:

.Degraded Hot Shutdown Capability EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 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 I 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: 037-02-0 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 plant buildings 7

I

PROCRJORK PLAN NO. PROCEDUREIWORK PLAN TILE: PAGE: 58 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037402-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.2 CONDITION

Ongoing security threat within the Protected Area Security Fence but outside of plant buildings

,EMERGENCY CLASSIFICATION:

Alert MODES All RELATED EALS: TAB Ongoi~ng security threat within plant buildings but not in Control 7 Room or vital areas.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 59 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.3 CONDITION

lOngoing security threat within plant buildings but not within the Control Room or vital areas EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

Same as the Condition stated above.

RELATED EALS: TAB Ongoing security Threat within Control Room or Vital Areas 7

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 60 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 03742-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.4 CONDITION

Ongoing security threat within the Control Room or vital areas EMERGENCY CLASSIFICATION:

General Emergency MODES All CRITERIA:

Same as the Condition stated above.

RELATED EALS: TAB None

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 61 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.5 CONDITION

.Fire or Explosion Onsite EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

1. Fire within the Protected Area Security Fence which is not extinguished within 10 minutes.

OR

2. Explosion causing facility damage.

RELATED EALS: TAB (Fire or Explosion Onsite Affecting One Train of an ES System 7

PROCJWORK PLAN NO. PROCEDUREMNORK PLAN TITLE: PAGE: 62 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.6-CONDITION:

Fire or Explosion Onsite Affecting One Train of ANY ES Systems EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. 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. PROCEDUREMWORK PLAN TITLE: PAGE: 63 of 130 .

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.7 CONDITION

Fire or Explosion Onsite Affecting Both Trains of ANY ES Systems 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 l 6 established in 15 minutes

PROCJWORK PLAN NO. PROCEDURENVORK PLAN TrTLE: PAGE: 64 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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 Train 7 of ANY ES System

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 65 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 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

PROCJNORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 66 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.10 CONDITION:

Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ANY ES System 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

2. A potential OR actual loss of BOTH trains of ANY ES system RELATED EALS:- TAB Fire or Explosion Onsite Affecting Both Trains of an ES System 7

PROCJWORK PLAN NO. PROCEDUREJNORK PLAN TILE: PAGE: 67 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 3 UNIT 1 NATURAL EVENTS

8.1 CONDITION

Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake 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 >340' 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, Earthquake 8 j

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TffLE: PAGE: 68 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 NATURAL EVENTS

8.2 CONDITION

'Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake J 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 .lg alarm.

or Any natural event resulting in the potential or actual loss of ONE train of ANY ES system.

RELATED EALS: TAB Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake -8 Loss of or challenge to all 3 Fission Product Barriers

ATTACHMENT 3 UNIT 1 NATURAL EVENTS 8.3 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 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.

RELATED EALS: TAB Loss of or challenge to all 3 Fission Product Barriers.

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1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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:

Notification of Unusual Event MODES All 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.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 71 of 130

. 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. . . CHANGE: 037-02-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS

9.2 CONDITION

Other plant conditions exist that warrant precautionary activation of the Technical Support Center and placing the near-site Emergency Operations Facility and other key emergency personnel on standby.

EMERGENCY CLASSIFICATION:

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.

OR Plant conditions exist that warrant activation of the Emergency Response Organization.

[

RELATED EALS:

Plant Conditions Exist that Warrant Activation of the Emergency Response Centers.

TAB 9

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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.

EMERGENCY CLASSIFICATION:

Site Area Emergency-..

MODES All-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 9 Radioactivity Possible

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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.

RELATED EALS: TAB None

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1.1 CONDITION

[RCS Activity indicates >0.1% fuel cladding failure l EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-5 CRITERIA:

1. Greater than 0.1% fuel cladding failure as indicated by EITHER of the following:

A. Selected isotope activity (1-131) >5.5E 5 CPM (2RR4806 on 2C14 or 2RITS 4806B on 2C22)

B. Specific I-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

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- UNIT 2 PRIMARY SYSTEM EVENTS

1.2 CONDITION

[RCS Activity indicates >1.0% fuel cladding failure EMERGENCY CLASSIFICATION:

Alert MODES 1-5 CRITERIA:

1. Greater than 1% fuel cladding failure as indicated by either of the following:

1. RCS Sample Analysis >378 pCi/gm specific I-131 OR

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: 037-02-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.3 CONDITION

Core Damage Indicated with an Inadequate Core Cooling Condition EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-5 CRITERIA:

1. Greater than 1% fuel cladding failure as indicated by either of the following:

1. RCS Sample Analysis >378 pCi/gm specific I-131 OR

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'F superheat AND RVLMS LVL 7 or Lower indicates Dry.

B. Th RTD and average CET temperature indicates >100F superheat with both RVLMS Channels inoperable AND RCS temperatures increasing.

C. CET Temperatures indicate greater than 700'F.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 77 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 I^

ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.4 CONDITION

IContainment Radiation readings which indicate 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 6)

AND

2. LOCA occurring within the Containment Building

.RELATEDEALS: TAB Containment Radiation 1 Loss of or challenge to 3 Fission Product Barriers 1 Radiological Effluents 5 Core Melt 1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 78 of 130 :

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 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 6)

AND

2. LOCA occurring within the Containment Building RELATED EALS: TAB Loss of or challenge to 3 Fission Product.Barriers Radiological Effluents 5 Core Melt

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 79 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS 1.6 CONDITION:

Core Melt with Containment Integrity Lost or Challenged ]

EMERGENCY CLASSIFICATION:

General Emergency M

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. PROCEDUREIWORK PLAN TITLE: PAGE: 80 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037.02-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS 1.7 EMERGENCY CLASSIFICATION:

General Emergency MODES All CRITERIA:

1. 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 PLANNO. PROCEDUREINORK PLAN TITLE: PAGE: 81 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 RCS LEAKAGE

2.1 CONDITION

RCS Leakage EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 CRITERIA:

NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

1. Unidentified or pressure boundary RCS leakage greater than 10 gpm.

OR

2. Identified RCS leakage greater than 25 gpm.

RELATED EALS: TAB RCS Leakage 2 T.S. L.C.O.'s 6 Primary to Secondary Leakage 3 General Area Radiation/Airborne 5

9 PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 82 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-024 ATTACHMENT 4 UNIT 2 RCS LEAKAGE 2.2 EMERGENCY CLASSIFICATION:

Alert MODES 1-4 CRITERIA:

NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.-

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. PROCEDUREIWORK PLAN TITLE: PAGE: 83 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 4

- UNIT 2 RCS LEAKAGE 2.3 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

1NOTE RCS leakage is defined as a loss of RCS inventory due to a leak in the RCS or a supporting system that is not or cannot be isolated within 10 minutes.

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 >100 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 700°F.

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. PROCEDUREJWORK PLAN TITLE: PAGE: 84 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS

3.1 CONDITION

Uncontrolled S/G Depressurization Resulting in MSIS Actuation 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: 037.02-0 ATTACHMENT 4-UNIT 2 SECONDARY SYSTEM EVENTS

3.2 CONDITION

S/G Tube Leak > Tech Spec Limits EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 CRITERIA:

1. 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. PROCEDUREIWORK PLAN TITLE: . PAGE: 86 of 130 j 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION ATTACHMENT 4 UNIT 2 CHANGE: 037-02-0 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 from either or both steam generators 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: 037-02-0 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).

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

1. S/G tube leak >44 gpm with a Steam Release in Progress from either or both steam generator(s) 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 pCi/gm (T.S. 3.4.8), but < 378 pCi/gm (1% fuel cladding failure).

RELATED EALS:

CAUTwION If fuel cladding failure is > 1% (> 378 pCi/gm I-131), EAL 1.7 will apply.

If fuel cladding is degrading and failure approaches 1% (378 pCi/gm I-131),

consider EAL 1.7.-

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. PROCEDUREIWORK PLAN TITLE: PAGE: 88 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.1

- CONDITION:

Degraded Power EMERGENCY CLASSIFICATION:

[Notification of Unusual Event MODES All Modes CRITERIA:

1. Temporary Loss of Normal Control Room Lighting

• AND

2. No voltage indicated on Both 4.16 KV nonvital busses (2A1 & 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

I PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 89 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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: 037.02-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.3 EMERGENCY CLASSIFICATION:

Alert MODES 1-4 CRITERIA:

1. Loss of All of the following busses has occurred:

A. 2D01 and 2D02 B. 2RAI and 2RA2 C. 2D21 and 2D23 D. 2D22 and 2D24 RELATED EALS: TAB Electrical Power 4 Communications, Dose Assessment 6

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 91 of 130 1903.010  : EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4

- UNIT 2 ELECTRICAL POWER FAILURES 4.4 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. Blackout has occurred as indicated by ALL of the following:

A. Loss of all Control Room lighting except emergency DC lights B. No voltage indicated on Both 4.16 KV nonvital busses (2A1 and 2A2)

C. Neither Vital 4.16 KV Buss energized (2A3 or 2A4)

AND

2. The Blackout Condition exists for >15 minutes RELATED EALS: TAB Decay Heat Removal 6 Electrical Power 4 Primary to Secondary Leakage 3 Core Melt 1 Radiological Effluents 5

I PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 92 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.5 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. Loss of both of the following trains of DC Busses has occurred:

RED TRAIN GREEN TRAIN 2D01 2D02 2RA1 2RA2 2D21 2D22 2D23 2D24 AND-

2. Power is not restored to at least one train within 15 minutes RELATED EALS: TAB Communications, Dose Assessment .6 Decay Heat Removal 6 Core Melt 1 Radiological Effluents 5

PROCJWORK PLAN NO. PROCEDUREINORK PLAN WTLE: PAGE: 93 of 130 1903.010  : EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 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:

Notification of Unusual Event 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 0.05 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: TAB Radiological Effluents 5 General Area Radiation/Airborne 5 Primary to Secondary Leak 3

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 94 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 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:

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

PROCWWORK PLANNO. PROCEDURE/NORK PLAN TITLE: PAGE: 95 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 4 UNIT 2 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.

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. 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 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt 1

PROCJWORK PLAN NO. PROCEDUREINORK PLAN TITLE: PAGE: 96 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037.02-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.4 CONDITION

I

.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:

1. 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

PROCWNORKPLANNO. PROCEDUREWORKPLAN TITLE: PAGE: 97 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.5 CONDITION

lHigh Radiation/Airborne Levels ]

EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. The loss of control of radioactive material results in ANY of the following:

A. Containment radiation indicates >2R/hr B. 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 boundaries.

(For Example: Spent resin spill, RCS liquid spill, Spent fuel accident resulting in gaseous release, etc.)

RELATED EALS: TAB Radiological Effluents 5 Containment Radiation 1 Spent Fuel Damage 5 RCS Leakage 2

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 98 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS 5.6 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. 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 by Area Radiation Monitors or 10 Rem/hr HP survey report.

RELATED EALS: TAB Radiological Effluents 5 General Area Radiation/Airborne 5 Miscellaneous 9

PROCJWORK PLANNO. PROCEDURENWORK PLAN TITLE: PAGE: 99 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.1 CONDITION

Deviation from T.S. action statements when required to shutdown or cooldown or deviations pursuant to 10CFR50.54(x)

EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4

• 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 Primary to Secondary Leakage 3 RCS Activity 1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 100 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.2 EMERGENCY CLASSIFICATION: .

Alert MODES 1-2 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 .1 Core Damage/ICC 1

PROCJWORK PLAN NO. PROCEDURENVORK PLAN TITLE: PAGE: 101 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.3 CONDITION

,Reactor Protection System Failure to Complete a Manual Trip EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-2 CRITERIA:

1. A valid RPS trip setpoint is exceeded AND

2. Ten (10) or more CEAs fail to insert after the RPS, DSS and manual trip (Example: 2B7 & 2B8 feeder breakers opened to insert CEAs due to a failure of automatic and manual RPS trips.)

RELATED EALS: TAB Loss of or Challenge to 3 Fission Product Barriers.

Core Melt Core Damage/ICC l

PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 102 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 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 B. Compacting is in progress 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 />.

OR

2. Reactor Building Purge penetration is not isolable and both the applicable SPING and the Process Radiation Monitor are inoperable.

OR

3. All of the following conditions exist for any source of gaseous effluents in the Auxiliary Building, Auxiliary Extension Building, or Spent Fuel Storage Building ventilation systems.

A. Applicable SPING is inoperable B. Applicable Process Radiation Monitor is inoperable 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 />.

RELATED EALS: TAB

[Communications, Dose Assessment 6 j

-PROCJWORKPLANNO. PROCEDUREIWORKPLAN TITLE: PAGE: 103 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.5 CONDITION

Loss of Communications ]

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 RELATED EALS: TAB None:l

PROCJWORK PLAN NO. PROCEDURE/NORK PLAN TITLE: PAGE: 104 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.6 CONDITION

Control Room Evacuation EMERGENCY CLASSIFICATION:

Alert MODES All RELATED EALS: TAB lControl Room Evacuation l 6 l

PROCANORK PLAN NO. PROCEDURErwORK PLAN TITLE: PAGE: 105 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.7 CONDITION

Control Room Evacuation and control of shutdown systems not established in 15 minutes.

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:-

1. Control Room evacuation has occurred AND control of shutdown systems is not established from local stations within 15 minutes.

RELATED EALS: TAB Core Damage/ICC 1 Decay Heat Removal 6 Core Melt1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 106 of 130 I1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.8 EMERGENCY CLASSIFICATION:

Alert MODES 5-6 CRITERIA:

1. Loss of Decay Heat Removal capabilities shall be identified as ANY of the following:

A. RCS indicates saturated conditions B. Loss of both shutdown cooling trains for >1 hr and S/G's not available for decay heat removal (NA if Fuel Transfer Canal >23 ft)

C. HPSI injection required for cooling the core RELATED EALS: TAB Spent Fuel Accident 5 Core Damage/ICC 1 Radiological Effluents 5 Loss of or Challenge to 3 Fission Product Barriers 1 High Radiation/Airborne 5 Core Melt 1

PROCJNORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 107 of 130

. 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. . CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.9 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

1. ALL of the following conditions exist:

A. S/G level in BOTH S/Gs is <70" AND B. ECCS Vent System is utilized RELATED EALS: TAB Containment Radiation 1 RCS Leakage 2 Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1

PROCJWORK PLAN NO. PROCEDURENWORK PLAN TITLE: PAGE: 108 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. CHANGE: 037-024 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.10 CONDITION:

Loss of Control Room Annunciators EMERGENCY CLASSIFICATION:

Alert MODES ALL CRITERIA:

1. Loss of BOTH AC and DC power to 9 or more of the Control Room Annunciator Panels.

RELATED EALS: TAB Loss of Control Room Annunciators with a Transient in progress 6 Electrical Power 4

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 109 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.11 CONDITION:.

Loss of Control Room Annunciators with a Transient in Progress EMERGENCY CLASSIFICATION:

Site Area Emergency MODES ALL CRITERIA:

1.. Loss of BOTH AC and DC power to 9 or more of the Control Room Annunciator Panels.

AND

2. A plant transient is initiated OR in progress. (See Section 4.18 of this procedure for the definition of a Plant Transient).

RELATED EALS: TAB Electrical Power 4

PROCJWORK PLAN NO. PROCEDUREMORK PLAN TITLE: PAGE: 110 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. . CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 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 Security Threat 7

-PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 111 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.2 CONDITION

Ongoing security threat within the Protected Area Security Fence but outside of plant buildings.

EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

Same as the Condition stated above.

RELATED EALS: TAB Security Threat 7 Fire or Explosion 7

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 112 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.3 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All RELATED EALS: TAB Security Threat -

Fire/Explosion -7

PROCJWORKPLANNO. PROCEDUREIWORKPLAN TITLE: PAGE: 113 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.4 EMERGENCY CLASSIFICATION:

'General Emergency MODES All CRITERIA:

Same as the Condition stated above.

RELATED EALS: TAB None

PROCJWORK PLAN NO. PROCEDURENVORK PLAN TITLE: PAGE: 114 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION X  ; CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.5 CONDITION:.

Fire or Explosion Onsite EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES. All CRITERIA:

1. Fire within the Protected Area Security Fence which is not extinguished within 10 minutes.

OR

2. Explosion causing facility damage.

RELATED EALS: TAB Fire or Explosion Security Threat 7

7 I

PROCJWORK PLAN NO. PROCEDURENIORK PLAN TITLE: PAGE: 115 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.6 CONDITION

Fire or Explosion Onsite affecting One Train of ESF Systems J EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. Fire or explosion onsite AND

2. A potential or actual loss of a single train of ANY ESF system as a result of the fire or explosion.

RELATED EALS: TAB Fire or Explosion 7 Communications, Dose Assessment 6 Control Room Evacuation 6

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 116 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.7 CONDITION

Fire or Explosion Onsite affecting Both Trains of ESF Systems 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 ESF system as a result of the fire or explosion.

RELATED EALS: TAB Communications, Dose Assessment 6 Control Room Evacuation 6

PROCJWORKPLANNO. PROCEDURE/WORKPLAN TITLE: PAGE: 117 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037.02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.8 CONDITION

Aircraft Crash, Unusual Aircraft Activity, Train Derailment, Turbine failure, Toxic or Flammable Gas 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 7 Security Threat 7 MSIS 3 Other Hazards 7

PROCJWORK PLAN NO. PROCEDUREINORK PLAN TITLE: PAGE: 118 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.9 CONDITION

. Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ESF 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 ESF system RELATED EALS: TAB Fire or Explosion 7 Other Hazards 7

PROCJWORK PLAN NO. PROCEDUREINORK PLAN TITLE: PAGE: 119 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.10 CONDITION:

Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Redundant ESF Trains 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

2. A potential OR actual loss of BOTH trains of ANY ESF system RELATED EALS: TAB Fire or Explosion 7

.PROC.NORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 120 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 NATURAL EVENTS

8.1 CONDITION

Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake 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 >340' elev. and rising with forecasted lake level

>350' elev.

C. Low Level - Lake level <337' AND forecasted by U.S. Army Corp of Engineers to reach 335' D. Earthquake - VERIFIED earthquake accompanied by .0lg alarm.

RELATED EALS: TAB Natural Events 8

PROCJWORK PLAN NO. PROCEDUREINORK PLAN TITLE: PAGE: 121 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 NATURAL EVENTS

8.2 CONDITION

Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake 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 >72 mph (10 minute average as reported by RDACS from either the 10 or 57 meter instruments).

C. Flood - Flood waters >350' and are forecasted by U.S. Army Corp of Engineers to reach or exceed 354' D. Low Level - Lake level <335' elevation E. Earthquake - VERIFIED. Earthquake accompanied by .lg alarm.

OR Any natural event resulting in the potential or actual loss of ONE train of ANY ES system RELATED EALS: TAB Natural Events 8 Loss of or challenge to all 3 Fission Product Barriers 1

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 122 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4

'UNIT 2 NATURAL EVENTS

8.3 CONDITION

Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, Earthquake EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

1. ANY of the following A. High Winds - Sustained winds of >80 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 ESF system.

RELATED EALS: TAB LOSS of or challenge to all 3 Fission Product Barriers 1

123 of 130 I

PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE:

1903.010 EMERdENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02.0

'I a

ATTACHMENT 4 UNIT 2 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:

Notification of Unusual Event MODES All 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 RCS Activity 1 RCS Leakage 2 Primary to Secondary Leak 3 Radiological Effluents 5 T.S. L.C.O.'s 6 Loss of Indications/Communications/Dose Assessment 6

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 124 of 130

. 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037402-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS

9.2 CONDITION

Other plant conditions exist that warrant precautionary activation of the Technical Support Center and placing the near-site Emergency Operations Facility and other key emergency personnel on standby.

EMERGENCY CLASSIFICATION:

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

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 125 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS

9.3 CONDITION

Other plant conditions exist that warrant activation of emergency response facilities and monitoring teams or a precautionary notification to the public near the site.

EMERGENCY CLASSIFICATION:

FSite Area Emergency MODES All CRITERIA:

The following conditions must exist

1. 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 RELATED EALS: TAB Core Damage/ICC 1 Containment Radiation 1 Decay Heat Removal -6 Radiological Effluents 5 RCS Leakage 2 Primary to Secondary Leak 3

PROCJWORK PLAN NO. PROCEDUREIMORK PLAN TITLE: V PAGE: 126 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

.I . CHANGE: 037-02-0 ATTACHMENT 4

- UNIT 2 MISCELLANEOUS EVENTS 9.4 CONDITION:.

lPlant 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.

RELATED EALS:. TAB Core Melt 1 Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 1 Radiological Effluents 5

PROCWORK PLAN NO. PROCEDUREMWORK PLAN 1TILE: PAGE: 127 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 037-02-0 ATTACHMENT 5 UNIT 1 CONTAINMENT RADIATION EAL PLOT

_;EeS 2 -

- - l. - l - l l l l I.

N 4'

2 GEIONERAL 4 r- nj 2I _ _ _ _ _ _ -EMERGENCY 4

2 1E4024 l~~~oSSX _ _ _ _ _ _____~~~~~~~~~~~fl 21 AREA D 2 4 ib 1 l2 14 i6 f1 'O 22 2I TIiE INHOUR

\-tI INSTRUCTIONS U

I CAUTION

• In the absence of a significant containment temperature transient, monitor readings should be considered valid.

In the event of a significant containment temperature transient, monitor readings may be erratic for a short duration (Ref.IN-97-45, Supplement 1)

A. Determine the containment radiation level.

1. If the plant has been operating at 100% for the past 30 days, use the reading from RE-8060 or RE-8061.

2. If the plant has been operating at less than 100% power for the past 30 days, determine the radiaiton level as follows:

Rad level = Reading from RE-8060 or RE-806 1 X 100%

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.

1. SITE AREA EMERGENCY - intersection is between the two curves

2. GENERAL EMERGENCY - intersection is above the upper curve

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 128 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION

. A 6 CHANGE: 037-02-0 ATTACHMENT 6

- UNIT 2 CONTAINMENT RADIATION EAL PLOT tI 2

I E+0S4ll GENERAL EMERGENCY 2

RAHR I Ee04 4Eo1 2 { l l l l 2s1'1 11111 -

I V M SITE 2 AREA 1 E.0D EMERGENCY b 2 4 10 12 14 1i IB 20 22 AI TIME INHOUR INSTRUCTIONS CAUTION

• In the absence of a significant containment temperature transient,

. . monitor readings should be considered valid.

In the event of a significant containment temperature transient, monitor readings may be erratic for a short duration (Ref.IN-97-45, Supplement 1)

A. Determine the containment radiation level.

1. If the plant has been operating at 100% for the past 30 days, use the reading from 2RY-8925-1 or 2RY-8925-2.

2. If the plant has been operating at less than 100% power for the past 30 days, determine the radiaiton level as follows:

Rad level = Reading from 2RY-8925-1 or 2RY-8925-2 X 100%

I I estimated I~~~~~~~ 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.

1. SITE AREA EMERGENCY - intersection is between the two curves

2. GENERAL EMERGENCY - intersection is above the upper curve

Attachment 7 (oCNAOS0o).

Unit 1 Fuel Cladding Failure Radiation Plot mRemlhr at SA-229 NOTE: If RX is critical, use Time 0 2000- __.

1500

@ 1000-CX n 500 -.

• 0 0 0.5 1 3 6 12 24 48 96 192 Time (hours since shutdown, if RX is critical, use Time 0) l- -5% Fuel Cladding Failure - - 1% Fuel Cladding Failure Instructions for obtaining the dose rates resides in the Chemistry sample procedure. This procedure partially fullfills T.S. 5.5.3

(  ::C: ...- (:

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN 1TTLE: - PAGE: 130 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION -

-  :  : . CHANGE: 037-020 .

Attachment 8 (OCNAosooo5)

Unit 2 Fuel Cladding Failure Radiation Plot mRem/hr at 2TCD-19 NOTE: If RX is critical, use Time 0 3500 3000 i 2500 2000 1500-1000 500 _

0 -------- ~ ~ ~ ~ a -

0 0.5 1 3 6 12 24 48 96 192 Time (hours since shutdown if RX is critical, use Time 0)-

l ~5%

~ Fuel Cladding Failure - - - 1%Fuel Cladding Failurel Instructions for obtaining the dose rate resides in the Chemistry sampling procedure