ML021330545

Transmittal of OP-1903.010, Revision No. 036-05-0, Change No. PC-05 to Emergency Action Level Classification.

ML021330545
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/02/2002
From:	Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML021330545 (134)

Text

Arkansas Nuclear One - Administrative Services Document Control Thursday, May 02, 2002 Document Update Notification COPYHOLDER NO: 103 TO: NRC - WASHINGTON ADDRESS: OS-DOC CNTRL DESK MAIL STOP OPI 17 WASHINGTON DC 20555-DC DOCUMENTNO: OP-1903.010 TITLE: EMERGENCY ACTION LEVEL CLASSIFICATION REVISION NO: 036-05-0 CHANGE NO: PC-05 SUBJECT.- PERMANENT CHANGE (PC)

F 4 If this box is checked, please sign, date, and return within 5 days.

El ANO-] Docket 50-313 SThis ANO-2 Docket 50-368 Signature Date SIGNATURE CONFIRMS UPDATE HAS BEEN MADE RETURN TO:

ATTN: DOCUMENT CONTROL ARKANSAS NUCLEAR ONE 1448 SR 333 RUSSELLVILLE, AR 72801 V \OVN

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

CLASSIFICATION 1903.010 036-05-0 WORK PLAN EXP. DATE TC EXP. DATE I N/A N/A SET# )7  %. SAFETY-RELATED IPTE 0YES ONO] []YES 0NO TEMP ALT

__YES ONO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionilnterruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: [FORM NO. CHANGE NO.

VERIFICATION COVER SHEET I1000.006Aj 050-00-0

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE:EMERGENCY ACTION AFFECTED UNIT:

E UNIT 1 0 U TYPE OF CHANGE:

El NEW El REVISION

[] YES ED NO

1. Supersede or replace another procedure?

(If YES, complete 1000.006B for deleted procedure.) (0CAN058107) D3 YES ED NO

2. Alter or delete an existing regulatory commitment?

(IfYES, coordinate with Licensing before implementing.) (0CNA128509)(0CAN049803) 19 YES [ NO 15)

3. Require a 50.59 review per LI-101? (See also 1000.006, Attachment (If 50.59 evaluation, OSRC review required.)

[ YES 0 NO

4. Cause the MTCL to be untrue? (See Step 8.5 for details.)

0CNA128509, OCAN049803)

(If YES, complete 1000.009A) (1CAN108904, OCAN099001, El YES ED NO

5. Create an Intent Change?

(If YES, Standard Approval Process required.) [D YES [0 NO

6. Implement or change IPTE requirements?

(If YES, complete 1000.143Ak OSRC review required.) [D YES 0 NO

7. Implement or change a Temporary Alteration?

(If YES, then OSRC review required.)

Was the Master Electronic File used as the source document?

Interim approval allowed for non-intent changes requiring no 50.59 evaluation that are stopping work in progress.

Standard Approval required for intent changes or changes requiring a 50.59 evaluation.

• Ifchange not required to support work in progress, Department Head must sign.

• • If both units are affected by change, both SRO signatures are required. (SRO signature required for safety related procedures only.)

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE:EMERGENCY ACTION LEVEL 1903.010 036-05-0 CLASSIFICATION PAE1IJ

"]WORK PLAN, EXP. DATE_ PAGE 1 OF-1__

[9PROCEDURE I] ELECTRONIC DOCUMENT TYPE OF CHANGE: LI DELETION LI NEW PC ED TC EJEZ EXP. DATE:______

LI REVISION AFFECTED SECTION: DESCRIPTION OF CHANGE: (For each change made, include sufficient detail to describe (Include step # if reason for the change.)

applicable)

Attachment 3 Deleted "> Tech Specs Limits requiring a plant SID or C/D".

EAL 2.1 page 26 Attachment 4 Deleted ">Tech Specs Limits requiring a plant S/D or C/D".

EAL 2.1 page 81 in the procedure for both Reason: The proposed change involves replacing the current EAL 2.1 number SU5 (see Unit I and Unit 2 and replace it with the approved NUMARC example EALinitiating condition in for the NUMARC 99-01, REV 4). The ANO EALs are overly conservative incorporate the example relation to the NUMARC EALs. Therefore the proposed change will NUMARC EAL.

FORM NO. CHANGE NO.

FORM1TTLE:

1000.006C 050-00-0 DESCRIPTION OF CHANGE

PAGE: I of 130 PROC.NVORK PLAN NO. PROCEDUREINORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

NOTE Specifications (ITS) content in This procedure contains Improved Technica-----

the following format:

[ITS Example Content ITS]

This content is not valid until after the implementation of Improved Technical Specifications.

TABLE OF CONTENTS PAGE NO.

SECTIONPS 2

1.0 Purpose .............................................................

Scop e ............................. . . . . . . . . . . . . . . . . 2 2.0 3.0 References .......................................................... 2 3

4.0 Definitions .........................................................

............................................................ 8 5.0 Responsibility and Authority..

6.0 Instructions .................. .... . . . . . .. . . . .. . . . . . . . . . . . . . . .. .. . . . .. 9 7.0 Attachments and Forms .........

........................ 13 7.1 Attachment 1 - Unit 1 Index of EALs

........................ 16 7.2 Attachment 2 - Unit 2 Index of EALs

............... 19 7.3 Attachment 3 - Unit 1 Emergency Action Levels

............... 74 7.4 Attachment 4 - Unit 2 Emergency Action Levels Radiation EAL Plot ....... 127 7.5 Attachment 5 - Unit 1 Containment Radiation EAL Plot ....... 128 7.6 Attachment 6 - Unit 2 Containment Failure Radiation Plot .129 7.7 Attachment 7 - Unit 1 Fuel Cladding Radiation Plot .130 7.8 Attachment 8 - Unit 2 Fuel Cladding Failure

PAGE: 2 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 1903.010 1.0 PURPOSE for detection and classification of plant This procedure establishes criteria events into the four standard Emergency Classes.

2.0 SCOPE 2 in all modes; it does not This procedure is applicable to Units 1 and operations requirements, procedures or systems include specific plant casualty only.

but rather provides administrative processes

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-1, Rev. 1 3.1.4 10 CFR 50 to Appendix 1 3.1.5 NRC Branch Position on Acceptable Deviations to NUREG-0654/FEMA-REP-1, July 11, 1994

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" 1903.065, "Emergency Response Facility - Technical Support 3.2.4 Center (TSC)"

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

Emergency 3.2.6 1903.067, "Emergency Response Facility -

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" and 3.2.11 1404.016, "Post Earthquake Data acquisition Measurement" 3.2.12 1904.002, "Offsite Dose Projections-RDACS Method"

PAGE: 3 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 of 3.2.13 NRC Position Paper on "Timeliness of Classification 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" WHICH ARE 3.4 REGULATORY CORRESPONDENCE CONTAINING NRC COMMITMENTS HAND MARGIN:

PROCEDURE ARE DENOTED IN LEFT IMPLEMENTED IN THIS 3.4.1 0CAN068320 (P-10766) Section 4.3 3.4.2 OCNA08005 (P-16725) Allow for 1% fuel cladding failure to Step 4.16.1.A.2 be determined by radiation dose readings.

Unit 1 EALs 1.2 and 1.3, Unit 2 EALs 1.2 and 4.16.1.B.2, and 1.3, Attachments 7 and 8.

4.0 DEFINITIONS cladding integrity to the extent that 4.1 Core Damage - A failure of fuel 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.

for its design 4.1.3 A major portion of the core cannot be operated 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 in procedure 1903.11, those constituting an Emergency Class as listed "Emergency Response/Notifications", Section 6.3.

PAGE: 4 of 130 PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

4.3 Emergency Action Level - Alarms, instrument readings or visual sightings that have exceeded pre-determined limits which would the one of categorize the situation into an initiating condition of 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.

General Emergency - Events are in progress or have occurred 4.3.4 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.

{0CAN068320} 4.4 Emergency Direction and Control - Overall direction of facility for the response which must include the non-delegable responsibilities decision to notify and to recommend protective actions to Arkansas for Department of Health personnel and other authorities responsible With activation of the EOF, the EOF offsite emergency measures.

Direction Director typically assumes the responsibility for Emergency The management of on-site facility activities to and Control.

TSC Director in the mitigate accident consequences remains with the Technical Support Center. The Shift Manager retains responsibility for the Control Room and plant systems operation.

response 4.5 Emergency Operations Facility (EOF) - A nearsite emergency approximately 0.65 miles northeast of the reactor facility located 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.

PAGE: 5 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

which is 4.7 Emergency Response Organization (ERO) - The organization the TSC the EOF staff, composed of the Initial Response Staff (IRS), the Team members. It has staff, the OSC staff, and the Emergency for other resources necessary capability to provide manpower and situation.

immediate and long-term response to an emergency Levels - The projected 4.8 EPA Protective Action Guideline (PAG) Exposure from an unplanned dose to reference man, or other defined individual, action a specific protective release of radioactive material at which or 5 Rem recommended (i.e., 1 Rem TEDE to reduce or avoid that dose is Child Thyroid (CDE)).

of 4.9 Exclusion Area: That area surrounding ANO within a minimum radius but outside the protected area 0.65 miles of the reactor buildings, periods of and controlled to the extent necessary by ANO during emergency.

4.10 FISSION PRODUCT BARRIER FAILURE rod 4.10.1 Fuel Cladding Failure - Condition where the fuel cannot contain the fission cladding becomes defective and between the fuel pellet and the gases that have accumulated (commonly referred to as the gap).

fuel rod cladding 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 1-131.

{OCNA08005} 2. Radiation levels that indicate >1% fuel cladding failure per Unit 1 Fuel Cladding Failure Radiation Plot (Att 7).

3. Failed Fuel Iodine process monitor (RE 1237S) indicates > 8.2 x l05 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 1-131.

{OCNA08005} 2. Radiation levels that indicate >1% fuel cladding failure per Unit 2 Fuel Cladding Failure Radiation Plot (Att 8).]

3. Containment Radiation Levels correspond to a Site Area Emergency from Containment Radiation EAL Plot (Attachment 6).

PAGE: 6 of 130 PROC./WORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 (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).

of B. Unit 2 - RCS leakage greater than 44 gpm (capacity 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 of 8925-1 or 2RY-8925-2 for Unit 2) and indications 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 which in 4.11.1 Challenge to Fuel Cladding: any event or condition Director presents the judgement of the SM/TSC Director/EOF failure; the potential for greater than 1% fuel cladding 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) which, in 4.11.2 Challenge to RCS Boundary: any event or condition Director could the judgement of the SM/TSC Director/EOF of normal makeup capacity result in RCS leakage in excess for (i.e., 50 gpm for Unit 1 or 44 gpm for Unit 2);

example:

A. RCS pressure > 2450 psig and not decreasing.

B. Two out of three seal stages failed on any RCP (U-l).

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

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 (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.

or 4.11.3 Challenge to Containment Building Integrity: any event 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 RB actuation setpoint and increasing with no available 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.

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

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

defined as the 4.14 Normal Makeup (MU) Capacity - Normal MU capacity is water addition to the RCS through the MU line with maximum expected RC pressure.

This amount will vary with the letdown line isolated.

4.15 Offsite - Those areas not covered by Section 4.13.

4.16 Onsite - The area within the Exclusion Area Boundary.

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

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

PAGE: 8 of 130 PROC.JWORK PLAN NO. PROCEDUREJWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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.

or ESF 4.18.3 Any event resulting in an automatic ESAS (Unit 1) initiation (Unit 2) actuation or any event requiring manual likely of these systems where automatic initiation would have occurred.

MWe in 4.18.4 Any turbine-generator power change in excess of 100 minute other than a momentary spike due less than one (1) to a grid disturbance or a manually initiated runback.

4.18.5 Any unplanned main turbine or main feedwater pump turbine (change trip which results in a significant plant transient in excess of 100 MWe).

(i.e., the 4.19 Protected Area: The area encompassed by physical barriers security fence) and to which access is controlled.

the ANO 4.20 Technical Support Center (TSC) - The location within and Administration Building equipped with instrumentation the course communication systems and facilities useful in monitoringof the ANO located in the 3rd Floor of an accident; this center is Administration Building.

5.0 RESPONSIBILITY AND AUTHORITY to the 5.1 The responsibility for event classification is assigned and Control individual with responsibility for Emergency Direction (i.e., The Shift Manager, TSC Director, or EOF Director).

Direction and 5.2 The Control Room Supervisor (CRS) will assume Emergency to assume whenever the SM is not available Control responsibilities and a this responsibility (e.g. the SM becomes incapacitated replacement has not yet arrived).

which warrants an 5.3 Any individual who observes an initiating condition 3 and 4, emergency class declaration, as described in Attachments with current responsibility for shall immediately notify the person Director).

Emergency Direction and Control (i.e. SM/TSC Director/EOF

PAGE: 9 of 130 PROC.IWORK PLAN NO. PROCEDURENWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 6.0 INSTRUCTIONS NOTE tornado's, etc.,

On emergencies that effect both units such as earthquakes, Classification should be the unit with the highest Emergency Action Level the one that is declaring the emergency.

6.1 CLASSIFYING EMERGENCIES:

NOTE that once indications are available to ANO staff NRC guidelines recommend is a reasonable period of that an EAL has been exceeded, a 15 minute goal time for assessing and classifying an emergency.

received by 6.1.1 When indications of abnormal occurrences are Director the Control Room staff, the SM/TSC Director/EOF shall:

or A. Verify the indications of the off-normal event reported sighting.

of B. Ensure that the immediate actions (e.g., use are taken Emergency and Abnormal Operating Procedures) for the safe and proper operation of the plant.

in C. Compare the abnormal conditions with those listed the "Index Of Emergency Action Levels" (Blue Tabs - Unit 1; Green Tabs - Unit 2).

to the D. Turn to the appropriate tab which corresponds 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.

PAGE: 10 of 130 PROC/WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 NOTE not intended to The emergency action levels described in this procedure are abnormal maintenance and/or testing situations where be used during In addition, temperature, pressure, equipment status, etc., is expected.during which it is each EAL contains information on the mode(s) of operation 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 A

undeclared event will provide an acceptable alternative.

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 to procedure, 1903.011, "Emergency Response Notifications",

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.

PAGE: 11 of 130 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 C. Assess the information available from valid indications or reports, compare it to the given EALs.

Obtain concurrence from NRC and State officials that downgrading is appropriate (if their emergency response organizations have been activated as a result of this event). Downgrade to the emergency classification that is indicated.

given D. If the indications or reports do not match the 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".

then 6.2.3 If no emergency classification appears necessary, terminate the emergency per step 6.3.

If the emergency classification is still required, repeat 6.2.4 conditions again steps 6.2.1 through 6.2.3 whenever plant appear to have improved.

6.3 TERMINATING THE EMERGENCY:

following:

6.3.1 Compare the existing plant conditions with the 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.

the B. Non-routine releases of radioactive material to environment are under control or terminated.

C. Any fire, flood, earthquake, or similar emergency condition is controlled or has ceased.

the D. All specified corrective actions have occurred OR 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).

the 6.3.2 If the conditions of 6.3.1 A-F are met, terminate emergency or proceed to the recovery phase.

PAGE: 12 of 130 PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 7.0 ATTACHMENTS AND FORMS 7.1 Attachment 1 - Unit 1 Index of EALs 2 Index of EALs 7.2 Attachment 2 - Unit 1 Emergency Action Levels 7.3 Attachment 3 - Unit 2 Emergency Action Levels 7.4 Attachment 4 - Unit 1 Containment Radiation EAL Plot 7.5 Attachment 5 - Unit 2 Containment Radiation EAL Plot 7.6 Attachment 6 - Unit 1 Fuel Cladding Failure Radiation Plot 7.7 Attachment 7 - Unit 2 Fuel Cladding Failure Radiation Plot 7.8 Attachment 8 - Unit

PAGE: 13 of 130 PROC.IWORK PLAN NO. PROCEDURENWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 1 UNIT 1 INDEX OF EALS NOTE (EAL),

Once available plant parameters reach an Emergency Action Level classifications should be made within 15 minutes.

1.0 PRIMARY SYSTEM EVENTS

........ NUE 1.1 RCS Activity Indicates >0.1% Fuel Cladding Failure ......... ALERT RCS Activity Indicates > 1% Fuel Cladding Failure 1.2 Cooling 1.3 Core Damage Indicated with an Inadequate Core SAE Condition .................................................. >1%

LOCA and 1.4 Containment Radiation Reading which Indicates SAE Fuel Cladding Failure ...................................... and Containment Radiation Reading which Indicates LOCA 1.5 GE

>50% Fuel Overheat ......................................... GE 1.6 Core Melt ..................................................

Fission Product Barriers ..... GE 1.7 Loss of or challenge to all 3 2.0 RCS LEAKAGE 2.1 RCS Leakage > T.S. Limits requiring a plant S/D or C/D ..... NUE Normal Makeup Capacity (50 gpm) .............. ALERT 2.2 RCS Leakage >

Normal Makeup Capacity (50 gpm) with >1.0%

2.3 RCS Leakage > SAE Fuel Cladding Failure Conditions ...........................

HPI Capacity ................................. SAE 2.4 RCS Leakage >

3.0 SECONDARY SYSTEM EVENTS 3.1 Uncontrolled OTSG Depressurization Resulting in MSLI NUE Actuation .... .. ............................................

NUE 3.2 OTSG Tube Leak > Tech Spec limits ..........................

3.3 OTSG Tube Leak 10gpm Concurrent with an On-going Steam ALERT Release,or loss of offsite power ...........................

3.4 OTSG Tube Rupture with Primary to Secondary Leakage >

release Normal Makeup Capacity (50 gpm) with ongoing steam SAE or loss of offsite power ...................................

and 3.5 OTSG Tube Leak >1 gpm with >1% Fuel Cladding Failure SAE on-going Steam Release .....................................

4.0 ELECTRICAL POWER FAILURES NUE 4.1 Degraded Power ............................................. ALERT 4.2 Station Blackout ........................................... SAE 4.3 Blackout for more than 15 minutes .......................... ALERT 4.4 Loss of All Vital DC Power ................................. SAE 4.5 Loss of All Vital DC Power for more than 15 minutes

PAGE: 14 of 130 PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 1 UNIT 1 INDEX OF EALS NOTE Emergency Action Level (EAL),

Once available plant parameters reach an minutes.

classifications should be made within 15 5.0 RADIOLOGICAL EFFLUENTS or .15 mRem/hr 5.1 Radiological Effluents >.05 mRem/hr TEDE Radiological Child Thyroid CDE at Site Boundary or Liquid Limitations .......................... NUE Effluents exceed ODCM or 1.5 mRem/hr 5.2 Radiological Effluents >.5 mRem/hr TEDE Radiological Child Thyroid CDE at Site Boundary or Liquid ODCM Limitations .................. ALERT Effluents exceed 10 times 150 mRem/hr 5.3 Radiological Effluents >50 mRem/hr TEDE or SAE Child Thyroid CDE at the Site Boundary .....................

or 500 mRem/hr 5.4 Radiological Effluents >250 mRem/hr TEDE GE Child Thyroid CDE at the Site Boundary .....................

ALERT 5.5 High Radiation/Airborne Levels ............................. SAE 5.6 Spent Fuel Accident ........................................

6.0 SAFETY SYSTEM FUNCTION required to 6.1 Deviation from T.S. action statements when to shutdown or cooldown or deviations pursuant NUE 10CFR50.54 (x) .............................................. ALERT 6.2 RPS Failure to Complete an Automatic Trip ................... SAE Complete aCapabilities ......................

Manual Trip .......................

6.3 6.4 6

RPS of Dose to Loss Failure Assessment NUE NUE

............... ALERT 6.5 6.6 of Communicationsn..........

Loss of Loss Control Room Annunciators..............................ALR in 6.7 Loss of Control Room Annunciators with Transient SAE Progress ................................................... ALERT 6.8 Control Room Evacuation .................................... systems 6.9 Control Room Evacuation and control of shutdown SAE not established in 15 minutes ..............................

ALERT 6.10 Loss of Decay Heat Removal Systems ......................... SAE 6.11 Degraded Hot Shutdown Capability ............................

PROCEDURE/WORK PLAN TITLE: PAGE: 15 of 130 PROC.IWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 1 UNIT 1 INDEX OF EALS NOTE Level (EAL),

Once available plant parameters reach an Emergency Action classifications should be made within 15 minutes.

7.0 HAZARDS TO STATION OPERATION

... NUE 7.1 Security Threat or Attempted Entry or Attempted Sabotage Ongoing Security Threat within Protected Area Security 7.2 ALERT Fence ......................................................

SAE 7.3 Ongoing Security Threat Within Plant Building ............... GE 7.4 Ongoing Security Threat Within CR or Vital Area NUE 7.5 Fire or Explosion Onsite ...................................

ANY ES 7.6 Fire or Explosion Onsite Affecting One Train of ALERT Systems ....................................................

ANY ES 7.7 Fire or Explosion Onsite Affecting Both Trains of SAE Systems ...................................... ...............

7.8 Aircraft Crash, Unusual Aircraft Activity, Train Gas Derailment, Turbine Failure, Toxic or Flammable NUE Release ....................................................

Gas Affecting 7.9 Aircraft Crash, Missiles, Toxic or Flammable ALERT One Train of ANY ES Systems ................................

Affecting 7.10 Aircraft Crash, Missiles, Toxic or Flammable Gas SAE Both Trains of ANY ES Systems ..............................

8.0 NATURAL EVENTS

... NUE 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake Flood, Loss of Dardanelle Reservoir, 8.2 Tornado, High Winds, ALERT Earthquake . ................................................

8.3 Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, SAE Earthquake .................................................

9.0 MISCELLANEOUS EVENTS 9.1 Plant Conditions Exist Which Require an Increased Local Awareness by Operations Staff and State and/or NUE Authorities ................................................

of the TSC .. ALERT 9.2 Plant Conditions Exist that Warrant Activation that Warrant Activation of the 9.3 Plant Conditions Exist SAE Emergency Response Facilities ..............................

Make Release of Large Amount 9.4 Plant Conditions Exist That GE of Radioactivity Possible ..................................

PAGE: 16 of 130 PROC.[WORK PLAN NO. PROCEDURE[WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 2 UNIT 2 INDEX OF EALS NOTE (EAL),

Once available plant parameters reach an Emergency Action Level classifications should be made within 15 minutes.

1.0 PRIMARY SYSTEM EVENTS NUE 1.1 RCS Activity Indicates >0.1% Fuel Cladding Failure .........

Indicates >1.0% Fuel Cladding Failure ......... ALERT 1.2 RCS Activity Core Damage Indicated with an Inadequate Core Cooling 1.3 SAE Condition ..................................................

Containment Radiation Indicates LOCA and >1% Fuel Cladding 1.4 SAE Failure ....................................................

Containment Radiation Indicates LOCA and >50% Fuel 1.5 GE Overheat ...................................................

Challenged .... GE 1.6 Core Melt with Containment Integrity Lost or Fission Product Barriers ..... GE 1.7 Loss of or challenge to all 3 2.0 RCS LEAKAGE 2.1 RCS Leakage > Tech Spec Limits requiring a Plant S/D or

........................................................ NUE C/D ALERT 2.2 RCS Leakage > 44 gpm .......................................

SAE 2.3 RCS Leakage > 44 gpm with ICC Conditions ...................

3.0 SECONDARY SYSTEM EVENTS 3.1 Uncontrolled S/G Depressurization Resulting in MSIS NUE Actuation ..................................................

NUE 3.2 S/G Tube Leak > Tech. Spec. Limits ......................... ALERT 3.3 S/G Tube Leak >10gpm with an Ongoing Steam Release .........

and 3.4 S/G Tube Rupture >44 gpm With an Ongoing Steam Release RCS Activity > 1.0 pCi/gm, but < 378 ý1ci/gm (1% fuel SAE cladding failure) ..........................................

4.0 ELECTRICAL POWER FAILURES NUE 4.1 Degraded Power .............................................

ALERT 4.2 Station Blackout ...........................................

ALERT 4.3 Loss of All Vital DC ........................................

SAE 4.4 Blackout > 15 minutes ......................................

SAE 4.5 Loss of All Vital DC for > 15 minutes ......................

PAGE: 17 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 2 UNIT 2 INDEX OF EALS NOTE Level (EAL),

Once available plant parameters reach an Emergency Action 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 NUE Effluents exceed ODCM Limitations ..........................

5.2 Radiological Effluents >.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE at Site Boundary or Liquid Radiological ALERT Effluents exceed 10 times ODCM Limitations ..................

5.3 Radiological Effluents >50 mrem/hr TEDE or 150 mrem/hr SAE Child Thyroid CDE at the Site Boundary .....................

5.4 Radiological Effluents >250 mrem/hr TEDE or 500 mrem/hr GE Child Thyroid CDE at the Site Boundary ...................... ALERT 5.5 High Radiation/Airborne Levels ............................. SAE 5.6 Spent Fuel Accident ........................................

6.0 SAFETY SYSTEM FUNCTION to 6.1 Deviation from T.S. action statements when required shutdown or cooldown or deviations pursuant to NUE 10CFR50.54 (X) ..............................................

ALERT 6.2 RPS Failure to Complete an Automatic Trip ...................

SAE 6.3 RPS Failure to Complete a Manual Trip ......................

NUE 6.4 Loss of Dose Assessment Capabilities .......................

NUE 6.5 Loss of Communications .....................................

ALERT 6.6 Control Room Evacuation ....................................

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

ALERT 6.8 Loss of Decay Heat Removal Systems .........................

SAE 6.9 Loss of Both S/Gs as a Heat Removal Method ..................

ALERT 6.10 Loss of Control Room Annunciators ..........................

6.11 Loss of Control Room Annunciators with a Transient in SAE Progress ...................................................

PAGE: 18 of 130 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 2 UNIT 2 INDEX OF EALS NOTE Level (EAL),

Once available plant parameters reach an Emergency Action classifications should be made within 15 minutes.

7.0 HAZARDS TO STATION OPERATION

... NUE 7.1 Security Threat or Attempted Entry or Attempted Sabotage Ongoing Security Threat Within Protected Area Security 7.2 ALERT Fence ......................................................

SAE 7.3 Ongoing Security Threat Within Plant Buildings ..............

GE 7.4 Ongoing Security Threat Within CR or Vital Area ............ NUE 7.5 Fire or Explosion Onsite ...................................

7.6 Fire or Explosion Onsite Affecting One Train of ESF ALERT Systems ....................................................

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

7.8 Aircraft Crash, Unusual Aircraft Activity, Train

........ NUE Derailment, Turbine Failure, Toxic or Flammable Gas Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting 7.9 ALERT One Train of ESF Systems ...................................

7.10 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting SAE Both Trains of ESF Systems .................................

8.0 NATURAL EVENTS

... NUE 8.1 Tornado, Flood, Loss of Dardanelle Reservoir, Earthquake Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, 8.2 ALERT Earthquake .................................................

Tornado, High Winds, Flood, Loss of Dardanelle Reservoir, 8.3 SAE Earthquake .................................................

9.0 MISCELLANEOUS EVENTS 9.1 Plant Conditions Exist Which Require an Increased Awareness by Operations Staff and State and/or Local NUE Authorities ................................................

that Warrant Activation of the TSC .. ALERT 9.2 Plant Conditions Exist Plant Conditions Exist that Warrant Activation of the 9.3 SAE Emergency Response Facility ................................

Plant Conditions Exist That Make Release of Large Amount 9.4 GE of Radioactivity Possible . .................................

PAGE: 19 of 130 PROC.1WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS 1.i CONDITION:

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

Notification of Unusual Event MODES All CRITERIA:

by EITHER of the

1. Greater than 0.1% fuel cladding failure as indicated following:

>40.0 A. Nuclear Chemistry analysis of RCS sample yields

ýiCi/gm specific 1-131 OR B. Failed Fuel Iodine monitor (RE 1237S) indicates >3.3 x 105 CPM TAB RELATED EALS:

1 RCS Activity indicates >1% fuel cladding failure 5 High Radiation / Airborne Levels 6 Initiation of Plant S/D or C/D due to T.S. L.C.O.

PAGE: 20 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.2 CONDITION

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

Alert CRITERIA:

Greater than 1% fuel cladding failure is indicated by Either of the 1.

following:

A. Nuclear Chemistry analysis of RCS sample yields:

1. >400 pCi/gm specific 1-131 OR

{ocNAo8005} 2. Radiation levels that indicate >1% fuel cladding Plot failure per Unit 1 Fuel Cladding Failure Radiation (Att 7)

OR (RE 1237S) indicates >8.2 x 105 CPM.

B. Failed Fuel Iodine monitor TAB RELATED EALS:

1 RCS Activity indicates >0.1% fuel cladding failure

>1% fuel cladding failure 1 Containment Radiation indicates LOCA and 1

Loss of or Challenge to 3 Fission Product Barriers 1 Core Damage indicated with an ICC Condition 5 High Radiation/Airborne Levels 6 Initiation of Plant S/D or C/D due to T.S. L.C.O. I

PAGE: 21 of 130 PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.3 CONDITION

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

Site Area Emergency MODES All CRITERIA:

evidenced by CETS indicating

1. Inadequate core cooling capacity exists as 3 of Figure 4 of EOP 1202.013.

superheated conditions of Region AND Greater than 1% fuel cladding failure is indicated by EITHER of the 2.

following:

A. Nuclear Chemistry analysis of RCS sample yields:

1. >400 pCi/gm specific 1-131 OR failure

{OCNA08005} 2. Radiation levels that indicate >1% fuel cladding Plot (Att 7) per Unit 1 Fuel Cladding Failure Radiation OR (RE 1237S) indicates >8.2 x l05 CPM.

B. Failed Fuel Iodine process monitor TAB RELATED EALS:

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

PAGE: 22 of 130 PROC./WORK PLAN NO. PROCEDUREINORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.4 CONDITION

>1% fuel cladding failure Containment Radiation reading which indicates LOCA and EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

Emergency as

1. Containment Radiation Levels correspond to a Site Area EAL Plot (Att 5)

Determined from the Containment Radiation AND

2. LOCA occurring within the containment building TAB RELATED EALS:

overheat 1 Containment Radiation indicates LOCA and > 50% fuel Fission Product Barriers 1 Loss of or Challenge to 3 1

Core Melt 5

Radiological Effluents

PAGE: 23 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.5 CONDITION

>50% fuel overheat Containment Radiation readings which indicate LOCA and EMERGENCY CLASSIFICATION:

CRITERIA:

Emergency as

1. Containment Radiation Levels correspond to a General Radiation EAL Plot (Att 5) determined from the Containment AND

2. LOCA occurring within the Containment Building RELATED EALS:

Loss of or Challenge to 3 Fission Product Barriers Radiological Effluents Core Melt

~A s4ofl PROCEDURENWORK PLAN TITLE:

S.... "JA *41: d'*n PROC.IWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.6 CONDITION

Core Melt RELATED EALS:

Loss of or Challenge to 3 Fission Product Barriers Containment Radiation High/Very High Radiological Effluents

PAGE: 25 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 PRIMARY SYSTEM EVENTS

1.7 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) 4.11.3)

B. Challenge to Containment Integrity (refer to section TAB RELATED EALS:

containment Radiation High/Very High Core Melt Radiological Effluents Natural Events

PAGE: 26 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE

2.1 CONDITION

RCS Leakage EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES Above CSD CRITERIA:

greater than 10 gpm.

1. Unidentified or pressure boundary RCS leakage OR

2. Identified RCS leakage greater than 25 gpm.

TAB RELATED EALS:

2 RCS Leakage > Normal Makeup Capacity (50 gpm) 6 Initiation of Plant S/D due to TS LCO 3 OTSG Tube Leak

PAGE: 27 of 130 PROC.IWORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE

2.2 CONDITION

RCS Leakage > Normal Makeup Capacity (50 gpm)

CRITERIA:

1. An RCS leak necessitates EITHER of the following:

pump A. Need to open the BWST suction for the operating makeup due to a decreasing makeup tank level.

OR B. Full or partial HPI is needed to maintain the RCS Pressure or Pressurizer Level TAB RELATED EALS:

2 Cladding Failure RCS Leakage > Normal Makeup Capacity with Fuel 2 Conditions 5 RCS Leakage > HPI Capacity 1 Containment Radiation High/Very High 1 Core Damage Indicated with an ICC Condition 5 1

Loss of or Challenge to 3 Fission Product Barriers Radiological Effluents Core Melt

PAGE: 28 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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 MODES Above CSD CRITERIA:

(EAL 2.2) with >1.0%

1. RCS Leakage > Normal Makeup Capacity (50 gpm)

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 TAB RELATED EALS:

1 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 5 Radiological Effluents 1 Core Melt

PAGE: 29 of 130 PROC.WORK PLAN NO. PROCEDUREfWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 RCS LEAKAGE

2.4 CONDITION

RCS Leakage > HPI Capacity EMERGENCY CLASSIFICATION:

Site Area Emergency MODES Above CSD CRITERIA:

1. RCS Leakage > HPI Capacity as indicated by:

core A. Full available HPI being injected into the AND or RCS B. RCS Pressure/Pressurizer Level continues to decrease no indication of Subcooling margin remains inadequate with recovery.

TAB RELATED EALS:

1 Containment Radiation High/Very High 1 Core Damage Indicated with an ICC Condition 1 Loss of or Challenge to 3 Fission Product Barriers I5 Radiological Effluents Core Melt

PAGE: 30 of 130 PROC.JORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS 3.1 EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES Above CSD CRITERIA:

OTSG

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

TAB RELATED EALS:

3 OTSG Tube Leak 5

Radiological Effluents

PAGE: 31 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS

3.2 CONDITION

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

CRITERIA:

(.104 gpm), coincident with one or

1. RCS Leak rate of > 150 gallons per day more of the following:

a)Main Steam line N-16 alarm(s) or 2682) b)Steam Line High Range RAD Monitors Increase (RI-2681 c)Condenser off gas process monitor count rate increase tube leak d)Nuclear Chemistry sample indicating Primary-Secondary TAB

PAGE: 32 of 130 PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS

3.3 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 (RI-2681 or RI-2682)

c. Steam Line High Range Rad Monitors increase tube leak

d. Nuclear Chemistry sample indicating primary-secondary AND

2. ANY of the following occur:

A. Loss of offsite power B. Steam release to the environment indicated by:

1. Main Steam Safety Valve(s) maintaining OTSG pressure

2. Use of ADV(s) to control OTSG pressure maintain OTSG

3. P7A is in use and continued operation required to levels

4. Steam line break outside containment TAB RELATED EALS:

3 OTSG Tube Rupture >50 gpm with ongoing steam release 3 OTSG Tube Leak with fuel cladding failure 2 RCS Leakage 5 Radiological Effluents 5 High Radiation/Airborne Levels 4 Electrical Power Failures 1 Loss of or Challenge to 3 Fission Product Barriers

PAGE: 33 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS

3.4 CONDITION

>normal makeup capacity (50 OTSG Tube Rupture with primary to secondary leakage release or loss of offsite power.

gpm) with ongoing steam EMERGENCY CLASSIFICATION:

Site Area Emergency MODES Above CSD CRITERIA:

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

RCS Leakage > Normal Makeup Capacity (50 gpm)

A.

B. Coincident with one or more of the following:

a)Main Steam line N-16 alarm(s) or 2682) b)Steam Line High Range RAD Monitors Increase (RI-2681 count rate increase c)Condenser off gas process monitor tube leak d)Nuclear Chemistry sample indicating Primary-Secondary AND

2. ANY of the following occur:

A. Loss of offsite power B. Steam release to the environment indicated by:

1. Main Steam Safety Valve(s) maintaining OTSG pressure

2. Use of ADV(s) to control OTSG pressure to maintain OTSG

3. P7A is in use and continued operation required levels

4. Steam line break outside containment TAB RELATED EALS:

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

PAGE: 34 of 130 PROC.IWORK PLAN NO. PROCEDURENWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SECONDARY SYSTEM EVENTS

3.5 CONDITION

with ongoing steam release OTSG Tube Leak >1 gpm with >1% fuel cladding failure EMERGENCY CLASSIFICATION:

Site Area Emergency MODES Above CSD CRITERIA:

Caution leakage approaches 50 gpm, consider transitioning to As Primary-to-Secondary EAL 1.7.

one or more of the

1. OTSG Leakrate increase of >1 gpm, coincident with following:

a) Main Steam line N-16 alarm(s)

(RI-2681 or 2682) b) Steam Line High Range RAD Monitors Increase rate increase c) Condenser off gas process monitor count tube leak d) Nuclear Chemistry sample indicating Primary-Secondary AND in the RCS (EAL 1.2)

2. Greater than 1% fuel cladding failure indicated AND

3. ANY of the following occur:

A. Loss of offsite power B. Steam release to the environment indicated by:

1. Main Steam Safety Valve(s) maintaining OTSG pressure

2. Use of ADV(s) to control OTSG pressure to maintain OTSG

3. P7A is in use and continued operation required levels

4. Steam line break outside containment TAB RELATED EALS:

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

PAGE: 35 of 130 PROC.IWORK PLAN NO. PROCEDURENWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.1 CONDITION

Degraded Power EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

Diesel) power is

1. Only Diesel Generator (Station Blackout Diesel or Emergency available to 4160V Buses (A3 and/or A4).

AND buses (HI, H2,

2. No voltage indicated on 6.9 KV AND 4.16 KV nonvital Al, and A2)

PAGE: 36 of 130 PROC.fWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.2 CONDITION

=Station Blackout EMERGENCY CLASSIFICATION:

RELATED EALS:

Blackout more than 15 minutes Loss of Control Room Annunciators

PAGE: 37 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.3 CONDITION

Blackout for more than 15 minutes.

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

than 15 minutes.

1. All 4160V buses de-energized for greater TAB RELATED EALS:

4 Electrical Power Failures 6 Loss of Control Room Annunciators 1 Core Melt

PAGE: 38 of 130 PROC.NVORK PLAN N

O. PROCEDURE

/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.4 CONDITION

Loss of All Vital DC Power RELATED EALS:

Loss of All Vital DC Power for more than 15 minutes Loss of Control Room Annunciators

PAGE: 39 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 ELECTRICAL POWER FAILURES

4.5 CONDITION

minutes Loss of All Vital DC Power for more than 15 CRITERIA:

1. Loss of voltage on ALL of the following busses A. D01 and D02 B. RAl and RA2 C. D11 and D21 AND

2. DC power is not restored within 15 minutes RELATED EALS:

Electrical Power Failures Loss of Control Room Annunciators

PROCEDURENVORK PLAN TITLE: PAGE: 40 of 130 PROC./WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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:

I. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS or 0.15 method, indicate greater than or equal to 0.05 mrem/hr TEDE 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:

V Radiological Effluents High Radiation/Airborne OTSG Tube Leak Levels

I .~~~.- A.t4'f In UAE*,

• m 111 1-111 PROC.NVORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS

5.2 CONDITION

is Projected or measured activity at the Site Boundary, averaged over one hour, mrem/hr Child Thyroid CDE or greater than or equal to 0.5 mrem/hr TEDE or 1.5 exceed 10 times ODCM Limitations.

Liquid radiological effluents CRITERIA:

i. Radiological Release which exceeds ANY of the following limits A. Projected activity at the Site Boundary, as calculated by the RDACS TEDE or 1.5 method, indicates greater than or equal to 0.5 mrem/hr mrem/hr Child Thyroid CDE.

OR Offsite monitoring teams report activity at the Site Boundary which, B.

when averaged over the previous one hour, exceeds 0.5 mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE.

OR ODCM Limitations.

C. Liquid radiological effluents exceed 10 times RELATED EALS:

Radiological Effluents OTSG Tube Leak Containment Radiation High

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 42 of 130 1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS

5.3 CONDITION

TEDE or 150 mrem/hr Radiological Effluents are greater than or equal to 50 mrem/hr Child Thyroid CDE at the Site Boundary.

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

limits I. Radiological Release which exceeds ANY of the following A. Projected dose rates at the Site Boundary, as calculated by the RDACS or 150 method, indicate greater than or equal to 50 mrem/hr TEDE mrem/hr Child Thyroid CDE.

OR Boundary are B. Offsite monitoring teams report dose rates at the Site TEDE or 150 mrem/hr Child Thyroid greater than or equal to 50 mrem/hr CDE.

TAB RELATED EALS:

5 Radiological Effluents 1 Containment Radiation High / Very High 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt

PAGE: 43 of 130 PROC.NVORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS

5.4 CONDITION

250 mrem/hr TEDE or 500 mrem/hr Radiological Effluents are greater than or equal to Child Thyroid CDE at the Site Boundary.

EMERGENCY CLASSIFICATION:

General Emergency MODES All CRITERIA:

I. Radiological Release which exceeds ANY of the following limits by the RDACS A. Projected dose rates at the Site Boundary, as calculated TEDE or 500 method, indicate greater than or equal to 250 mrem/hr mrem/hr Child Thyroid CDE.

OR Site Boundary are B. Offsite monitoring teams report dose rates at the mrem/hr Child Thyroid greater than or equal to 250 mrem/hr TEDE or 500 CDE.

TAB RELATED EALS:

Core Melt 1

Loss of or Challenge to 3 Fission Product Barriers 1

Containment Radiation High / Very High

PAGE: 44 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 RADIOLOGI CAL EFFLUENTS

5.5 CRITERIA

results in ANY of the following:

1. The loss of control of radioactive material A. Containment radiation indicates >2R/hr containment)

B. Area Radiation levels in controlled access (excluding increase by 1 Rem/hr at 2 or more locations.

controlled C. General area radiation levels outside of radiologically areas increase by 10 mRem/hr.

D. Airborne levels as follows:

"* Auxiliary Building >100 DAC (General Area)

"* Turbine Building >10 DAC "Loss of Control" shall be defined as: ANY radioactive material outside spent resin spill, RCS NOTE: (For Example:

ý --- astm hbundries.

etc.)

liquid spill, spent fuel accident resulting in gaseous release,

PAGE: 45 of 130 PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 RADIOLOGICAL EFFLUENTS

5.6 CRITERIA

occurs in the

1. The loss of water OR damage to a spent fuel assembly refueling canal, spent fuel pool, cask Rx core (head removed),

fuel tilt pit or any plant area involved in the loading pit, movement or storage of spent fuel.

AND Monitors or

2. Radiation levels increase to 10 R/hr on Area Radiation 10 Rem/hr HP Survey Report.

PAGE: 46 of 130 PROC.NVORK PLAN NO. PROCEDURENWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.1 CONDITION

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

EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES Above CSD CRITERIA:

1. EITHER of the following conditions exist:

Spec. limits.

A. Inability to reach required mode within Tech.

B. Deviation from Tech Specs authorized pursuant to 10CFR50.54(x)

TAB RELATED EALS:

2 RCS Leakage 3 OTSG Tube Leak 1 RCS Activity High

PAGE: 47 of 130 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.2 CONDITION

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

CRITERIA:

1. A valid RPS trip setpoint is exceeded on ANY TWO RPS channels and the RPS fails to initiate and complete an automatic trip that brings the reactor subcritical.

AND

2. Subsequent efforts to manually trip the Reactor from the Control Room and bring it subcritical are successful.

TAB RELATED EALS:

RPS Failure to Complete a Manual Trip Core Melt Core Damage Indicated with an ICC Condition Loss of or Challenge to 3 Fission Product Barriers

PAGE: 48 of 130 PROC.IWORK PLAN NO. PROCEDURENORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.3 CONDITION

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

Site Area Emergency MODES Hot Stdy-Pwr Ops CRITERIA:

setpoint is exceeded on ANY TWO RPS channels and the RPS

1. A valid RPS trip the reactor fails to initiate and complete an automatic trip that brings subcritical.

AND (Failure to trip the Reactor in the

2. Failure of manual trip function occurs.

Control Room; i.e., must leave Control Room to trip the Reactor.)

TAB RELATED EALS:

Boundaries Loss of or Challenge to 3 Fission Product Core Melt 1

Core Damage Indicated with an ICC Condition

PAGE: 49 of 130 PROC./WORKPLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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 every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

C. Inability to obtain and analyze local grab samples OR System is not

2. Reactor Building Purge System or Penetration Ventilation isolable, and the applicable SPING is inoperable.

OR of gaseous effluents in

3. All of the following conditions exist for any source Building ventilation systems.

the Auxiliary Building or Spent Fuel Storage A. Applicable SPING is inoperable AND every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. Inability to obtain and analyze local grab samples

PAGE: 50 of 130 PROC./WORK PLAN NO. PROCEDUREWORK PLAN TITLE:

EMERGENCY ACTION LEVEL CLASSIFICATION 1903.010 I CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.5 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

PAGE: 51 of 130 jPROC.IWORK PLAN N

O. PROCEDURE

/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.6 CRITERIA

room annunciators.

1. Loss of both AC and DC power to >50% of control TAB RELATED EALS:

PAGE: 52 of 130 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.7 CRITERIA

annunciators.

1. Loss of both AC and DC power to >50% of control room AND A plant transient is initiated or in progress. (See section 4.18 of this 2.

procedure for the definition of a Plant Transient.)

PAGE: 53 of 130 PROC./WORK PLAN N

O. PROCEDURE

NWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.8 RELATED EALS:

systems not Control Room Evacuation and control of shutdown established in 15 minutes of any ES Systems Fire or explosion onsite affecting both trains

PAGE: 54 of 130 PROC.JWORK PLAN N

O. PROCEDURE

WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION

6.9 CONDITION

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

RELATED EALS:

Core Damage Indicated with an ICC Condition Loss of Decay Heat Removal Systems Core Melt

PAGE: 55 of 130 PROC.1NORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6.10 CONDITION:

Loss of Decay Heat Removal Capabilities EMERGENCY CLASSIFICATION:

Alert MODES CSD-Refueling S/D CRITERIA:

as ANY of the

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

A. RCS indicates saturated conditions not available B. Loss of both Decay Heat trains for >1 hr and OTSGs are Canal is flooded) for decay heat removal (NA if Fuel Transfer C. HPI is required for cooling the reactor core.

TAB RELATED EALS:

1 Core Damage Indicated with an ICC Condition 5 Radiological Effluents 1 Loss of or Challenge to 3 Fission Product Barriers 5 High Radiation/Airborne Levels 1 Core Melt

PAGE: 56 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 SAFETY SYSTEM FUNCTION 6 .11 CONDITION:

Degraded Hot Shutdown Capability CRITERIA:

as ANY of the following:

1. Degraded HSD capability shall be identified OTSGs. (e.g., Loss of ALL A. Loss of ALL steam removal capability on BOTH and Main Steam Safety Turbine Bypass Valves, Atmospheric Dump Valves, Valves)

OTSGs. (e.g., Loss of B. Loss of ALL feedwater supply capability on BOTH BOTH Main Feedwater Trains and BOTH EFW trains) required for cooling the C. BOTH HPI Trains are inoperable and they are I

reactor core.

TAB RELATED EALS:

Core Damage Indicated with an ICC Condition Containment Radiation Very High Core Melt 1

Loss of or Challenge to 3 Fission Product Barriers

PAGE: 57 of 130 PROC.IWORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.1 CONDITION

Security Fence (e.g.,

Security threat onsite but outside the Protected Area stopped outside the security fence) attempted entry or sabotage which has been EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

Security Fence (e.g.,

1. Security threat onsite but outside the Protected Area stopped outside the security fence).

attempted entry or sabotage which has been or

2. A Credible site-specific security threat notification.

TAB RELATED EALS:

outside Ongoing security Threat Inside Protected Area Fence but plant buildings

PAGE: 58 of 130 PROC.JWORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.2 CONDITION

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

Alert MODES All RELATED EALS:

Control Ongoing security threat within plant buildings but not in Room or vital areas.

PAGE: 59 of 130 PROC.IWORK PLAN N

O. PROCEDURE

IWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.3 CRITERIA

Same as the Condition stated above.

TAB

D*E*.

I ~ ~ Nil IN&

42A~

i.llI PROC.WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.4 CONDITION

vital areas Ongoing security threat within the Control Room or EALS : TAB F*ELATED

~ELATED EALSi: I______

None

PAGE: 61 of 130 PROC.,WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.5 EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All

PAGE: 62 of 130 PROC.WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.6 CRITERIA

1. Fire or explosion onsite AND A potential or actual loss of a single train of ANY ES system as a 2.

result of the fire or explosion TAB

PAGE: 63 of 130 PROCJWORK PLAN N

O. PROCEDURE

IWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.7

PAGE: 64of130 PROC./WORK PLAN NO. PROCEDURENIORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.8 CONDITION

Train Derailment, Turbine Failure, Toxic Aircraft Crash, Unusual Aircraft Activity, 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.

plant shutdown.

D. Turbine rotating component failure causing rapid or restricts access to E. Toxic or flammable gas release which limits the plant.

areas required for security or safe operation of TAB RELATED EALS:

7 Fire or Explosion Onsite 7 Security Threat 7 Gas Affecting One Aircraft Crash, Missiles, Toxic or Flammable Train of ANY ES System

PAGE: 65 of 130 PROC.JWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION

7.9 CONDITION

ANY ES Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of 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 ES system

2. A potential OR actual loss of a single train of ANY TAB RELATED EALS:

an ES System 7 Fire or Explosion Onsite Affecting One Train of 7 Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting Both Trains of ANY ES System

PAGE: 66 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 1903.010 ATTACHMENT 3 UNIT 1 HAZARDS TO STATION OPERATION 7.10 CRITERIA:

1. ANY of the following:

A. Aircraft crash onsite.

B. Missiles/Projectiles from any source C. Toxic or flammable gas release AND A potential OR actual loss of BOTH trains of ANY ES system 2.

PAGE: 67 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 1903.010 ATTACHMENT 3 ATTACHMENT UNIT UNIT 1 NATURAL NATURAL EVENTS 8.1 8.1 CRITERIA:

1. ANY of the following:

Area A. Tornado observed on the ground within the Exclusion Flood - Lake level >340' elev. and rising, with forecasted B.

lake level >350' elev.

by U.S.

C. Low Level - Lake level <337' elev. AND forecasted Army Corp of Engineers to reach 335' elev.

- VERIFIED earthquake accompanied by .01g alarm.

D. Earthquake

PAGE: 68 of 130 PROC.IWORK PLAN NO. PROCEDURENVORK PLAN TITLE:

TION EMERGENCY ACTION LEVEL CLASSIFICA CHANGE: 036-05-0 1903.010 ATTACHMENT 3 UNIT 1 NATURAL EVENTS

8.2 CRITERIA

1. ANY of the following:

facility structures (e.g. housing ES A. Tornado striking vital related equipment) minute average B. High Winds - Sustained winds of >60 mph (10 by RDACS from either the 10 or 57 meter as reported instruments).

by U.S.

C. Flood - Flood waters >350' elev. and are forecasted to reach or exceed 354' elev.

Army Corp of Engineers D. Low Level - Lake level <335' elev E. Earthquake VERIFIED earthquake accompanied by .1g alarm.

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

RELATED EALS:

Loss of Dardanelle Reservoir, Earthquake Tornado, High Winds, Flood, Loss of or challenge to all 3 Fission Product Barriers

PAGE: 69 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 3 UNIT 1 NATURAL EVENTS 8.3 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES Above CSD CRITERIA:

1. ANY of the following:

average A. High Winds - Sustained winds of >67 mph (10 minute 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 earthquake resulting in E. Tornado, high wind, flood, low lake level or of ANY ES system.

the potential or actual loss of BOTH trains

PROCEDUREIWORK PLAN TITLE: PAGE: 70 of 130 PROC.WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS

9.1 CONDITION

on the part of the Other plant conditions exist that warrant increased awareness offsite authorities or involve other than operating staff and state and/or local 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 fission product barrier

2. This event does not challenge or cause the loss of a AND this event requires an

3. In the judgement of the SM/TSC Director/EOF Director increased awareness by the ANO staff and offsite authorities.

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

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS

9.2 CONDITION

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

CRITERIA:

The following conditions must exist

1. This event is not covered by any other EAL.

AND loss of a fission product

2. This event must either challenge or cause the barrier.

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

PAGE: 72 of 130 PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS

9.3 CONDITION

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

CRITERIA:

CRITERIA:

The following conditions must exist

i. 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 TAB RELATED EALS:

Large Amounts of 9 Plant Conditions Exist that Make Release of Radioactivity Possible

PAGE: 73 of 130 PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 3 UNIT 1 MISCELLANEOUS EVENTS

9.4 CRITERIA

The following conditions must exist:

1. This event is not covered by any other EAL AND amounts of radioactivity in

2. Events have occurred that make a release of large a short period of time possible.

TAB

PAGE: 74 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.1 CONDITION

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

Notification of Unusual Event MODES 1-5 CRITERIA:

by EITHER of the

1. Greater than 0.1% fuel cladding failure as indicated following:

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

B. Specific 1-131 sample results >37.8 ý1Ci/gm TAB RELATED EALS:

1 RCS Activity 6 T.S. L.C.O.'s 5 General Area Radiation/Airborne

PAGE: 75 of 130 PROCJWORK PLAN N

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/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.2 CONDITION

RCS Activity indicates >1.0% fuel cladding failure RELATED EALS:

General Area Radiation/Airborne Containment Radiation Loss of or Challenge to 3 Fission Product Barriers Core Damage/ICC

-Y IF 4 11A I PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.3 CRITERIA

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

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

{0CNA08005} 2. Radiation levels that indicate >1% fuel cladding failure per Unit 2 Fuel Cladding Failure Radiation Plot (Att 8)

AND by ANY of the following:

2. Inadequate core cooling capacity exists as indicated 0

F superheat A. Th RTD and average CET temperature indicates >10 AND RVLMS LVL 7 or Lower indicates Dry.

superheat B. Th RTD and average CET temperature indicates >10°F with both RVLMS Channels inoperable AND RCS temperatures increasing.

0 C. CET Temperatures indicate greater than 700 F.

TAB RELATED EALS:

6 Decay Heat Removal 1 Containment Radiation 1 Core Melt 2 RCS Leakage

PAGE: 77 of 130 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.4 CONDITION

and >1% fuel cladding failure Containment Radiation readings which indicate LOCA EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

Area Emergency as

1. Containment Radiation Levels correspond to a Site radiation EAL plot (Att 6) determined from the containment AND

2. LOCA occurring within the Containment Building TAB RELATED EALS:

1 Containment Radiation 1 Loss of or challenge to 3 Fission Product Barriers 15 Radiological Effluents 1 Core Melt

PAGE: 78 of 130 PROC.1WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.5 CONDITION

and >50% fuel overheat Containment Radiation readings which indicate LOCA EMERGENCY CLASSIFICATION:

General Emergency MODES All CRITERIA:

i. 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 TAB RELATED EALS:

1 Loss of or challenge to 3 Fission Product Barriers 5 Radiological Effluents I Core Melt

I ~ y 7O 4 4f I2 7Q ,*f I*N PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.6 CRITERIA

RITERIA:

1. ANY of the following events occur failure of ALL ECCS systems occurs.

A. Small or Large LOCA and a complete S/G's is <70" (Wide Range)

B. Loss of ALL feedwater AND S/G Level in both 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)

TAB RELATED EALS:

Loss of or challenge to 3 Fission Product Barriers Containment Radiation Radiological Effluents

PAGE: 80 of 130 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTIOIN LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 PRIMARY SYSTEM EVENTS

1.7 CRITERIA

i. Either of the following conditions exist:

A. Fuel Cladding Failure (refer to section 4.10.1)

B. Challenge to Fuel Cladding (refer to sect+/-u+/-+/- .

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)

PAGE: 81 of 130 PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RCS LEAKAGE

2.1 CONDITION

RCS Leakage EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES 1-4 RELATED EALS:

RCS Leakage T.S. L.C.O.'S Primary to Secondary Leakage General Area Radiation/Airborne

PAGE: 82 of 130 PAGE:

PROC./WORK PLAN N

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/WORK PLAN TITLE:

EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 1903.010 CHANGE:

ATTACHMENT 4 UNIT 2 RCS LEAKAGE 2.2 TAB RELATED EALS:

2 RCS Leakage 5 General Area Radiation/Airborne 1 Containment Radiation 6 Decay Heat Removal Primary to Secondary Leakage 3HE

PAGE: 83of130 PROC.IWORK PLAN NO. PROCEDURENWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RCS LEAKAGE

2.3 CONDITION

RCS Leakage > 44 gpm with ICC Conditions EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

1. RCS Leakage is >44 gpm (Capacity of a single Charging Pump).

AND ANY of the

2. Inadequate Core Cooling conditions exist as indicated by following:

0 AND RVLMS A. Th RTD and average CET temperature indicates >10 F superheat LVL 7 or Lower indicates Dry.

0 with both B. Th RTD and average CET temperature indicates >10 F superheat RVLMS Channels inoperable AND RCS temperature increasing.

0 C. CET Temperatures indicate greater than 700 F.

TAB RELATED EALS:

1 Core Damage/ICC 5 Radiological Effluents 1 Containment Radiation 1 Core Melt 1 Loss of or challenge to 3 Fission Product Barriers 3 Primary to Secondary Leakage

ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS 3.1

- PAGE: 85 of 130 PROC.!WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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

> 300 gallons per day (0.2083 gpm)

A. Total leakage through both S/G's is OR B. Leakage to 1 S/G is > 150 gallons per day (0.1042 gpm)

TAB RELATED EALS:

2 RCS Leakage 3 Primary to Secondary Leakage 5 Radiological Effluents

PAGE: 86 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS 3.3 EMERGENCY CLASSIFICATION:

Alert MODES 1-4 CRIT 'ERIA:

Release in Progress as indicated by ANY of

1. S/G tube leak >10 gpm with a Steam 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 maintain S/G levels.

D. 2P7A is in use and continued operation is required to TAB RELATED EALS:

3 Primary to Secondary Leakage 2

RCS Leakage 5

General Area Radiation/Airborne 5

Radiological Effluents 4

Electrical Power

a7 f 42 PROC.NVORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SECONDARY SYSTEM EVENTS

3.4 CONDITION

Steam Release and RCS Steam Generator Tube Rupture >44 gpm With an Ongoing (1% fuel cladding failure).

Activity > 1.0 pCi/gm, but < 378 pCi/gm CRITERIA:

S/G tube leak >44 gpm with a Steam Release in Progress as indicated by ANY of 1.

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 to maintain S/G D. 2P7A is in use and continued operation is required levels.

AND

2. RCS Activity > 1.0 gCi/gm (T.S. 3.4.8), but < 378 pCi/gm (1% fuel cladding failure).

S uCAUT I ION FAs fuel cladding failure approaches 1% (378 ýjCi/gm 1-131) EAL 1.7 may apply.

TAB RELATED EALS:

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

PAGE: 88 of 130 PROC.JWORK PLAN NO. PROCEDURENORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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 (2A1 & 2A2)

2. No voltage indicated on Both 4.16 KV nonvital busses AND Diesel started

3. At least one Emergency Diesel or Station Blackout and supplying a vital bus (2A3 or 2A4)

TAB

PAGE: 89 of 130 PROC./WORK PLAN N

O. PROCEDURE

/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.2 TAB RELATED EALS:

4 Electrical Power 6 Communications, Dose Assessment 3 Primary to Secondary Leak 6 Decay Heat Removal 1 Core Melt

PROCEDURENVORK PLAN TITLE:

PAGE: 90 of 130 PROC.JNORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.3 RELATED EALS:

Electrical Power Communications, Dose Assessment I

PAGE: 91 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.4 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

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

A. Loss of all Control Room lighting except emergency DC lights (2A1 and 2A2)

B. No voltage indicated on Both 4.16 KV nonvital busses C. Neither Vital 4.16 KV Buss energized (2A3 or 2A4)

AND

2. The Blackout Condition exists for >15 minutes TAB RELATEDaiu EL:

6 Decay Heat Removal 4

Electrical Power 3

Primary to Secondary Leakage 1

Core Melt 5

Radiological Effluents

PAGE: 92 of 130 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 ELECTRICAL POWER FAILURES 4.5 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

has occurred:

1. Loss of both of the following trains of DC Busses RED TRAIN GREEN TRAIN 2D01 2D02 2RAI 2RA2 2D21 2D22 2D23 2D24 AND

2. Power is not restored to at least one train within 15 minutes TAB RELATED EALS:

I 6

Communications, Dose Assessment Decay Heat Removal 1 Core Melt 5 Radiological Effluents

PAGE: 93 of 130 PROC.IWORK PLAN NO. PROCEDUREfWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.1 CONDITION

CONDITION:

Projected or measured activity at the Site Boundary, averaged over one hour, is Child Thyroid CDE or greater than or equal to 0.05 mrem/hr TEDE or 0.15 mrem/hr 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 TEDE or 0.15 method, indicate greater than or equal to 0.05 mrem/hr 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.

TAB SANS: TAB

• ELATED R~ELATED1- EALS:

5 Radiological Effluents General Area Radiation/Airborne 3 Primary to Secondary Leak

PROCEDUREIWORK PLAN TITLE: PAGE: 94 of 130 PROC.JWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.2 CONDITION

is Projected or measured activity at the Site Boundary, averaged over one hour, mrem/hr TEDE or 1.5 mrem/hr Child Thyroid CDE or greater than or equal to 0.5 Liquid radiological effluents exceed 10 times ODCM Limitations.

EMERGENCY CLASSIFICATION:

Alert MODES All CRIERIAkl-:

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, TEDE or when averaged over the previous one hour, exceeds 0.5 mrem/hr 1.5 mrem/hr Child Thyroid CDE.

OR C. Liquid radiological effluents exceed 10 times ODCM Limitations.

TAB RELATED EALS:

5 Radiological Effluents 3

Primary to Secondary Leak 1

Containment Radiation

PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTIOIN LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.3 CONDITION

to 50 mrem/hr TEDE or 150 mrem/hr Radiological Effluents are greater than or equal Child Thyroid CDE at the Site Boundary.

CRITERIA:

1. Radiological Release which exceeds ANY of the following limits calculated by the RDACS A. Projected dose rates at the Site Boundary, as TEDE or 150 method, indicate greater than or equal to 50 mrem/hr mRem/hr Child Thyroid CDE.

OR Site Boundary are B. Offsite monitoring teams report dose rates at the 150 mrem/hr Child Thyroid greater than or equal to 50 mrem/hr TEDE or CDE.

TAB RELATED EALS:

5 Radiological Effluents 1 Containment Radiation 1 Loss of or Challenge to 3 Fission Product Barriers 1 Core Melt

PAGE: -96 of 130 PROC.JWORK PLAN NO. PROCEDUREWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.4 CONDITION

to 250 mrem/hr TEDE or 500 mrem/hr Radiological Effluents are greater than or equal Child Thyroid CDE at the Site Boundary.

CRITERIA:

limits

1. Radiological Release which exceeds ANY of the following calculated by the RDACS A. Projected dose rates at the Site Boundary, as or equal to 250 mrem/hr TEDE or 500 method, indicate greater than mrem/hr Child Thyroid CDE.

OR at the Site Boundary are B. Offsite monitoring teams report dose rates greater than or equal to 250 mrem/hr TEDE or 500 mrem/hr Child Thyroid CDE.

PAGE: 97 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS 5.5 SVT17)T 7-I.-rq*

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

1.

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.

controlled C. General area radiation levels outside of radiologically 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.

Spent resin spill, RCS liquid spill, Spent fuel accident (For Example:

resulting in gaseous release, etc.)

• !J/-YI*U *:

TAB K ELATED EALS:

5 Radiological Effluents 1 Containment Radiation 5 Spent Fuel Damage 2 RCS Leakage

PROCEDUREIWORK PLAN TITLE: PAGE: 98 of 130 PROC.JORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 RADIOLOGICAL EFFLUENTS

5.6 C2RITERIA

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.

TAB RELATED EALS:

5 Radiological Effluents 5

General Area Radiation/Airborne 9

Miscellaneous

PAGE: 99 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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:

Spec. limits.

A. Inability to reach required mode within Tech.

B. Deviation from Tech Specs authorized pursuant to 10CFR50.54(x)

TAB RELATED EALS:

2 RCS Leakage 3

Primary to Secondary Leakage RCS Activity

PROCEDUREIWORK PLAN TITLE: PAGE: 100 of 130 PROC./WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.2 CRITERIA

1. A valid RPS trip setpoint is exceeded AND Ten (10) or more CEAs fail to insert as result of the automatic trip 2.

AND

3. CEAs are inserted either by manual trip or DSS.

mflr\ t'T C TAB 6

RPS Failure Core Melt 1 1

Core Damage/ICC

PROCEDURE/WORK PLAN TITLE: PAGE: 101 of 130 PROC.IWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.3 C-RIKTjI-A

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.)

TAB RELATED EALS:

1 Loss of or Challenge to 3 Fission Product Barriers 1

Core Melt Core Damage/ICC 1

PROCEDURE/WORK PLAN TITLE: PAGE: 102 of 130 PROCJWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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 applicable

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

OR effluents in

3. All of the following conditions exist for any source of gaseous Auxiliary Extension Building, or Spent Fuel Storage the Auxiliary Building, 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 />.

TAB RELATED EALS:

Dose Assessment 6 Communications,

PAGE: 103 of 130 PROC./WORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.5 EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All All Event of Unusual CLASSIFICATION:

EMERGENCYMODES Notification I. Complete loss of ANY TWO of the following:

A. Plant telephone systems (Commercial telephones and microwave)

B. Station Radio C. Emergency Notification System TAB RELATED EALS:

None

PROCEDURE/WORK PLAN TITLE: PAGE: 104 of 130 PROC/WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.6 CONDITION

Control Room Evacuation EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. Control Room evacuation is expected to occur OR has already occurred TAB RELATED EALS:

6 Control Room Evacuation

PROCEDURE/WORK PLAN TITLE: PAGE: 105 of 130 PROC.IWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.7 EMERGENCY CLASSIFICATION:

Site Area Emergency MODES 1-4 CRITERIA:

is not

1. Control Room evacuation has occurred AND control of shutdown systems established from local stations within 15 minutes.

TAB RELATED EALS:

1 Core Damage/ICC 6

Decay Heat Removal 1

Core Melt

PAGE: 106 of 130 PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION

6.8 CRITERIA

1. Loss of Decay Heat Removal capabilities shall be identified as ANY of the f ol lowing:

A. RCS indicates saturated conditions and S/G's not available B. Loss of both shutdown cooling trains for >1 hr Canal >23 ft) for decay heat removal (NA if Fuel Transfer C. HPSI injection required for cooling the core TAB RELATED EALS:

5 Spent Fuel Accident 1 Core Damage/ICC 5 Radiological Effluents 1 Loss of or Challenge to 3 Fission Product Barriers 5 High Radiation/Airborne 1 Core Melt

PROCEDURE/WORK PLAN TITLE:

PAGE: 107 of 130 PROC.IWORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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 TAB RELATED EALS:

Containment Radiation 1 2

RCS Leakage 1

Core Melt 1

Loss of or Challenge to 3 Fission Product Barriers

PAGE: 108 of 130 PROC./WORK PLAN NO. PROCEDUREjWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.10 CONDITION: I Loss of Control Room Annunciators CRITERIA:

Room Annunciator

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

TAB RELATED EALS:

progress 6 Loss of Control Room Annunciators with a Transient in 4

Electrical Power

PROCEDURENVORK PLAN TITLE: PAGE: 109 of 130 PROC./WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 SAFETY SYSTEM FUNCTION 6.11 CONDITION:

EMERGENCY CLASSIFICATION:

Site Area Emergency MODES ALL CRITERIA:

Annunciator

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

TAB RELATED EALS:

4 Electrical Power

PAGE: 110 of 130 PROC.JORK PLAN NO. PROCEDUREWNORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.1 CONDITION

Fence (e.g.

Security threat onsite but outside the Protected Area Security outside the security fence).

attempted entry or sabotage which has been stopped EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

Security Fence (e.g.,

1. Security threat onsite but outside the Protected Area which has been stopped outside the security fence).

attempted entry or sabotage or

2. A credible site-specific security threat notification.

TAB RELATED EALb:

7 Security Threat

PAGE: 111 of 130 PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.2 CONDITION

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

EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

Same as the Condition stated above.

I TAB RELATED EALS:

PROCEDURE/WORK PLAN TITLE: PAGE: 112 of 130 PROC.1WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.3 CONDITION

within the Control Room or Ongoing security threat within plant buildings but not vital areas.

CRITERIA:

Same as the Condition stated above.

TAB RELATED EALS:

7 Security Threat 7 Fire/Explosion

PROCEDURE/WORK PLAN TITLE: PAGE: 113 of 130 PROC./WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 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.

mr'n flT C' TAB I,

I<

None

PAGE: 114 of 130 PROC.,WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.5 CONDITION

Fire or Explosion Onsite EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

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

OR

2. Explosion causing facility damage.

TAB RELATED EALS:

7 Fire or Explosion 7

Security Threat

PAGE: 115 of 130 PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION 0 PERATION 7.6 EMERGENCY CLASSIFICATION:

Alert MODES All CRITERIA:

1. Fire or explosion onsite AND of ANY ESF system as a result of

2. A potential or actual loss of a single train the fire or explosion.

TAB RELATED EALS:

7 Fire or Explosion 6

Communications, Dose Assessment 6

Control Room Evacuation

PROCEDURE/WORK PLAN TITLE: PAGE: 116 of 130 PROC./WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.7 CONDITION

Trains of ESF Systems Fire or Explosion Onsite affecting Both EMERGENCY CLASSIFICATION:

Site Area Emergency MODES All CRITERIA:

1. Fire or explosion onsite AND of ANY ESF system as a result of

2. A potential or actual loss of Both trains the fire or explosion.

TAB RELATED EALS:

6 Communications, Dose Assessment 6

Control Room Evacuation

PAGE: 117 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.8 CONDITION

Derailment, Turbine failure, Toxic Aircraft Crash, Unusual Aircraft Activity, Train 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 access to E. Toxic or flammable gas release which limits or restricts areas required for security or safe operation of the plant.

TAB RELATED EALS:

7 Fire or Explosion 7 Security Threat 3 MSIS 7

Other Hazards

PAGE: 118 of 130 PROC./WORK PLAN NO. PROCEDUREdWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION

7.9 CONDITION

Aircraft Crash, Missiles, Toxic or Flammable Gas Affecting One Train of ESF Systems 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 TAB RELATED EALS:

7 Fire or Explosion 7 Other HaZards

PAGE: 119 of 130 PROC./WORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 HAZARDS TO STATION OPERATION 7.10 CONDITION:

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

PAGE: 120 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 NATURAL EVENTS

8.1 CONDITION

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

Notification of Unusual Event MODES All DT'ThDTS.

ýUO T"A

1. ANY of the following A. Tornado observed on the ground within the Exclusion Area B. Flood - Lake level >340' elev. and rising with forecasted lake level

>350' elev.

C. Low Level - Lake level <337' AND forecasted by U.S. Army Corp of Engineers to reach 335' D. Earthquake - VERIFIED earthquake accompanied by .01g alarm.

TAB RELATED EALS:

8 Natural Events

It.4~4f 0A NAf*,

CHN.JG*: 036-0m I J I Ill I-Ill PROC.IWORK PLAN NO. PROCEDUREINORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 NATURAL EVENTS

8.2 CONDITION

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

Alert MODES All

,-rTmDT7\

k. n

k. -L I r11%"r 7\ :

--- 7

1. ANY of the following A. Tornado striking vital facility structures (e.g. housing ES related equipment) as reported B. High Winds - Sustained winds of >72 mph (10 minute average by RDACS from either the 10 or 57 meter instruments).

Army Corp of C. Flood - Flood waters >350' and are forecasted by U.S.

Engineers to reach or exceed 354' D. Low Level Lake level <335' elevation E. Earthquake - VERIFIED Earthquake accompanied by .1g alarm.

OR Any natural event resulting in the potential or actual loss of ONE train of ANY ES system RELATED EALS:

Natural Events Loss of or challenge to all 3 Fission Product Barriers

PAGE: 122 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 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 as reported A. High Winds - Sustained winds of >80 mph (10 minute average 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 in E. Tornado, high wind, flood, low lake level or earthquake resulting the potential or actual loss of BOTH trains of ANY ESF system.

TAB RELATED EALS:

3 Fission Product Barriers 1 Loss of or challenge to all

I92-fIfl I e* 3 1* 0EV 19 PROCEDUREINORK PLAN TITLE:

• Lq*

PROC./WORK PLAN NO.

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS

9.1 CONDITION

awareness on the part of the other plant conditions exist that warrant increased and state and/or local offsite authorities or involve other than operating staff normal controlled shutdown.

EMERGENCY CLASSIFICATION:

Notification of Unusual Event MODES All CRITERIA:

An event has occurred and the following conditions exist:

i. This event is not covered by any other EAL AND of a fission product barrier

2. This event does not challenge or cause the loss AND this event requires an

3. In the judgement of the SM/TSC Director/EOF Director authorities.

increased awareness by the ANO Staff and offsite TAB RELATED EALS:

1 RCS Activity 2 RCS Leakage 35 Primary to Secondary Leak 6 Radiological Effluents T.S. L.C.O.'s6 6 Loss of Indications/Communications/Dose Assessment

PAGE: 124 of 130 PROC.!WORK PLAN N

O. PROCEDURE

/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS

9.2 CONDITION

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

TAB RELATED EALS:

1 RCS Activity 2 RCS Leakage 3 Primary to Secondary Leak 5 Radiological Effluents 6 Decay Heat Removal

PAGE: 125 of 130 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS

9.3 CONDITION

response Other plant conditions exist that warrant activation of emergency notification to the public near facilities and monitoring teams or a precautionary 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. This event may cause ANY of the following:

A. Challenge to two fission product barriers B. Failure of one fission product barrier and a challenge to another C. Failure of 2 fission product barriers TAB RELATED EALS:

1 Core Damage/ICC 1

Containment Radiation 6

Decay Heat Removal 5

Radiological Effluents 2

RCS Leakage 3

Primary to Secondary Leak

PAGE: 126 of 130 PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION 036-05-0 CHANGE:

ATTACHMENT 4 UNIT 2 MISCELLANEOUS EVENTS

9.4 CRITERIA

The following conditions must exist I. This event is not covered by any other EAL AND of radioactivity in

2. Events have occurred that make a release of large amounts a short period of time possible.

TAB RELATED EALS:

1 1

[core Melt Loss of or Challenge to 3 Fission Product Barriers 1 Containment Radiation 5 Radiological Effluents

PAGE: 127 of 130 PROC.IWORK PLAN NO. PROCEDURENVORK PLAN TITLE:

1903.010 EMERGENCY ACTION LEVEL CLASSIFICATION CHANGE: 036-05-0 ATTACHMENT 5 UNIT 1 NOTE:

with 1903.011 Attachment 7 (WITH Spray), SAE equals 1%

This graph corresponds Clad Failure and GE equals 50% Fuel Overheat.

CONTAINMENT RADIATION EAL PLOT GENERAL EMERGENCY RHR SITE AREA EMERGENCY TIME INHOUR INSTRUCTIONS I CAUTION In the absence of a significant containment temperature transient,

• monitor readings should be considered valid. monitor In the event of a significant containment temperature transient, Supplement 1) readings may be erratic for a short duration (Ref.IN-97-45, A. Determine the containment radiation level.

RE-8060 or

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

the

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

Rad level = Reading from RE-8060 or RE-8061 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

I ... 4'O

,3a- 4,2n PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

N LEVEL CLASSIFICATION 036-05-0 1903.010 EMERGENCY ACTIOI CHANGE:

ATTACHMENT 6 UNIT 2 NOTE:

with 1903.011 Attachment 8 (WITH Spray), SAE equals 1%

This graph corresponds Clad Failure and GE equals 50% Fuel Overheat.

CONTAINMENT RADIATION EAL PLOT I E+06 4

2' 1 E+05 4

GENERAL 2

EMERGENCY IE+04 R ,R 4 11 TIME IN HOUR INSTRUCTIONS CAUTION

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

• In the event of a significant containment temperature Supplement 1) readings may be erratic for a short duration (Ref.IN-97-45, A. Determine the containment radiation level.

from 2RY-8925-1 or

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

determine the

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

100%

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

Attachment 7 (0CNA08005)

Unit 1 Fuel Cladding Failure Radiation Plot mRem/hr at SA-229 2000 I-J 1500

() 1000 500 - m - - -n-

- -In m m m - m S -- *-

A U

6 12 24 48 96 192 0 0.5 1 3 Instructions for obtaining the dose rates Time (hours since shutdown) resides in the Chemistry sample procedure. -- 5% Fuel Cladding Failure M - 1% Fuel Cladding Failure 1

Attachment 8 (OCNA08005)

Unit 2 Fuel Cladding Failure Radiation Plot mRem/hr at 2TCD- 19 3500 3000 I.

2500

"* 2000 S1500 1000 500 0

6 12 24 48 96 192 0 0.5 1 3 Instructions for obtaining the dose rate Time (hours since shutdown) resides in the Chemistry sampling 5% Fuel Cladding Failure - - - 1% Fuel Cladding Failure procedure