ML081840502

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Retake Exam 05000338-06-302 Draft Job Performance Measures (Part 2 of 2)
ML081840502
Person / Time
Site: North Anna Dominion icon.png
Issue date: 07/02/2008
From:
- No Known Affiliation
To:
NRC/RGN-II
References
50-338/06-302
Download: ML081840502 (63)
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Text

CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 1 & 2 Required to determine path's dose.

3 Required to determine path with lowest dose.

NAPS Admin-3 Page 6 of 7

NAPS Admin-3 Page 7 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The crew is attempting to place a system in service, but they are unable to remotely open a valve.

You have been tasked with entering containment and locally opening the valve.

Health Physics personnel are currently unavailable to provide assistance.

Two routes are available to the valve:

o Route 1 consists of twosegments.

Segment 1 has you walk through a 200mRlhr general field for 2 minutes.

Segment 2 has you walk in a 300 mRlhr general field to the valve for 8 minutes o

Route 2 consists of twosegments.

Segment 1 has you walk through a 50 mRlhr general field for 4 minutes.

Segment 2 has you walk in a 150 mRlhr general field to the valve for 12 minutes o

The two routes as detailed are to be considered separately and are listed as the round-trip time to and from the manual valve.

INITIATING CUE:

You are to determine which route allows the lowest exposure.

I "

NAPS Adm in-4 Page 1 of 7 DRAFT REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-4 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE Determine highest EPIP classification.

CANDIDATE EXAMINER DRAFT

NAPS Admin-4 Page 2 of 7 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCEMEASURE Classify an emergency event (EPIP-1.01).

Alternate Path:

Facility JPM #:

KIA Rating(s):

Gen 2.4.29 (2.6/4.0)

Task Standard:

Event is classified as a Notification of Unusual Event (NOUE) per TAB B.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulate _X_

Perform X

Simulator X

Classroom _....<..:..._

References:

EPIP-1.01, "EMERGENCY MANAGER CONTROLLING PROCEDURE, Rev. 42.

EMERGENCY ACTION LEVEL TECHNICAL BASIS DOCUMENT, Rev. 13 Validation Time: 10 min.

Time Critical: NO

=======================================================================

Candidate:

NAME Time Start :

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

NAME SIGNATURE

/

DATE

=======================================================================

Comments

SIMULATOR OPERATOR INSTRUCTIONS:

NONE NAPS Admin -4 Page 3 of 7

NAPS Admin-4 Page 4 of 7 Tools/Equipment/Procedures Needed:

EPIP-1.01, "EMERGENCY MANAGER CONTROLLING PROCEDURE, Rev 42.

EMERGENCY ACTION LEVEL TECHNICAL BASIS DOCUMENT, Rev. 13 READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit-1 Shutdown Banks had been pulled and an RCS dilution was about to begin, in preparation for a unit start-up.

Due to an increase in containment sump pumping rate, the control room crew completes a leak rate PT and determines that unidentified RCS leakage inside Unit-1 containment has increased to 1.01 gpm. The leak rate PT was completed at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />.

The operating crew entered the applicable Technical Specification.

Efforts to determine the location of the leak and reduce the leakage have been unsuccessful.

At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> the shutdown banks were inserted.

At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />, the OATC operates the Steam Dumps to begin cooling down the unit.

INITIATING CUE:

You are requested to classify the emergency event and determine any Protective Action Recommendation if required.

Assume any support personnel designated by the procedure are performing as required.

START TIME:

NAPS Admin-4 Page 5 of 7 STEP 1:

Determine the event category using the emergency action level table index.

SAT STANDARD:

Event is identified as a "Reactor Coolant System" event COMMENTS:

UNSAT STEP 2:

Review the emergency action level tab associated with the event category.

SAT STANDARD :

Emergency action level tab is reviewed.

COMMENTS:

UNSAT STEP 3:

Use available resources to obtain indications of emergency conditions.

SAT STANDARD:

Conditions are reviewed.

COMMENTS:

UNSAT STEP 4:

Verify that an emergency action level has been exceeded.

CRITICAL STEP STANDARD:

Event is classified as a Notification of Unusual Event (NOUE) per SAT TAB B.8 COMMENTS:

UNSAT END OF TASK TIME STOP:

NAPS Admin-4 Page 6 of 7 CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 4

The candidate needs to be able to utilize the procedure and determine that a Notification of Unusual Event (NOUE) needs to be declared.

NAPS Admin-4 Page 7 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit-1 Shutdown Banks had been pulled and an RCS dilution was about to begin, in preparation for a unit start-up.

Due to an increase in containment sump pumping rate, the control room crew completes a leak rate PT and determines that unidentified RCS leakage inside Unit-1 containment has increased to 1.01 gpm. The leak rate PT was completed at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />.

The operating crew entered the applicable Technical Specification.

Efforts to determine the location of the leak and reduce the leakage have been unsuccessful.

At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> the shutdown banks were inserted.

At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />, the GATC operates the Steam Dumps to begin cooling down the unit.

INITIATING CUE:

You are requested to classify the emergency event and determine any Protective Action Recommendation if required.

Assume any support personnel designated by the procedure are performing as required.

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;
b. 1 gpm unidentified LEAKAGE;
c. 10 gpm identified LEAKAGE;
d. 1 gpm total primary to secondary LEAKAGE through all steam generators (SGs); and
e. 500 gallons per day primary to secondary LEAKAGE through anyone SG.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limits for reasons within limits.

other than pressure boundary LEAKAGE.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR Pressure boundary LEAKAGE exists.

North Anna Units 1 and 2 3.4.13-1 Amendments 231/212

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.13.1

NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

Verify RCS operat ional LEAKAGE is within limits by performance of RCS water inventory balance.

FREQUENCY 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> SR 3.4.13.2 Verify steam generator tube integrity is in accordance with the Steam Generator Tube Surveillance Program.

In accordance with the Steam Generator Tube Surveillance Program North Anna Units 1 and 2 3.4.13-2 Amendments 231/212

VIRGINIA POWER NORTH ANNA POWER STATION

~-

EMERGENCY PLAN IMPLEMENTING PROCEDU~5)i)NTI<O-; Li~':7

  • ~.ll.,;

1'or.3YJ

~

~

NUMBER PROCEDURE TITLE REVISION EPIP-l.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 (W ith 3 Attachments)

PAGE 1 of 7 PURPOSE To asses s potential emergency conditions and initiate corrective actions.

ENTRY CONDITIONS Any of the following:

1.

Another station procedure directs initiation of this procedure.

2.

A potential emergency condition is reported to the Shift Manager.

Approvals on File Effective Date 7-I'D-t26

NUMBER PROCEDURE TITLE REVISION EPIP-l.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 2 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

Declaration of the highest emergency class for wh ich an Emergency Action Level is exceeded shall be made.

NOTE:

The PCS is potentially unreliable in the event of an earthquake.

Therefore. PCS parameters should be evaluated for accuracy shoul d this situation occur.

__ 1 EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using.

EMERGENCY ACTION LEVEL TABLE INDEX b) Review EAL Tab associated with event category c) Use Control Room monitors. PCS.

and outside reports to get indications of emergency conditions listed in the EAL Table d) Verify EAL - CURRENTLY EXCEEDED (STEP 1 CONTINUED ON NEXT PAGE) d) 1£ basis for EAL no longer exists when discovered AND no other reason s exist for an emergency declaration. THEN do the following:

RETURN TO procedure in effect.

GO TO VPAP-2802.

NOTIFICATIONS AND REPORTS. to make one-hour. non-emergency reports for classification without declaration.

1£ EAL was NOT exceeded. THEN RETURN TO procedure in effect.

NUMBER PROCEDURE TITLE REVISION EPIP-I.OI EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 3 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

EVALUATE EMERGENCY ACTION LEVELS: (Continued) e) Record procedure initiation:

  • By:

Date:

Time:

f) Initiate a chronological log of events g) Declare position of Station Emergency Manager NOTE:

Assembly. accountability and/or initiation of facility staffing may not be desired during certain situations (e.g.. security event.

severe weather. anticipated grid disturbance) or may have already been completed.

These activities should be implemented as quickly as achievable given the specific situation.

______ 2 CHECK - CONDITIONS ALLOW FOR NORMAL IMPLEMENTATION OF EMERGENCY RESPONSE ACTIONS 1£ deviation from normal emergency response actions warranted. THEN do the following:

a) Refer to Attachment 3.

Considerations for Operations Response Under Abnormal Conditions.

b) Consider applicability of 50.54(x).

c) 1£ classification/assembly announcement deferred. THEN GO TO Step 4.

NUMBER PROCEDURE TITLE REVISION EPI P-l. 01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 4 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__ 3 NOn FY PLANT STAFF OF ALERT OR HIGHER CLASSIFICATION:

a) Check classification - ALERT OR HIGHER b) Check if emergency assembly and accountability - PREVIOUSLY CONDUCTED c) Have Control Room sound EMERGENCY alarm and make announcement on station Gai-Tronics system as follows:

"(Emergency classification) has been declared as the result of (event) d) Repeat Step 3.c a)

GO TO Step 4.

b) Do the following:

1) Have Control Room sound EMERGENCY alarm and make announcement on station Gai-Tronics system as follows:

"(Emergency classification) has been declared as the result of (event)

"All Emergency Response personnel report to your assigned stations" "All contractor personnel not responding to the emergency and all visitors report to the Security Building" "All other personnel report to your Emergency Assembly Areas"

2) Repeat RNO Step 3.b.1.
3) GO TO Step 4.

NUMBER PROCEDURE TITLE REVISION EPIP-l.Ol EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 5 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

Continue through this and all further instructions unless otherwise directed to hold.

______ 4 INITIATE SUPPORTING PROCEDURES:

a) Direct Emergency Communicators to initiate the following procedures:

1) EPIP-2.0l. NOTIFICATION OF STATE AND LOCAL GOVERNMENTS
2) EPIP-2.02. NOTIFICATION OF NRC b) Direct HP to initiate EPIP-4.0l.

RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE c) Establish communications with Security Team Leader:

1) Provide Security with current emergency classification
2) Notify Security which Operations Shift is designated for coverage
3) Direct Security to initiate EPIP-5.09. SECURITY TEAM LEADER CONTROLLING PROCEDURE

NUMBER PROCEDURE TITLE REVISION EPIP-l.OI EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 6 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__ 5 CHECK TSC - ACTIVATED

__ 6 IMPLEMENT EPI P FOR EMERGENCY CLASSIFICATION IN EFFECT:

  • Notification of Unus~al Event -

GO TO EPIP-I.02, RESPONSE TO NOTIFICATION OF UNUSUAL EVENT

  • Alert -

GO TO EPIP-I.03, RESPONSE TO ALERT

  • Site Area Emergency -

GO TO EPIP-I.04, RESPONSE TO SITE AREA EMERGENCY

  • General Emergency -

GO TO EPIP-I.05, RESPONSE TO GENERAL EMERGENCY 1£ TSC NOT activated. THEN do the following:

a) Have STA report to the Control Room.

b) Notify Manager Nuclear Operations or Operations Manager On Call.

c) Consider having Radiological Assessment Director report to the Control Room.

d)

WHEN relief SEM arrives. THEN perform turnover using EPIP-I.OI. Attachment 2.

Turnover Checklist.

NUMBER PROCEDURE TITLE REVISION EPI P-l. 01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 7 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__ 7 NOTI FY OFFSITE AUTHORITI ES OF EMERGENCY TERMINATION:

a) State and local governments (made by LEOF or CEOF when activated) b) NRC

__ 8 NOTI FY STATION PERSONNEL ABOUT THE FOLLOWING:

  • Emergency termination
  • Facility de-activation
  • Selective release of personnel
  • Completion and collection of procedures
  • Recovery

__ 9 TERMINATE EPI P-l. 01:

  • Completed By:

Date:

Time:

-END-

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT PAGE INDEX 1

1 I"\\-F L1.?

CAUTION:

  • Declaration of the highest emergency class for which an EAL is exceeded shall be made.
  • Emergency Action Levels shall be conservatively classified based on actual or anticipated plant conditions.

EVENT CATEGORY:

I.

2.

3.

4.

5.

6.

7.

8.

9.

10.

II.

12.

13.

Safety, Shutdown, or Assessment System Event A

Reactor Coolant System Event B

Fuel Failure or Fuel Handling Accident C

Contai nment Event D

Radioactivity Event E

DELETED Loss of Secondary Coolant.

G Electrical Failure H

Fire I

Securi ty Event J

Hazard to Station Operation K

Natural Events L

Miscellaneous Abnormal Events M

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACT ION LEVEL TABLE 42 ATTACHMENT (TAB A)

PAGE SAFETY. SHUTDOWN. OR ASSESSMENT 1

SYSTEM EVENT 2 of 42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION CAUTION :

EAL C.2 is duplicated below for cross -reference/comparison to EAL A.1 :

C.2.

Probable large radioactivity release initiated by loss of heat sink leading to cor e degradation MODES 1. 2. 3 &4 Loss of Main Feedwat er System. Condensate System and Auxiliary Feedwater System GENERAL EMERGENCY 1.

Loss of function needed for unit HSD condition MODES 1. 2. 3 &4 Total loss of the Charging/SI System OR Total loss of the Main Feedwater and Auxiliary Feedwater systems SITE AREA EMERGENCY 2.

Failure of the Reactor trip setpoint and SITE AREA Reactor Protection coincidences - EXCEEDED EMERGENCY System to initiate and complete a AND required trip while at power Automatic trip from RPS -

FAI LED MODES 1 &2 AND Manual t rip f rom Control Room - FAILED

NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)

PAGE SAFETY

  • SHUTDOWN.

OR ASSESSMENT 1

SYSTEM EVENT

~ of 47 INDICATION CONDITION/APPLICABILITY 3.

Inability to monitor a si gnifi cant transient in progress MODES 1. 2. 3 &4 Most (>75%) or all annunciator alarms on panels "A" to "K" - NOT AVAILABLE AND All computer monitoring capability (e.g.

- NOT AVAILABLE AND CLASSI FICATI ON SITE AREA EMERGENCY 4.

Evacuation of Main Control Room with control not established within 15 minutes ALL MODES Significant transient - IN PROGRESS (e.g.* reactor trip. SI actuation. turbine runback >25% thermal reactor power. thermal power oscillations >10%)

AND Inability to directly monitor anyone of the following using Control Room indications:

Subcriticality Core Cooling Heat Sink Vessel Integrity Containment Integrity Evacuation of the Control Room SITE AREA with local shutdown control not EMERGENCY established within 15 minutes

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)

PAGE

SAFETY, SHUTDOWN, OR ASSESSMENT 1

SYSTEM EVENT 4 of 47 INDICATION Loss of any of the following systems:

Service Water Component Cooling

.RHR CONDITION/APPLICABILITY 5.

Total loss of function needed for unit CSD condition MODES 5 &6 Secondary system cooling capability - UNAVAILABLE AND CLASSI FICATI ON ALERT AND RCS temperature GREATER THAN 140 0 F 6.

Fail ure of the Reactor trip setpoint and ALERT Reactor Protection coincidences - EXCEEDED System to com~lete a trip which ta es the AND Reactor Subcritical Automatic trip from RPS -

MODES 1 &2 FAI LED AND Manual trip - REQUIRED AND Manual trip from Control Room - SUCCESSFUL

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)

PAGE SAFETY. SHUTDOWN.

OR ASSESSMENT 1

SYSTEM EVENT I) of 4?

INDICATION CONDITION/APPLICABILITY 7.

Unplanned loss of safety system annunciators with compensatory indicators unavailable or a transient in progress MODES 1. 2. 3 &4 Unplanned loss of most

(>75%) or all annunciator alarms on panels "A" to "K"

for GREATER THAN 15 minutes AND All computer monitoring capability (e.g.. PCS)

- NOT AVAILABLE OR CLASSI FICATION ALERT 8.

Evacuation of Main Control Room required ALL MODES Significant transient -

INITIATED OR IN PROGRESS (e.g.. reactor trip. SI.

turbine runback > 25%

thermal reactor power.

thermal power oscillations

> 10%)

Evacuation of the Control Room with shutdown control established within 15 minutes ALERT 9.

Inability to reach required mode within technical specification limits Intentional reduction in power. load or temperature lAW T.S. Action Statement -

HAS COMMENCED Non FICAnON OF UNUSUAL EVENT MODES 1. 2. 3 &4 AND T.S. Action Statement time limit for mode change -

CANNOT BE MET

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)

PAGE SAFETY. SHUTDOWN.

OR ASSESSMENT 1

SYSTEM EVENT 6 of 42 Main Steam INDICATION CLASSI FICATI ON RCS NOTI FICATION OF UNUSUAL RCS pressure - LESS EVENT THAN 2000 psig OR NOT Protection System -

IN SERVICE AND Any indication after lift or actuation that Pressurizer Safety or PORV - REMAINS OPEN AND Flow - UNISOLABLE CONDITION/APPLICABILITY

10. Failure of a safety or relief valve to close after pressure reduction. which may affect the health and safety of the public MODES 1. 2. 3. 4 &5 Excessive Steam Generator Safety.

PORV or Decay Heat Release flow as indicated by rapid RCS cool down rate AND

11. Unplanned loss of most or all safety system annunciators for greater than 15 minutes MODES 1. 2. 3 &4 Main Steam pressure greater than 100 psi below setpoint of affected valve Unplanned loss of most

<>75%) or all annunciators on panels "A" to "K" for GREATER THAN 15 minutes NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)

PAGE SAFETY

  • SHUTDOWN.

OR ASSESSMENT 1

SYSTEM EVENT 7 of 42 CONDITION/APPLICABILITY

12. Loss of communications capabil i ty ALL MODES INDICATION Station PBX phone system -

FAI LED Station Gai-tronics system - FAILED AND Station UHF radio system -

FAILED CLASSI FI CATI ON NOTI FICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-1. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM EVENT 1

R of 47 Any t wo of a). b) or c) exist GENERAL and the third i s imminent:

EMERGENCY a)

Fuel clad integrity failure as indica t ed by any of the fol lowing :

RCS specific activity greater than or equal to 300.0

~ C i / g r a m dose equivalent 1-131 OR CONDI TION/APPLICABILITY 1.

Loss of 2 of 3 fis sion product bar ri ers with potential lo ss of 3rd bar rier ALL MODES INDICATION CLASSI FICATION 5 or more core exit thermocouples greater than 1200 0 F OR Containment High Range Radiation Monitor RM -RMS-165. -166 or RM-RMS-265. -266 GREATER THAN 1.88xl02 R/hr b)

Loss of RCS integrity as indirated by any of the foll owi ng:

RCS pressure greater than 2735 psig OR Loss of Reactor Coolant in progress c)

Los s of containment integri ty as indicat ed by any of t he f ol l owi ng:

Containment pre ssure greater t han 60 psia and not decrea sing OR Rel ease path to envi ronment -EXISTS

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM EVENT 1

g of 42 CONDITION/APPLICABILITY INDICATION 2.

Fuel fa ilure with steam generator tube rupture ALL MODES Any two of a), b) or c) exist and the third is imminent:

a)

Fuel clad integrity failure as indicated by any of the following:

  • RCS specific activity greater than 300 ~Ci/gram dose equivalent 1-131 OR 5 or more core exit thermocouples GREATER THAN 1200 of OR High Range Letdown radiation monitor 1-CH-RI -128 or 2-CH-RI -228 GREATER THAN 5.9 x 104 mR/hr b)

Steam Generator tube rupture as indicated by both of the following:

  • SI coincidence - SATISFIED AND

Loss of secondary integrity associated with ruptured steam generator pathway as indicated by any of the following:

  • Steam Generator PORV - OPEN OR Main Steam Code Safety Valve - OPEN Loss of secondary coolant outside containment - IN PROGRESS CLASSI FICATION GENERAL EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM EVENT 1

10 of 42 CLASSIFICATION SITE AREA EMERGENCY INDICATION Primary system leak (LOCA)

- IN PROGRESS AND Safety Injection - REQUIRED AND RCS subcooling based on Core Exit Thermocouples -

LESS THAN 30° F 3.

Res 1eak rate exceeds makeup capacity MODES 1. 2. 3. &4 CONDITION/APPLICABILITY OR RCS inventory cannot be maintained based on pressurizer level or RVLIS indication 4.

Gross primary to secondary leakage with loss of offsite power MODES 1. 2. 3. &4 Steam Generator Tube Rupture - IN PROGRESS AND Safety Injection - REQUIRED AND Vent Vrnt A MGPI Monitor SITE AREA EMERGENCY RM-VG-179 GREATER THAN 1.25 x 108 ~Ci/sec Steam Generator Blowdown monitor on affected pathway RM-SS-122.

-222 RM-SS-123.

-223 RM-SS-124.

- 2211 GREATER THAN 1x106 cpm AND A subsequent loss of offsite power indicated by zero volts on voltmeters for 4160V buses D. E. & F

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVE L TABLE 42 ATTACHMENT (TAB B).

PAGE REACTOR COOLANT SYSTEM EVENT 1

11 of 47 Pressurizer level cannot be ALERT maintained greater than 20%

with one (1) Charging/SI pump in operation AND RCS inventory balance indicates leakage - greater than 50 gpm CONDITION/APPLICABILITY 5.

RCS l eak rate limit

- EXCEEDED MODES 1. 2. 3. &4 INDICATION CLASSI FICATI ON 6.

Gross primary to '

secondary leakage MODES 1. 2. 3. &4 primary to leakage of offsite AND Vent Vent A MGPI Monitor ALERT ALERT Intentional reduction in power. load or temperature lAW T.S. 3.4.13 primary-to -secondary leakage LCO Action Statement Steam Generator Tube Rupture IN PROGRESS AND Safety Injection - REQUIRED Excessive secondary with loss power MODES 1. 2. 3. &4 7.

RM-VG-179 GREATER THAN 1.73 x 106 ~Ci/sec Steam Generator Blowdown monitor on affected pathway RM-SS-122.

-222 RM-SS -123.

-223 RM-SS-124*

-224 GREATER THAN 1x105 cpm AND A subsequent loss of offsite power indicated by zero volts on voltmeters for 4160V buses D. E. & F

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM EVENT 1

12 of 42 CONDITION/APPLICABILITY 8.

RCS operational leakage requiring plant shut down IAW 1. S. 3.4.13 MODES 1. 2. 3. &4 INDICATION Intentional reduction in power load or temperature lAW T.S.

3.4.13 leakage limit action statement - HAS COMMENCED CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

n of 47 INDICATION CONDITION/APPLICABILITY 1.

Probable large radioactivity release initiated by LOCA with ECCS failure leading to core degradation ALL MODES Loss of reactor coolant in progress AND RCS specif i c activity -

greater than 300 ~Ci/gram dose equivalent 1-131 OR Containment High Range Radiation Monitor RM-RMS-165. -166 or RM-RMS-265. -266 GREATER THAN

1. 88x102 R/hr CLASSI FICATI ON GENERAL EMERGENCY AND High or low head ECCS flow not being delivered to the core (if expected by plant conditions)

CAUTION :

EAL A.l is duplicated below for cross -reference/comparison to EAL C.2 :

A.I.

Loss of f unct i on Total l oss of the needed for unit Charging/51 System HSD conditi on SITE AREA EMERGENCY MODES 1. 2. 3 &4 OR Total loss of the Main Feedwater and Auxiliary Feedwater systems 2.

Probable large radioactivity release initiated by loss of heat sink leading to core degradation MODES 1. 2. 3 &4 Loss of Main Feedwater System.

GENERAL Condensate System and Auxiliary EMERGENCY Feedwater System

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

14 of 42 INDICATION Turbine Driven Auxiliary Feedwater Pump not operable AND Restoration of either of the above not likely within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> CONDITION/APPLICABILITY 3.

Probable large radi oacti vi ty release initiated by failure of protection system to bring Rx subcritical and causing core degradation ALL MODES 4.

Probable large radioactivity release initiated by loss of AC power and all feedwater ALL MODES Rx nuclear power after a trip - greater than 5%

AND RCS pressure greater than or equal to 2485 psig OR Containment pressure and temperature rapidly increasing Loss of all onsite and offs ite AC power AND CLASSI FI CATI ON GENERAL EMERGENCY GENERAL EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

15 of 42 CONDITION/APPLICABILITY 5.

Probable large radioactivity release initiated by LOCA with loss of ECCS and containment cooling ALL MODES INDICATION Loss of reactor coolant in progress AND High or low head ECCS flow not being delivered to the core (if expected by plant conditions)

Containment RS sump temperature greater than 1900F and NOT decreasing OR All Quench Spray and Recirculation Spray systems

- NOT OPERABLE CLASS! FICATION GENERAL EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

16 of 42 CONDITION/APPLICABILITY 6.

Core damage with possible loss of coolable geometry MODES 1. 2. 3. &4 INDICATION a)

Fuel clad failure as indicated by any of the foll owi ng:

RCS Specific activity greater than 60

/lCi/gram dose equivalent 1-131 OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 GREATER THAN 1.2x104 mR/hr AND b)

Loss of cooling as indicated by any of the following:

5 confirmed core exit thermocouples greater than 1200 0 F OR Core delta T - zero OR Core delta T - rapidly diverging CLASSI FICATION SITE AREA EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP -l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

17 of 47 INDICATION CONDITION/APPLICABILITY 7.

Major fuel damage accident with radioactivity release to containment or fuel buil di ngs ALL MODES Water level in Rx vessel during refueling below the top of core Water level in spent fuel pool below top of spent fuel CLASSI FICATION SITE AREA EMERGENCY AND Verified damage to irradiated fuel resulting in readings on Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 2.69 x 108 ~Ci/sec 8.

Severe Fuel Clad High Range Letdown ALERT Damage radiation monitor MODES 1. 2. 3.

& 4 l -CH-RI -128 or 2-CH-RI-228 Increases to GREATER THAN Hi Hi Alarm setpoint (representing 1% fuel failure) within 30 minutes and remains for at least 15 minutes OR ReS specifi c activity -

greater than 300 ~Ci/gram dose equivalent 1-131

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

1R of 47 CLASSIFICATION ALERT INDICATION Verified accident involving damage to irradiated fuel AND Health Physics confirm s fission product release from fuel OR CONDITION/APPLICABILITY 9.

Fuel damage accident with release of radioactivity to containment or fuel buil di ngs ALL MODES Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 1.99 x 106 ~Ci/sec

10. Potential for fuel damage to occur during refueling MODE 6 Continuing uncontrolled decrease of water level in Reactor Refueling Cavity or Spent Fuel Pool ALERT

NUMBER ATTACHMENT TITLE REVISION EPI P-1. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

19 of 4?

CONDITION/APPLICABILITY

11. Fuel clad damage indication MODES 1. 2. 3. &4 INDICATION Intentional reduction in power. load or temperature lAW reactor coolant activity T.S. Action Statement - HAS COMMENCED OR High Range Letdown radiation monitor l-CH-RI-128 or 2-CH-RI-228 Increases to GREATER THAN Hi Alarm setpoint (representing 0.1%

fuel failure) within 30 minutes and remains for for at least 15 minutes CLASSI FICATI ON NOTI FICATION OF UNUSUAL EVENT

12. Independent Spent Fuel Storage Installation (lSFSI) event ALL MODES Verified Sealed Surface Storage Cask (SSSC) seal leakage OR Sealed Surface Storage Cask (SSSC) dropped or mishandled NOTI FICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-1. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB D)

PAGE CONTAINMENT EVENT 1

?O of 4?

INDICATION CONDITION/APPLICABILITY 1.

Extremely high containment radiation. pressure and temperature MODES 1. 2. 3. &4 Containment High Range radiation monitor RM-RMS-165. -166 or RM-RMS-265. -266 GREATER THAN 3.76 x 102 R/hr CLASSI FICATION GENERAL EMERGENCY Containment pressure greater than 45 psia and not decreasing 2.

High-high containment radiation. pressure.

and temperature MODES 1. 2. 3. &4 Containment temperature greater than 2800F Containment High Range radiation monitor RM-RMS-165. -166 or RM-RMS-265. -266 GREATER THAN 1.88 x 102 R/hr SITE AREA EMERGENCY Containment pressure -

greater than 27.75 psia and not decreasing Containment temperature -

greater than 200 of

NUMBER ATTACHMENT TITLE REVISION EPIP -l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB D)

PAGE CONTAINMENT EVENT 1

21 of 42 CONDITION/APPLICABILITY 3.

Hi gh Contai nment radiation. pressure and temperature MODES 1. 2. 3. &4 INDICATION Containment High Range radiation monitor RM-RMS -165. -166 or RM-RMS-265. -266 GREATER THAN 8l. 5 R/hr Containment pressure greater than 17 psia OR Containment temperature -

greater than 1500F CLASSI FI CATION ALERT

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEV EL TABLE 42 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT 1

22 of 47 INDICATION CONDITION/APPLICABILITY 1.

Release imminent or in progress and site boundary doses projected to exceed 1.0 Rem TEDE or 5.0 Rem Thyroid CDE ALL MODES HP assessment indicates actual or projected doses at or beyond site boundary greater than 1.0 Rem TEDE or 5.0 Rem Thyroid CDE CLASSI FICATION GENERAL EMERGENCY 2.

Release imminent or in progress and site boundary doses projected to exceed 0.1 Rem TEDE or 0.5 Rem Thyroid CDE ALL MODES HP assessment indicates SITE AREA actual or projected dose at EMERGENCY or beyond Site Boundary exceeds 0.1 Rem TEDE or 0.5 Rem Thyroid CDE

NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT 1

?1 of 47 CONDITION/APPLICABILITY 3.

Effluent relea se greater than 10 times ODCM allowable 1imit ALL MODES INDICATION a)

Any of the following monitors indicate valid readings above the specified values for greater than 15 minute s

  • Clarifier Effluent RM-LW-l11 GREATER THAN 4.8 x 105 cpm
  • Discharge Canal RM-SW-130 or -230 GREATER THAN 5 x 104 cpm
  • Vent Vent A MGPI RM-VG-179 GREATER THAN 1.73 x 106 ~Ci/sec
  • Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 106 ~Ci/sec
  • Process Vent MGPI RM -GW-178 GREATER THAN 1.35 x 107 ~Ci/ sec OR b)

HP assessment (sample results or dose projections) indicate greater than 10 times ODCM allowable 1imit CLASSI FICATION ALERT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT 1

24 of 47 CONDITION/APPLICABILITY 4.

High radiation or airborne contamination levels indicate a severe degradation in control of radioactive material ALL MODES INDICATION Valid readings on any of the following monitors have increased by a factor of 1000 and remain for at least 15 minutes:

Ventilation Vent Multi-sample gaseous or particulate monitor I RM-VG-106 or -105 Control Room Area I RMS-157 CLASSI FICATION ALERT Aux. Bldg. Control Area I RMS-154 Decon. Bldg. Area I RMS-151 Fuel Pool Bridge Area I RMS -153 New fuel storage Area I RMS-152 Laboratory Area I RMS-158 Sample Room Area I RMS-156

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT 1

25 of 42 CONDITION/APPLICABILITY 5.

Effluent release greater than ODCM allowable limit ALL MODES INDICATION a)

Any of the following monitors indicate valid readings above the specified value for more than 1 hour:

  • Clarifier Effluent RM-LW-111 GREATER THAN 4.8 x 104 cpm
  • Discharge Canal RM-SW-130 or -230 GREATER THAN 5 x 103 cpm
  • Vent Vent A MGPI RM-VG-179 GREATER THAN 1.73 x 105 ~Ci/sec
  • Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 105 ~Ci/sec
  • Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 106 ~Ci/sec OR b)

HP assessment (sample results or dose projections) indicates greater than ODCM allowable limit CLASSI FICATION NOTI FICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-1. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB G)

PAGE LOSS OF SECONDARY COOLANT 1

2fi of 42 CONDITION/APPLICABIL ITY INDICAT ION 1.

Major secondary line break with significant primary to secondary 1eakage and fuel damage indicated Conditions a) and b) exist with c):

a)

Uncontrolled loss of secondary coolant - IN PROGRESS AND CLASSI FICATION SITE AREA EMERGENCY b)

RCS specific activity exceeds MODES 1. 2. 3. &4 limits of T.S. Figure 3.4.16 -1 OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI -228 GREATER THAN Hi Alarm setpoint AND c)

Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 6.21 x 107

~ C i / s e c OR Affected path way Steam Gene rator Slowdown monitor RM-SS -122. -123. -124.

-222. -223. -224 GREATER THAN 1 x 106 cpm OR Affected pathway Main Stea m Line High Range moni tor RM-MS -170. -171. -172.

-270. -271. -272 GREATER THAN 12.2 mR/hr

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB G)

PAGE LOSS OF SECONDARY COOLANT 1

'17 of 4?

CONDITION/APPLICABILITY 2.

Majo r secondary line break with significant primary to secondary leakage MODES 1. 2. 3. &4 3.

Major secondary line break MODES 1. 2. 3. &4 INDICATION Uncontrolled loss of secondary coolant - IN PROGRESS AND Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 1.76 x 106 ~Ci/sec Steam Generator Blowdown monitor on affected pathway RM-SS-122. -123. -124 RM-SS-222. -223. -224 GREATER THAN lx l05 cpm OR Main Steam Line High Range monitor on affected pathway RM-MS-170. -171. -172 RM-MS-270. -271. -272 GREATER THAN 0.14 mR/hr Uncontrolled loss of secondary coolant - IN PROGRESS CLASSI FICATION ALERT NOTI FICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB H)

PAGE ELECTRICAL FAILURE 1

7R of 47 CONDITION/APPLICABILITY INDICATION CLASSIFICATION l.

Loss of offsite and The following conditions exist SITE AREA onsite AC power for for greater than 15 minutes:

EMERGENCY more than 15 minutes Ammeters for 4160V Reserve ALL MODES Station Service Buses D.

E.

& F all indicate - zero (0) amps AND Ammeters for 4160V Station Service Buses A. B. & Call indicate - zero (0) amps AND Ammeters for 4160V Emergency Buses H &J both indicate - zero (0) amps 2.

Loss of all onsite The following conditions exist SITE AREA DC power for greater for greater than 15 minutes:

EMERGENCY than 15 minutes All station battery ALL MODES voltmeters indicate zero (0) volts AND No light indication available to Reserve Station Service breakers 1501. 15El and 15Fl

NUMBER ATTACHMENT TITLE REVISION EPI P-I. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB H)

PAGE ELECTRICAL FAILURE 1

?g of 4?

CONDITION/APPLICABILITY INDICATION CLASSI FICATION CAUTION :

EAL A.l i s duplicated below for cross-reference/ compari son to EAL H.3:

A.I.

Loss of function needed for unit HSD condition MODES 1. 2. 3 &4 Total lo ss of t he Charging/SI System OR Tot al loss of the Main Feedwater and Auxiliary Feedwater Systems SITE AREA EMERGENCY 3.

Loss of all offsite Ammeters for 4160V Reserve ALERT and onsite AC power Station Service Buses D.

E.

& F all indicate - zero (0)

ALL MODES amps AND Ammeters for 4160V Station Service Buses A. B. & Call indicate - zero (0) amps AND Ammeters for 4160V Emergency Buses Hand J

both indicate - zero (0) amps 4.

Loss of all onsite All station battery ALERT DC power voltmeters indicate - zero (0) volts ALL MODES AND No light indication available to Reserve Station Service Breakers 1501. 15E1 and 15Fl

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB H)

PAGE ELECTRICAL FAILURE 1

i0 of 42 CONDITION/APPLICABILITY 5.

Loss of offsite power or onsite AC power capabil ity ALL MODES INDICATION Unit main generator and both emergency diesel generators out of service OR Loss of all 34.5 KV reserve station service buses CLASSI FICATION NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTI ON LEVEL TABLE 42 ATTACHMENT (TAB 1)

PAGE FIRE 1

11 of 47 CONDITION/APPLICABILITY 1.

Fire resulting in degradation of safety systems MODES 1. 2. 3. &4 2.

Fire potentially affecting station safety systems MODES 1. 2. 3. &4 3.

Fire lasting greater than 10 minutes in Protected Area or Service Water Pump/Valve House ALL MODES INDICATION Fire which causes major degradation of a safety system function required for protection of the public AND Affected systems are caused to be NOT operable as defined by Tech. Specs.

Fire which has potential for causing a safety system not to be operable as defined by Tech.

Specs.

Fire within the Protected Area or Service Water Pump/Valve House which is not under control within 10 minutes after Fire Brigade - DISPATCHED CLASSI FI CATION SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-1. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB J)

PAGE SECURITY EVENT 1

1/ of 4/

CONDITION/APPLICABILITY 1.

Loss of physical control of the facil ity ALL MODES 2.

Immi nent loss of physical control of the plant ALL MODES 3.

Ongoing Security compromise ALL MODES INDICATION A hostile force has taken control of plant equipment such that plant personnel are unable to operate equipment required to maintain safety functions A confirmed security event within a plant Vital Area OR A notification from the site security force that an armed attack. explosive attack. airliner impact.

or other hostile action is occurring or has occurred within the Protected Area A confirmed security event within the Protected Area A validated notification from NRC of an airliner attack threat less than 30 minutes away A notification from the site security force of an armed attack. explosive attack. airliner impact. or other hostile action within the Owner Controlled Area CLASSIFICATION GENERAL EMERGENCY SITE AREA EMERGENCY ALERT

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB J)

PAGE SECURITY EVENT 1

33 of 47 CONDITION/APPLICABILITY INDICATION CLASSIFICATION 4.

Security threat.

unauthorized attempted entry. or attempted sabotage ALL MODES A credible site -specific security threat notification OR A validated notification from NRC providing information of an aircraft threat A confirmed security event which indicates a potential degradation in the level of safety of the plant such as a violent civil disturbance or strike action. attempted sabotage. a hostage/extortion situation. or attempted intrusion in the Protected Area NOTI FICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION 1

34 of 42 CONDITION/APPLICABILITY 1.

Aircraft damage to vital plant systems MODES 1. 2. 3. &4 2.

Severe explosive damage MODES 1. 2. 3. &4 INDICATION Aircraft crash which affects vital structures by impact or fire Explosion which results in severe degradation of any of the following systems required for safe shutdown:

CLASSI FICATION SITE AREA EMERGENCY SITE AREA EMERGENCY CVCS System OR ECCS System OR 3.

Entry of toxic or flammable gases into plant vital areas other than the Control Room MODES 1.

2. 3. &4 Main/Auxiliary Feedwater System Uncontrolled release of toxic or flammable agents greater than life threatening or explosive limits in Vital Areas AND Evacuation of Vital Area other than Control Room -

REOUIRED OR Significant degradation of plant saf ety systems resulting in loss of a safety system function required for protection of the public SITE AREA EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION 1

~s of 47 CONDITION/APPLICABILITY 4.

Severe missile damage to safety systems MODES 1. 2. 3. &4 INDICATION Missile impact causing severe degradation of safety systems required for unit shutdown CLASSI FICATION SITE AREA EMERGENCY 5.

Aircraft crash on the facil ity ALL MODES Aircraft crash within the Protected Area or Switchyard (other than impact from airliner attack - See TAB J)

ALERT 6.

Explosion damage to Unplanned explosion resulting ALERT facility in damage to plant structure or equipment that affects plant ALL MODES operations 7.

Entry of toxic or Notification of uncontrolled ALERT flammable gases or release of toxic or flammable liquids into plant agent which causes:

facil i ty Evacuation of personnel ALL MODES from plant areas AND Safety related equipment is rendered inoperable 8.

Turbine failure or Failure of turbine/generator ALERT missile impact rotating equipment resulting in casing penetration MODES 1 &2

NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION 1

if) of 42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION 9.

Missile damage to safety related equipment or structures MODES 1.

2. 3. &4 Notification of missile impact ALERT causing damage to safety related equipment or structures
10. Aircraft crash or unusual aircraft activity ALL MODES Confirmed notification of an aircraft crash within the site boundary (other than impact from airliner attack - See TAB J)

OR Unusual aircraft activity in the vicinity of the site as determ ined by the Operations Shift Ma nager/

Station Emergency Manager or the Security Shift Supervisor NOTI FICATION OF UNUSUAL EVENT

11. Train derailment within Protected Area ALL MODES
12. Explosion within Protected Area ALL MODES
13. Onsite or nearsite release of toxic or flammable liquids or gases ALL MODES Confirmed report of train derailment within Protected Area Confirmed report of unplanned explosion within Protected Area Notification of unplanned release of toxic or flammable agents which may affect saf ety of station personnel or equipment NOTIFICATION OF UNUSUAL EVENT NOTIFICATION OF UNUSUAL EVENT NOTI FICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION 1

n of 42 CONDITION/APPLICABILITY
14. Turbine rotating component failure with no casing penetration MODES 1 &2 INDICATION Failure of turbine/generator rotating equipment resulting in immediate unit shutdown CLASSI FICATION NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP -l.01 EME RGENCY ACTION LEVEL TAB LE 42 ATTACHMENT (TAB L)

PAGE NATURAL EV ENTS 1

38 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION l.

Earthquake greater Confirmed earthquake SITE AREA than or equal to DBE which activates the Event EMERGENCY levels Indicator on the Strong Mot ion Accel er ograph MODES 1. 2. 3. &4 AND Alarms on the Peak Shock Annunciator i nd icate a horizontal motion of greater than or equal to 0.12 g or a vertical motion of greater than or equal to 0.08g 2.

Sustained wi nds in Sustained wi nds 150 mph SITE AREA excess of design OR GREATER experienced EMERGENCY level s experienced or projected or projected MODES 1. 2. 3. &4 3.

NOT USED

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB l)

PAGE NATURAL EVENTS 1

~9 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION 4.

Earthquake greater

  • Confirmed earthquake which ALERT than or equal to OBE activates Event Indicator levels on the Strong Motion Accelerograph ALL MODES AND
  • Alarms on the Peak Shock Annunciator indicate a horizontal motion of greater than or equal to 0.06 g or a vertical motion of greater than or equal to 0.04g 5.

Tornado striking Tornado visually detected ALERT facil ity striking structures within the Protected Area or Switchyard ALL MODES 6.

Hurricane winds Hurricane winds 120 mph ALERT near design basis OR GREATER experienced level experienced or projected or projected ALL MODES 7.

Flood near design levels ALL MODES Flood in the Lake Anna ALERT Reservoir with indicated level -

greater than 263 feet MSL

NUMBER ATTACHMENT TITLE REVISION EPI P-l. 01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB l)

PAGE NATURAL EVENTS 1

40 of 42 CONDITION/APPLICABILITY 8.

Earthquake detected ALL MODES 9.

Tornado within Protected Area or Switchya rd ALL MODES INDICATION Confirmed earthquake which activates the Event Indicator on the Strong Motion Accelerograph Tornado visually detected within Protected Area or Switchyard CLASSI FICATION NOTI FICATION OF UNUSUAL EVENT NOTI FICATION OF UNUSUAL EVENT

10. Hurri cane force Confirmation by Weather NOTI FICATION winds projected Center that hurricane force OF UNUSUAL onsite withi n 12 winds (greater than 73 mph)

EVENT hours

~rOjected onsite within 12 ours ALL MODES 1l. 50 year flood Flood in the Lake Anna NOTI FICATION Reservoir with indicated level -

OF UNUSUAL ALL MODES greater than 254 feet MSL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB M)

PAGE MISCELLANEOUS ABNORMAL EVENTS 1

41 of 42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION 1.

Any major internal or external events which singly or in combination cause massive damage to station facilities or may warrant evacuation of the public ALL MODES Shift Manager/Station Emergency GENERAL Manager judgement EMERGENCY 2.

Station conditions Shift Manager/Station Emergency SITE AREA which may warrant Manager judgement EMERGENCY notification of the public near the si t e ALL MODES 3.

Station conditions Shift Manager/Station Emergency ALERT which have the Manager judgement potential to degrade or are actually degrading the level of safety of the station ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE

. 42 ATTACHMENT (TAB M)

PAGE MISCELLANEOUS ABNORMAL EVENTS 1

42 nf 42 INDICATION Shift Manager/Station Emergency Manager judgement that any of the following exist:

CONDITION/APPLICABILITY 4.

Station conditions which warrant increased awareness of state and/or local authorities ALL MODES Unit shutdown is other than a controlled shutdown Unit i s in an uncontrolled condition during operation A condition exists which has the potential for escalation and therefore warrants notification CLASSI FICATION NOTI FICATI ON OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-I.OI TURNOVER CHECKLIST 42 ATTACHMENT PAGE 2

1 of 1 Conduct a turnover between the onshift and relief SEM in accordance with the following checklist.

Use placekeeping aid at left of item. "

". to track completion.

1.

Determine the st at us of primary responder notification.

2.

Determine the st at us of "Report of Emergency to State and Local Governments." EPIP-2. 0I. Attachment 2.

Get completed copies if available.

3.

Determine status of the "Report of Radiological Conditions to the St ate. " EPIP-2.01. Attachment 3.

Get completed copy if available.

4.

Determine status of Emergency Notification System (ENS) communications and completion status of NRC Event Notification Worksheet (EPIP-2.02 ).

5.

Review clas sification and initial PAR status.

6.

Review present plant conditions and status.

Get copy of Critica l Saf et y Functions form.

7.

Review status of station firewatches and re-est abl i sh if conditions allow.

8.

Determine readiness of TSC for activation.

9.

Afte r all information i s obtained. transfer location to TSC. (Consider direct transfer of State &local notifications to LEOF/CEOF.)

10. Call the Control Room and asses s any changes that may have occurred during transition to the TSC.
11. When sufficient personnel are available. the relief SEM is to assume the follow ing responsibilities from the onshift Station Emergency Manager:

a.

Reclassification.

b.

Protective Action Recommendations until LEOF act ivated.

c.

Notifications (i.e.. state. local. &NRC).

Upon LEOF activation.

transfer notification responsibilities except for the NRC ENS.

d.

Site evacuation authorization.

e.

Emergency exposure authorization.

f.

Command/control of onsite response.

12. Formal ly relieve the Int eri m SEM and assume control i n the TSC.

Announce name and facility activation st at us to facility.

NUMBER ATTACHMENT TITLE REVISION EPIP -I.OI CONSIDERATIONS FOR OPERATIONS RESPONSE 42 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 3

I of 2 This attachment provides procedural guidance for controll ing selected emergency response actions when their implementation would have adverse results.

Station Emergency Manager (SEM) approval is required before any required action is postponed. suspended or modified.

The guidance below i s not all -inclusive.

UNANTICIPATED HAZARD EXISTS (e.g.. security event. tornado or toxic release):

II notifying off -duty augmentation could create a safety hazard for personnel coming to the station. THEN consider the following alternatives:

Station Security (if available) can be directed to notify off-duty personnel to report to the remote mustering area (Louisa Fire Training Center).

Corporate Security. at 804-273-3161. can be directed to notify off-duty personnel to report to the remote mustering area (Louisa Fire Training Center).

Corporate Security. at 804-273-3161. can be directed to notify corporate emergency response organization only using CPIP-3.4.

INNSBROOK SECURITY SUPPORT.

Notifications can be deferred unti l hazardous conditions are resolved.

II implementation of emergency response actions could compromise Security Plan response strategies. THEN consider postponing or suspending emergency response actions until threat has been resolved. e.g.. on-site announcement directing assembly and emergency response facility activation. pager activation and call-out per EPIP -3.05. AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION. dispatch of Security Team members to the LEOF per EPIP-3.04. ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY. and staging of road blocks per EPIP-5.04. ACCESS CONTROL.

II assembling on-site personnel for accountability or activation of emergency response facilities could endanger plant personnel. THEN consider postponing emergency assembly until hazardous conditions are resolved. Corporate Security.

at 804-273-3161. can be directed to notify corporate emergency response organization only using CPIP-3.4. INNSBROOK SECURITY SUPPORT. Personnel in unaffected areas on-site can be notified selectively.

II primary ingress/egress route is NOT available. THEN evaluate alternate route for use during site evacuation or off-duty augmentation (e.g.. access via Dyke 1).

NUMBER ATTACHMENT TITLE REVISION EPIP-I.OI CONSIDERATIONS FOR OPERATIONS RESPONSE 42 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 3

2 of 2 ANTICIPATED SITUATION (e.g., forecasted severe weat her or grid disturbance) :

1£ all or part of t he ERO has been staged i n anticipation of a predicted event, THEN not i fy Security to omit performance of augmentation notification (as described in EPIP-3.05, AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION).

1£ adequate controls have been established t o continually account fo r personnel staged in antici pat io n of a predicted event, THEN notify Securi ty t o omit performance of initial accountability (as described in EPIP -5.03, PERSONNEL ACCOUNTABILITY).

1£ a decision has been made to staff t he Central EOF in l i eu of the LEOF, THEN notify Security t hat performance of EPIP -3.04, ACTI VATION OF LOCAL EMERGENCY OPERATIONS FACILITY, is not required.

1£ environmental conditions are hazardous, THEN consult wi t h Security Team Leader about suspending procedural requirements for staging road blocks (lAW EPIP -5.04, ACCESS CONTRO L).

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