ML081840502

Retake Exam 05000338-06-302 Draft Job Performance Measures (Part 2 of 2)

ML081840502
Person / Time
Site:	North Anna
Issue date:	07/02/2008
From:	- No Known Affiliation
To:	NRC/RGN-II
References
50-338/06-302
Download: ML081840502 (63)

Text

NAPS Admin -3 Page 6 of 7 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 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 two segments.

• 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 two segments.

• 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 PERFORMANCE MEASURE 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:

Simulator X Classroom X

_....<..:..._ Perform Simulate _X_

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: Time Start : _

NAME Time Finish : _

Performance Rating: SAT UNSAT _ Performance Time _

Examiner: _ /

NAME SIGNATURE DATE

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

Comments

NAPS Admin -4 Page 3 of 7 SIMULATOR OPERATOR INSTRUCTIONS:

NONE

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 perform ing as required.

NAPS Admin -4 Page 5 of 7 START TIME: _

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 FREQUENCY 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limits by performance of RCS water inventory balance.

SR 3.4.13.2 Verify steam generator tube integrity is in In accordance accordance with the Steam Generator Tube with the Steam Surveillance Program. 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 EPIP-l.01 PROCEDURE TITLE EMERGENCY MANAGER CONTROLLING PROCE DURE (W ith 3 Attachments)

REVISION PAGE 1 of 7 42 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

• ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 2 of 7 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 s ituation occur.

__ 1 EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using Attachment 1. 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 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.

(STEP 1 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-I.OI EMERGENCY MANAGER CONTROLLING PROCEDURE 42

• ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 3 of 7 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 1£ deviation from normal emergency response actions warranted. THEN RESPONSE ACTIONS 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/as sembly announcement deferred. THEN GO TO Step 4.

NUMBER PROCEDURE TITLE REVISION EPI P-l. 01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42

• ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 4 of 7

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

a) Check classification - ALERT OR a) GO TO Step 4.

HIGHER b) Check if emergency assembly and b) Do the following:

accountability - PREVIOUSLY CONDUCTED 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.

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

NUMBER PROCEDURE TITLE REVISION EPIP-l.Ol EMERGENCY MANAGER CONTROLLING PROCEDURE 42

• ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 5 of 7 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

• ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 6 of 7

_ _ 5 CHECK TSC - ACTIVATED 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.

• __ 6 IMPLEMENT EPI P FOR EMERGENCY CLASSIFICATION IN EFFECT:

Turnover Checklist .

• 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

NUMBER PROCEDURE TITLE REVISION EPI P-l. 01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42

• ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 7 of 7

__ 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:

• Give completed EPIPs. forms and other applicable records to Nuclear Emergency Preparedness (TSC Emergency Procedures Coordinator if TSC activated)

• Completed By:

Date:

Time:

-END-

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

• ATTACHMENT 1

INDEX 1

PAGE 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. Safety, Shutdown, or Assessment System Event A

2. Reactor Coolant System Event B

3. Fuel Failure or Fuel Handling Accident C

4. Contai nment Event D

5. Radioactivity Event E

• 6.

7.

8.

9.

DELETED Loss of Secondary Coolant.

Electrical Failure Fire G

H I

10. Securi ty Event J II. Hazard to Station Operation K

12. Natural Events L

13. 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 Loss of Main Feedwat er GENERAL radioactivity Sy stem . Conden sate Sy stem EME RGENCY release initiated and Auxiliary Feedwater by loss of heat Sy stem sink leading to cor e degradation MODES 1. 2. 3 & 4

1. Loss of function

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

2. Failure of the

• Reactor trip setpoint and SITE AREA Reactor Protection coincidences - EXCEEDED EMERGENCY System to init iate 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 CONDITION/APPLICABILITY INDICATION CLASSI FICATI ON

3. Inability to monitor

• Most (>75%) or all SITE AREA a s i gnifi cant annunciator alarms on EMERGENCY transient in panels "A" to "K" - NOT progress AVAILABLE MODES 1. 2. 3 & 4 AND

• All computer monitoring capability (e.g .

• PCS)

- NOT AVAILABLE AND

• 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

4. Evacuation of Main Evacuation of the Control Room SITE AREA Control Room with with local shutdown control not EMERGENCY control not established within 15 minutes established within 15 minutes ALL MODES

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 CONDITION/APPLICABILITY INDICATION CLASSI FICATI ON

5. Total loss of

• Secondary system cooling ALERT function needed for capability - UNAVAILABLE unit CSD condition AND MODES 5 & 6

• Loss of any of the following systems:

• Service Water

• Component Cooling

.RHR AND

• RCS temperature GREATER THAN 140 F0

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 Contro l 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?

CONDITION/APPLICABILITY INDICATION CLASSI FICATION

7. Unplanned loss of

• Unplanned loss of most ALERT safety system (>75%) or all annunciator annunciators with alarms on panels "A" to "K" compensatory for GREATER THAN 15 minutes indicators unavailable or a AND transient in progress

• All computer monitoring capability (e.g .. PCS)

MODES 1. 2. 3 & 4 - NOT AVAILABLE OR Significant transient -

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

turbine runback > 25%

thermal reactor power.

thermal power oscillations

> 10%)

• 8. Evacuation of Main Control Room required ALL MODES Evacuation of the Control Room with shutdown control established within 15 minutes ALERT

9. Inability to reach

• Intentional reduction in Non FICAnON required mode within power. load or temperature OF UNUSUAL technical lAW T.S. Action Statement - EVENT specification limits HAS COMMENCED 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 CONDITION/APPLICABILITY INDICATION CLASSI FICATI ON

10. Failure of a safety

• RCS NOTI FICATION or relief valve to OF UNUSUAL close after pressure

• RCS pressure - LESS EVENT reduction. which may THAN 2000 psig affect the health and safety of the OR public NOT Protection System -

MODES 1. 2. 3. 4 & 5 IN SERVICE AND

• Any indication after lift or actuation that Pressurizer Safety or PORV - REMAINS OPEN AND

• Flow - UNISOLABLE

• Main Steam

• Excessive Steam Generator Safety. PORV or Decay Heat Release flow as indicated by rapid RCS cool down rate AND

• Main Steam pressure greater than 100 psi below setpoint of affected valve

11. Unplanned loss of

• Unplanned loss of most NOTIFICATION most or all safety <>75%) or all annunciators OF UNUSUAL system annunciators on panels "A" to "K" for EVENT for greater than 15 GREATER THAN 15 minutes minutes MODES 1. 2. 3 & 4

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

• ATTACHMENT (T AB A) PAGE SAFETY

• SHUTDOWN. OR ASSESSMENT 1 SYSTEM EVENT 7 of 42 CONDITION/APPLICABILITY INDICATION CLASSI FI CATI ON

12. Loss of

• Station PBX phone system - NOTI FICATION communications FAI LED OF UNUSUAL capabil i ty EVENT ALL MODES

• Station Gai-tronics system - FAILED AND

• Station UHF radio system -

FAILED

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 CONDI TION/APPLICABILITY INDICATION CLASSI FICATION

1. Loss of 2 of 3 Any t wo of a) . b) or c) exist GENERA L fis sion product and the third i s imminent: EMERG ENCY bar ri ers wit h potential lo ss of a) Fuel clad integrity failur e 3rd bar rier as indica t ed by any of th e fol lo wing :

AL L MODES

• RCS specific activity greater than or equal to 300.0 ~ C i / g r a m dose equivalent 1-131 OR 5 or more cor e exit thermocouples greater than 1200 F 0 OR Containmen t High Range Radiation Monitor RM -RMS -165 . - 166 or RM -RMS-265 . - 266 GREATER THAN 1.88xl0 2 R/hr b) Lo ss of RCS integrity as indirated by any of th e f oll owi ng:

• RCS pressure greater than 27 35 ps ig OR Los s of Reactor Coolant in progre ss c) Los s of containment integr i ty as indica t ed by any of t he f ol l owi ng:

• Containmen t 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 CLASSI FICATION

2. Fuel fa ilure with Any two of a), b) or c) exist and the GENERAL steam generator third is imminent: EMERGENCY tube rupture a) Fuel clad integrity failure as ALL MODES ind icated 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

• Steam Generator tube rupture - I N PROGRESS c) 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 seconda ry coolant outside containment - IN PROGRESS

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 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Res 1 eak rate exceeds

• Primary system leak (LOCA) SITE AREA makeup capacity - I N PROGRESS EMERG ENCY MODES 1. 2. 3. & 4 AND

• Safety Injection - REQUIRED AND

• RCS subcooling based on Core Exit Thermocouples -

LESS THAN 30° F OR RCS inventory cannot be maintained based on pressurizer level or RVLIS indication

4. Gross primary to

• Steam Generator Tube SITE AREA secondary leakage Rupture - IN PROGRESS EMERGENCY with loss of offsite power AND MODES 1. 2. 3. & 4

• Safety Injection - REQUIRED AND

• Vent Vrnt A MGPI Monitor 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 1x10 6 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 LE VE L TABLE 42

• ATTACHMENT (TAB B). PAGE REACTOR COOLANT SYSTEM EVENT 1

11 of 47 CONDITION/APPLICABILITY INDICATION CLASSI FICATI ON

5. RCS l eak rate limit

• Pressurizer level cannot be ALERT

- EXCEEDED maintained greater than 20%

with one (1) Charging/SI MODES 1. 2. 3. & 4 pump in operation AND

• RCS inventory balance indicates leakage - greater than 50 gpm

6. Gross primary to ' Steam Generator Tube Rupture ALERT secondary leakage IN PROGRESS MODES 1. 2. 3. & 4 AND Safety Injection - REQUIRED

7. Excessive primary to

• Intentional reduction in ALERT secondary leakage power. load or temperature with loss of offsite lAW T.S. 3.4.13 primary-power to -secondary leakage LCO Action Statement MODES 1. 2. 3. & 4 AND

• Vent Vent A MGPI Monitor 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 INDICATION CLASSIFICATION

8. RCS operational Intentional reduction in power NOTIFICATION leakage requiring load or temperature lAW T.S. OF UNUSUAL plant shut down 3.4.13 leakage limit action EVENT IAW 1. S. 3.4.13 statement - HAS COMMENCED MODES 1. 2. 3. & 4

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 CONDITION/APPLICABILITY INDICATION CLASSI FICATI ON

1. Probable large

• Loss of reactor coolant in GENERAL radioactivity progress EMERGENCY release initiated by LOCA with ECCS AND failure leading to core degradation

• RCS speci f i c activity -

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

1. 88x10 2 R/hr 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 EA L C.2 :

A.I. Loss of f un ct i on

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

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

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 CONDITION/APPLICABILITY INDICATION CLASSI FI CATI ON

3. Probable large

• Rx nuclear power after a GENERAL radi oacti v i ty trip - greater than 5% EMERGENCY release initiated by failure of AND protection system to bring Rx subcritical

• RCS pressure greater than and causing core or equal to 2485 psig degradation OR ALL MODES Containment pressure and temperature rapidly increasing

4. Probable large

• Loss of all onsite and GENERAL radioactivity offs ite AC power EMERGENCY release initiated by loss of AC power and AND all feedwater

• Turbine Driven Auxiliary ALL MODES 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 />

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 INDICATION CLASS! FICATION

5. Probable large

• Loss of reactor coolant in GENERAL radioactivity progress EMERGENCY release initiated by LOCA with loss of AND ECCS and containment cooling

• High or low head ECCS flow not being delivered to the ALL MODES 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

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 INDICATION CLASSI FICATION

6. Core damage with a) Fuel clad failure as SITE AREA possible loss of indicated by any of the EMERGENCY coolable geometry foll owi ng:

MODES 1. 2. 3. & 4

• 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 1.2x10 4 mR/hr AND b) Loss of cooling as indicated by any of the following:

• 5 confirmed core exit thermocouples greater than 1200 F 0 OR Core delta T - zero OR Core delta T - rapidly diverging

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 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

7. Major fuel damage

• Water level in Rx vessel SITE AREA accident with during refueling below the EMERGENCY radioactivity top of core release to containment or fuel buil di ngs Water level in spent fuel ALL MODES pool below top of spent fuel AND

• Verified damage to irradiated fuel resulting in reading s on Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 2.69 x 108 ~Ci/sec

• 8. Severe Fuel Clad Damage MODES 1. 2. 3. & 4

• High Range Letdown radiation monitor l -CH-RI -128 or 2-CH-RI-228 Increases to GREATER ALERT 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 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

9. Fuel damage accident

• Verified accident involving ALERT with release of damage to irradiated fuel radioactivity to containment or fuel AND buil di ngs

• Health Physics confirm s fission ALL MODES product release from fuel OR Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 1.99 x 106 ~Ci/sec

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

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 INDICATION CLASSI FICATI ON

11. Fuel clad damage

• Intentional reduction in NOTI FICATION indication power. load or temperature OF UNUSUAL lAW reactor coolant EVENT MODES 1. 2. 3. & 4 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

12. Independent Spent

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

NUMBER ATTACHMENT TITLE REVISION EPI P-1. 01 EMERGENCY ACTION LEVEL TABLE 42

• ATTACHMENT (TAB D) PAGE CONTAINMENT EVENT 1

?O of 4?

CONDITION/APPLICABILITY INDICATION CLASSI FICATION

1. Extremely high

• Containment High Range GENERAL containment radiation monitor EMERGENCY radiation. pressure and temperature RM-RMS-165. -166 or RM-RMS-265. - 266 MODES 1. 2. 3. & 4 GREATER THAN 3.76 x 102 R/hr

• Containment pressure greater than 45 psia and not decreasing Containment temperature greater than 280 0F

2. High-high

• Containment High Range SITE AREA containment radiation monitor EMERGENCY radiation. pressure.

and temperature RM-RMS-165. -166 or RM -RMS-265. -266 MODES 1. 2. 3. & 4 GREATER THAN 1.88 x 102 R/hr

• 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 (T AB D) PAGE CONTAINMENT EVENT 1

21 of 42 CONDITION/APPLICABILITY INDICATION CLASSI FI CATION

3. Hi gh Contai nment

• Containment High Range ALERT radiation. pressure radiation monitor and temperature RM-RMS -165. - 166 or MODES 1. 2. 3. & 4 RM-RMS-265. - 266 GREATER THAN 8l. 5 R/hr

• Containment pressure greater than 17 psia OR Containment temperature -

greater than 1500F

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

• ATTACHMENT (T AB E) PAGE RADIOACTIVITY EVENT 1

22 of 47 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

1. Release imm inent or

• HP assessment indicates GENERAL in progress and site actual or projected dose s EMERGENCY boundary doses at or beyond site boundary projected to exceed greater than 1.0 Rem TEDE 1.0 Rem TEDE or 5.0 or 5.0 Rem Thyroid CDE Rem Thyroid CDE ALL MODES

2. Release imminent or

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

NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42

• ATTACHMENT (TAB E) PAGE RADIOACTIVITY EVENT 1

?1 of 47 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

3. Effluent relea se a) Any of the following ALERT greater than 10 monitors indicate valid times ODCM allowable readings above the 1imit specified values for greater than 15 minute s ALL MODES

• 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

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

• ATTACHMENT (TAB E) PAGE RADIOACTIVITY EVENT 1

24 of 47 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

4. High radiation or Valid readings on any of the ALERT airborne following monitors have contamination levels increased by a factor of 1000 indicate a severe and remain for at least 15 degradation in minutes:

control of radioactive material

• Ventilation Vent Multi-sample gaseous or ALL MODES particulate monitor I RM-VG -106 or -105

• Control Room Area I RMS-157

• 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 INDICATION CLASSI FICATION

5. Effluent release a) Any of the following NOTI FICATION greater than ODCM monitors indicate valid OF UNUSUAL allowable limit readings above the EVENT specified value for more ALL MODES 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

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 CLASSI FICATION

1. Major secondary Conditions a) and b) exist with c): SITE AREA line break wit h a) Uncontrolled loss of secondary EMERGENCY sign ificant primary coolant - IN PROGRESS to secondary 1eakage and fuel AN D damage indicated b) RCS specific activity exceeds MODES 1. 2. 3. & 4 limits of T.S . Figure 3.4 .16 -1 OR High Range Letdow n 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 Slo wdown monitor RM-SS -122 . -123 . -124 .

- 222. - 223. -224 GREATER THAN 1 x 106 cpm OR Affected pat hway Main Stea m Line Hig h Range moni t or 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 INDICATION CLASSI FICATION

2. Majo r secondary line

• Uncont rolled loss of ALERT break with secondary coolant - IN significant primary PROGRESS to secondary leakage AND MODES 1. 2. 3. & 4

• 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- 22 2. -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

3. Major secondary line Uncontrolled loss of secondary NOTI FICATION break coolant - IN PROGRESS OF UNUSUAL EVENT MODES 1. 2. 3. & 4

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 than 15 minutes ALL MODES for greater than 15 minutes:

• All station battery voltmeters indicate zero (0) volts AND EMERGENCY

• 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 o f 4?

CONDITION/APPLICABILITY INDICATION CLASSI FICATION CAUTION : EAL A.l i s duplicated below for cros s -re f erence/ compari son to EAL H.3:

A.I. Loss of fu nction

• Total lo s s of t he SITE AREA needed f or unit Charging/SI Sy stem EME RGE NCY HSD condition OR MOD ES 1. 2. 3 & 4 Tot al loss of the Main Feedwater and Auxiliary Feedwat er Systems

3. Loss of all offsite

• Ammeter s for 4160V Reserve ALERT and onsite AC power Station Service Bu ses D. E.

& F all indicate - ze ro (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 INDICATION CLASSI FICATION

5. Loss of offsite

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTI ON LEVEL TABLE 42

• ATTACHMENT (TAB 1) PAGE FIRE 1

11 of 47 CONDITION/APPLICABILITY INDICATION CLASSI FI CATION

1. Fire resulting in

• Fire which causes major SITE AREA degradation of degradation of a safety EMERGENCY safety systems system function required for protection of the MODES 1. 2. 3. & 4 public AND

• Affected systems are caused to be NOT operable as defined by Tech. Specs.

2. Fire potentially Fire which has potential for ALERT affecting station causing a safety system not to safety systems be operable as defined by Tech.

Specs.

MODES 1. 2. 3. & 4

• 3. Fire lasting greater than 10 minutes in Protected Area or Service Water Pump/Valve House ALL MODES Fire within the Protected Area or Service Water Pump/Valve House which is not under control within 10 minutes after Fire Brigade - DISPATCHED 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 INDICATION CLASSIFICATION

1. Loss of physical A hostile force has taken GENERAL control of the control of plant equipment EMERGENCY facil ity such that plant personnel are unable to operate equipment ALL MODES required to maintain safety functions

2. Immi nent loss of

• A confirmed security event SITE AREA physical control within a plant Vital Area EMERGENCY of the plant OR ALL MODES 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

• 3. Ongoing Security compromise ALL MODES

• A confirmed security event within the Protected Area A validated notification from NRC of an airliner ALERT 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

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

• ATTACHMENT (T AB J) PAGE SECURITY EVENT 1

33 of 47 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

4. Security threat.

• A credible site -specific NOTI FICATION unauthorized security threat OF UNUSUAL attempted entry. or notification EVENT attempted sabotage OR ALL MODES 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

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

• ATTACHMENT (T AB K) PAGE HAZARD TO STATION OPERATION 1

34 of 42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

1. Aircraft damage to Aircraft crash which affect s SITE AREA vital plant systems vital structures by impact or EMERGENCY fire MODES 1. 2. 3. & 4

2. Severe explosive Explosion which results in SITE AREA damage severe degradation of any of EMERGENCY the following systems required MODES 1. 2 . 3. & 4 for safe shutdown:

• CVCS System OR ECCS System OR Main/Auxiliary Feedwater System

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

• Uncontrolled release of toxic or flammable agents greater than life threatening or explosive limits in Vital Areas SITE AREA EMERGENCY MODES 1. 2. 3. & 4 AND

• Evacuation of Vital Area other than Control Room -

REOUIRED OR Significant degradation of plant saf et y systems resulting in loss of a safety system function required for protection of the public

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 INDICATION CLASSI FICATION

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

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

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 flammable gases or liquids into plant facil i ty ALL MODES Notification of uncontrolled release of toxic or flammable agent which causes:

• Evacuation of personnel from plant areas ALERT 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 Notification of missile impact ALERT safety related causing damage to safety equipment or related equipment or structure s structures MODES 1. 2. 3. & 4

10. Aircraft crash or

• Confirmed notification of NOTI FICATION unusual aircraft an aircraft crash within OF UNUSUAL activity the site boundary (other EVENT than impact from airliner ALL MODES 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

• 11. Train derailment within Protected Area or the Security Shift Supervisor Confirmed report of train derailment within Protected Area NOTIFICATION OF UNUSUAL EVENT ALL MODES

12. Explosion within Confirmed report of unplanned NOTIFICATION Protected Area explosion within Protected OF UNUSUAL Area EVENT ALL MODES

13. Onsite or nearsite Notification of unplanned NOTI FICATION release of toxic or release of toxic or flammable OF UNUSUAL flammable liquids or agent s which may affect saf et y EVENT gases of station personnel or equipment ALL MODES

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

• ATTACHMENT (T AB K) PAGE HAZARD TO STATION OPERATION 1

n of 42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

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

NUMBER ATTACHMENT TITLE REVISION EPIP -l.0 1 EME RG ENC Y ACTION LEVE L TAB LE 42 ATTACHMENT (TAB L) PAGE NATURAL EV ENTS 1

38 of 42 CONDITIO N/APPLIC ABILI TY INDICATION CLASSI FICATIO N

l. Earthquake greater

• Confirmed earthquake SITE AR EA than or equal to DB E which activate s the Event EMERGE NCY le vels Indicator on the Strong Mot io n Accel er ogr aph MOD ES 1. 2. 3. & 4 AND

• Alarms on the Peak Shock Annunci at or i nd icate a horizon tal motion of greater than or equal to 0.12 g or a vertical motion of greate r than or equal to 0.08g

2. Su stained wi nds in Sustained wi nd s 150 mph SITE AR EA excess of des ig n OR GREATER experienced EME RGENCY level s experienced or projected or projected MOD ES 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 near design basis level experienced or projected ALL MODES Hurricane winds 120 mph OR GREATER experienced or projected ALERT

7. Flood near design Flood in the Lake Anna ALERT levels Reservoir with indicated level -

greater than 263 feet MSL ALL MODES

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 INDICATION CLASSI FICATION

8. Earthquake detected Confirmed earthquake which NOTI FICATION activates the Event Indicator OF UNUSUAL ALL MODES on the Strong Motion EVENT Accelerograph

9. Tornado within Tornado visually detected NOTI FICATION Protected Area or within Protected Area or OF UNUSUAL Switchya rd Switchyard EVENT ALL MODES

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 ALL MODES Flood in the Lake Anna Reservoir with indicated level -

greater than 254 feet MSL NOTI FICATION OF UNUSUAL EVENT

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

• ATTACHMENT 1

CONDITION/APPLICABILITY (TAB M)

MISCELLANEOUS ABNORMAL EVENTS INDICATION PAGE 41 of 42 CLASSI FICATION

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

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

• 3. Station conditions which have the potential to degrade or are actually degrading the level of safety of the Shift Manager/Station Emergency Manager judgement ALERT 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 CONDITION/APPLICABILITY INDICATION CLASSI FICATION

4. Station conditions Shift Manager/Station Emergency NOTI FICATI ON which warrant Manager judgement that any of OF UNUSUAL increased awareness the following exist: EVENT of state and/or local autho rities

• Unit shutdown is other than ALL MODES a controlled shutdown Unit i s in an uncontrolled condition during opera tion A condition exists which has the potential for escalation and therefore warrants notification

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

• ATTACHMENT 2

Conduct a turnover between the onshift and relief SEM in accordance with the PAGE 1 of 1 following checklist. Use placekeeping aid at left of item. " ". to track comp letion.

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." EPI P- 2. 0I . Attachment 2. Get completed copies if available.

3. Determine status of the "Report of Radiological Conditions to the St at e . " EPIP-2.01. Attachment 3. Get completed copy if available.

4. Determine stat us of Emergency Notification Sy stem (ENS) commun ications and completion statu s of NRC Event Notification Work sheet (EPIP-2.02 Attachment 1).

5. Review clas sification and initial PAR status.

6. Review present plant conditions and status. Get copy of Critica l

• 7.

8.

Saf et y Function s form.

Review status of station firewatches and re -es t abl i s h if conditions allow.

Determine readines s of TSC for activation.

9. Afte r all information i s obtained. transfer location to TSC. (Consider direct tran sfer of State & local notificatio ns 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. Recla ssification.

b. Protective Action Recommendations until LEOF act ivated.

c. Notifications (i.e .. state. local. & NRC). Upon LEOF activation.

transfer notification responsibilitie s except for the NRC ENS.

d. Site evacuation authorization.

e. Emergency exposure authorization.

f. Command/control of onsite response.

12. Formal l y relieve the I nt e r i m SEM and as sume control i n the TSC.

Announce name and facility act ivation 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 adver se 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 CONT ROL.

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 ant icipation of a predicted event , THE N 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 estab lished t o continua lly account fo r per sonnel staged in antici pat io n of a pre dicted event , THE N notify Secur i ty t o omit perfo rmance of in itia l accountability (as descr i bed in EPIP -5 .03 , PERSONNEL ACCOUNTABILITY) .

1£ a decision has been mad e to staff t he Centra l EOF in l i eu of the LEOF , THE N notify Security t hat performance of EPIP -3 . 04, ACTI VATION OF LOCA L EMERGENCY OPERAT IONS FACILITY , is not req uired .

1£ environmental conditions are hazardous , THEN consult wi t h Security Team Leader about suspending procedur al requirements for staging road blocks (lAW EPIP -5 .0 4, ACCESS CONTRO L) .