ML040340545

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9 to EPIP-1.01, Emergency Manager Controlling Procedure
ML040340545
Person / Time
Site: North Anna  
Issue date: 01/23/2004
From: Jennifer Davis
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
04-042
Download: ML040340545 (55)
v • d • e


Text

K VIRGINIA ELECTRIC AND POWI R COMPANY RIChMOND, VIRGINIA 23261 January 23, 2004 U.S. Nuclear Regulatory Commission Serial No.04-042 Attention: Document Control Desk NAPS/MPW Washington, D.C. 20555 Docket Nos. 50-338/339 License Nos. NPF-4/7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REVISIONS TO EMERGENCY PLAN IMPLEMENTING PROCEDURES Pursuant to 10 CFR 50.54(q), enclosed is a recent revision to the North Anna Power Station Emergency Plan Implementing Procedure. This revision does not implement actions that decrease the effectiveness of our Emergency Plan. The Emergency Plan and Implementing Procedures continue to meet the standards of 10 CFR 50.47(b).

Please update your manual by performing the actions described in Attachment 1, Tabulation of Changes.

Very truly yours,

~~eV~avis e Vice President Commitments Stated or Implied: None.

Enclosures cc:

U.S. Nuclear Regulatory Commission (2 copies)

Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 Mr. M. T. Widmann NRC Senior Resident Inspector North Anna Power Station 5OY5

ATTACHMENT 1 TABULATION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY REVISIONS TO NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE Enclosed is a recent revision to the North Anna Power Station Emergency Plan Implementing Procedure (EPIP). Please take the following actions in order to keep your manual updated.

REMOVE AND DESTROY DATED INSERT EFFECTIVE DATE EPIP -1.01, Rev. 38 l 07/01/03 1 EPIP-1.01, Rev. 39 01/15/04 EmerQency Plan Privacy and Proprietary Material has been removed. Reference Generic Letter No. 81-27.

DATE:

2004-01-15 PAGE:

2 PAGE:

1 NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION DOCUMENT NUMBER

-- ------0---------

EPIP-1.01 EPIP-1.02 EPIP-1.03 EPIP-1. 04 EPIP-1.06 EPIP-1. 06 EPIP-2. 02 EPIP-Z.02 EPIP-3.02 EPIP-3.03 EPIP-3.04 EPIP-3.65 EPIP-4.01 EPIP-4.02 EPIP-4.03 EPIP-4. 04 EPIP-4.05 EPIP-4. 06 EPIP-4. 07 EPIP-4. 08 EPIP-4.09 EPIP-4.i0 EPIi-4.13 REV 039 011 014'.

014 016 004 025 els 021 015 o02 020 015.

009 009 009 014 014 014 il1 009 APPROVAL

    • DATEWm 01/15/04 09/07/99 09/07/99 09/07/99 09/07/99 09/05/01 08/13/02 08/13/02 03/04/03 03/04/03 07/14/98 04/02/03 06/24/03 06/24/03 12/20/93 11/21/94

@1/28/00 12/21/95 09/29/SO 05/10/02 06/24/13 08/13/02 09/29/s0 EFFECT**

    • DATE**

DOCUMENT TITLE 01/15/04 EMERGENCY MANAGER CONTROLLING PROCEDURE 10/01/99 RESPONSE TO NOTIFICATION OF UNUSUAL EVENT 10/01/99 RESPONSE TO ALERT 10/01/99 RESPONSE TO SITE AREA EMERGENCY 10/01/99 RESPONSE TO GENERAL EMERGENCY 09/05/01 PROTECTIVE ACTION RECOMNENDATIONS 08/28/02 NOTIFICATION OF STATE AND LOCAL GOVERNnENTS 08/28/02 NOTIFICATION OF NRC 03/17/03 ACTIVATION OF TECHNICAL SUPPORT CENTER 03/17/03 ACTIVATION OF OPERATIONAL SUPPORT CENTER 07/20/98 ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY 04/0803 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 07/81/03 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 07/01/03 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE 01/01/94 DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE 11/28/94 EMERGENCY PERSONNEL RADIATION EXPOSURE

  • 02/04/00 RESPIRATORY PROTECTION AND KI ASSESSMENT 12/28/95 PERSONNEL MONITORING AND DECONTAMINATION 10/06/OS PROTECTIVE MEASURES 06/19/02 INmAL OFFSITE RELEASE ASSESSMENT 07/01S/03

-SOURCE TERM ASSESSMENT 08/28/02 DETERMINATION OF X/Q 10/06/00 OFFSITE RELEASE ASSESSMENT WITH ENVIRONnENTAL DATA

DATE: 2004-01-15 PAGE: 2 DOCUMENT NUMBER

- 4--

EPIP-4.14 EPIP-4.16 EPIP-4.16 EPIP-4.17 EPIP-4.21 EPIP-4.21 EPIP-4.24 EPIP-4.26 EPIP-4.28 EPIP-4.30 EPIP-4.31 EPIP-4.33 EPIP-4.34 EPIP-4.35 EPIP-s.01 EPIP-5.03 EPIP-. 04 EPIP-5.05 EPIP-5.07 EPXP-;5.08 EPIP-5.*09 EPIP-6.0i NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION REV W--

007 1l1 015 016 013 00s 613 012 007 0os 003 003 603 000 011 616 016 013 012 608 064 007 APPROVAL

    • DiTE*

12/20/93 62/1 8/0.0 12/13/02 12/13/02 12/20/93 04/02/03 06/24/03 01/09/97 04/05/02 06/20/94 11/28/06 12/13/62 06/24/03 i211/96 02/18/60 03/04/03 06/25/96 66/24/03 04/02/03 08/02/02 65/12/99 EFFECT**

  • DATE*

01/01/94 12/28/02 12/18/02 12/18/02 0 i/O 1/94 04/08/03 07/01/03 81/14/97 04/09/02 06/20/94 l1/3@/6 S 12/18/82 07/01/03 12/17/96 62/28/60 03/17/03 07/62/96 07/61/03 04/68/03 68/15/62

.5/17/99 DOcUMENT TITLE INPLANT FONITORING ONSITE MONITORING OFFSITE MONITORING MONITORING OF EMERGENCY RESPONSE FACILITIES MONITORING OF LEOF EVACUATION AND REMOTE ASSEMBLY AREA MONITORING GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY HIGH LEVEL ACTIVITY SAMPLE ANALYSIS TSC/LEOF RADIATION MONITORING SYSTEM USE OF MIDAS CLASS A MODEL USE OF MIDAS CLASS B MODEL HEALTH PHYSICS NETWORK COMIUNICATIONS FIELD TEAM RADIO OPERATOR INSTRUCTIONS CHEMISTRY SAMPLING TRANSPORTATION OF CONTAMINATED INJURED PERSONNEL PERSONNEL ACCOUNTABILITY ACCESS CONTROL SITE EVACUATION ADMINISTRATION OF RADIOPROTECTIVE DRUGS DAMAGE CONTROL GUIDELINE SECURITY TEAM LEADER CONTROLLING PROCEDURE RE-ENTRY/RECOVERY GUIDELINE

. I

,. I

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 (With 3 Attachments)

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

LEVEL2 COPY THIS DOCUMENT SHALL BE VERIFIED TO A CONTROLLED SOURCE AS REQUIRED TO PERFORM WORK 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

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 PAGE L _

~~~~~~~~~~~~~~~~~~

of 7

-FAH l

ACTION/EXPECTED RESPONSE F-]

RESPONSE NOT OBTAINED F-a CAUTION:

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

a a

a a

NOTE:

The PCS is potentially unreliable in the event of Therefore. PCS parameters should be evaluated for this situation occur.

an earthquake.

accuracy should

_____1 EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using. EMERGENCY ACTION LEYEL 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) IF basis for EAL no longer exists when discovered AND no other reasons 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.

IF EAL was NOT exceeded, THEN RETURN TO procedure in effect.

(STEP 1.CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 PAGE 3 of 7

-EEH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H-1 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 NORMAL IMPLEMENTATION OF RESPONSE ACTIONS FOR EMERGENCY IF deviation from normal emergency response actions warranted, THEN do the following:

a) Refer to Attachment 3.

Considerations for Operations Response Under Abnormal Conditions.

r b) Consider applicability of 50.54(x).

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

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 PAGE 4 of 7

-EEH ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED l-

_____3 NOTIFY PLANT STAFF OF ALERT OR HIGHER CLASSIFICATION:

a) Check classification - ALERT OR HIGHER b) Check if emergency assembly and accountability -

PREVIOUSLY CONDUCTED 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.

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-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 PAGE 1

~~~~~~~~~~~~~~~~~~

of 7

-EU l

ACTION/EXPECTED RESPONSE F-I RESPONSE NOT OBTAINED F-CAUTION:

Continue through this and all further directed to hold.

instructions unless otherwise

_____4 INITIATE SUPPORTING PROCEDURES:

a) Direct Emergency Communicators to initiate the following procedures:

1) EPIP-2.01. NOTIFICATION OF STATE AND LOCAL GOVERNMENTS
2) EPIP-2.02. NOTIFICATION OF NRC b) Direct HP to initiate EPIP-4.01. 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-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 PAGE 6 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

.,__5 CHECK TSC - ACTIVATED IF 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-1.01. Attachment 2.

Turnover Checklist.

_____6 IMPLEMENT EPIP FOR EMERGENCY CLASSIFICATION IN EFFECT:

  • Notification of Unusual Event -

GO TO EPIP-1.02. RESPONSE TO NOTIFICATION OF UNUSUAL EVENT

  • Alert -

i GO TO EPIP-1.03, RESPONSE TO ALERT

  • Site Area Emergency -

GO TO EPIP-1.04, RESPONSE TO SITE AREA EMERGENCY

  • General Emergency -

GO TO EPIP-1.05, RESPONSE TO GENERAL EMERGENCY

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 39 PAGE 7 of 7

_1EH ACTION/EXPECTED RESPONSE 1-1 RESPONSE NOT OBTAINED

]-

_____7 NOTIFY OFFSITE AUTHORITIES OF EMERGENCY TERMINATION:

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

_____8 NOTIFY STATION PERSONNEL ABOUT THE FOLLOWING:

. Emergency termination

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

_____9 TERMINATE EPIP-1.01:

  • Completed By:

Date:

Time:

-END-

/

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT PAGE INDEX

~~ ~ ~~ ~~~~~~~1 pf A9 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:

TAB

1.

Safety. Shutdown, or Assessment System Event...................... A

2.

Reactor Coolant System Event...................................... B

3.

Fuel Failure or Fuel Handling Accident............................ C

4.

Containment Event...............................................

D

5.

Radioactivity Event............................................... E

6.

DELETED

7.

Loss of Secondary Coolant......................................... G

8.

Electrical Failure............................................... H

9.

Fire...............................................

I

10.

Security Event...............................................

J

11.

Hazard to Station Operation....................................... K

12.

Natural Events...............................................

L

13.

Miscellaneous Abnormal Events..................................... M

NUMBER ATTACHMENT TITLE REVISION EPIP-l.0l EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB A)

PAGE SAFETY, SHUTDOWN, OR ASSESSMENT

. ~

~1 SYSTEM EVENT

~~~~~~~~~~~~2 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION CAUTION:

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

C.2.

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

1. Loss of function needed for unit HSD condition MODES 1. 2, 3 & 4 Total loss of the Charging/SI System SITE AREA EMERGENCY OR Total loss of the Main Feedwater and Auxiliary Feedwater systems
2. Failure of the Reactor Protection System to initiate and complete a required trip while at power MODES 1 & 2 Reactor trip setpoint and coincidences -

EXCEEDED SITE AREA EMERGENCY AND Automatic trip from RPS FAILED AND Manual trip from Control Room -

FAI LED.

I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB A)

PAGE SAFETY. SHUTDOWN, OR ASSESSMENT 1

SYSTEM EVENT

~~~~~~~ ~~~~~3 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Inability to monitor a significant transient in progress MODES 1, 2. 3 & 4 Most (>75X) or all annunciator alarms on panels "AW to WK" - NOT AVAILABLE SITE AREA EMERGENCY AND All computer monitoring capability (e.g.. PCS)

NOT AVAILABLE AND Significant transient - IN PROGRESS (e.g.. reactor trip. SI actuation, turbine run back >25% thermal reactor power. thermal power oscillations >10%)

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

Subcriticality Core Cooling Heat Sink Vessel Integrity Containment Integrity

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB A)

PG SAFETY, SHUTDOWN. OR ASSESSMENT PAGE I

1.

I1SYSTEM EVENT

~

~

~

~

~

~

~

~

~

~

~

~

~

~

- 4 o f 4 2 CONDITION/APPLICABILITY

5. Total loss of function needed for unit CSD condition MODES 5 & 6 INDICATION Secondary system cooling capability - UNAVAILABLE AND Loss of any of the following systems:

CLASSIFICATION ALERT S

S Service Water Component Cooling RHR AND RCS temperature GREATER THAN 140 0F

6. Failure of the Reactor Protection System to complete a trip which takes the Reactor Subcritical MODES 1 & 2 Reactor trip setpoint and coincidences - EXCEEDED AND Automatic trip from RPS -

FAILED ALERT Manual trip - REQUIRED AND Manual trip from Control Room - SUCCESSFUL

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB A)

PAGE SAFETY, SHUTDOWN. OR ASSESSMENT 1

SYSTEM EVENT

_____________~~~~~~~~~~~~~

S of_42 CONDITION/APPLICABILITY

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

(>75%) or all annunciator alarms on panels "A" to "Kw for GREATER THAN 15 minutes AND All computer monitoring capability (e.g., PCS)

- NOT AVAILABLE OR Significant transient -

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

turbine runback > 25%

thermal reactor power.

thermal power oscillations

> 10%)

CLASSIFICATION ALERT

8. Evacuation of Main Evacuation of the Control Room ALERT Control Room with shutdown control required established within 15 minutes ALL MODES
9. Inability to reach required mode within technical specification limits MODES 1, 2, 3 & 4 Intentional reduction in power, load or temperature IAW T.S. Action Statement -

HAS COMMENCED NOTIFICATION OF UNUSUAL EVENT AND T.S. Action Statement time limit for mode change -

CANNOT BE MET

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB A)

PAGE SAFETY. SHUTDOWN. OR ASSESSMENT 1

SYSTEM EVENT 6

f of 42 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 INDICATION CLASSIFICATION RCS RCS pressure -

LESS THAN 2000 psig NOTIFICATION OF UNUSUAL EVENT NDT Protection System -

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 cooldown rate AND Main Steam pressure greater than 100 psi below setpoint of affected valve

11. Unplanned loss of most or all safety system annunciators for greater than 15 minutes

.MODES 1. 2. 3 & 4 Unplanned loss of most

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB A)

PAGE SAFETY. SHUTDOWN, OR ASSESSMENT SYSTEM EVENT

.___._7 of 42 CONDITION/APPLICABILITY

12. Loss of communications capability ALL MODES INDICATION Station PBX phone system -

FAIALED AND CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT Station Gai-tronics system -

FAILED AND Station UHF radio system -

FAILED I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB B)

PAGE

-1 REACTOR COOLANT SYSTEM EVENT PAGE 8 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of 2 of.3 fission product barriers with potential loss of 3rd barrier ALL MODES Any two of a). b) or c) exist and the third is imminent:

GENERAL EMERGENCY a) Fuel clad integrity failure as indicated by any of the following:

RCS specific activity greater than or equal to 300.0 ItCi/gram dose equivalent I-131 OR 5 or more core exit thermocouples greater than 1200 0F OR Containment High Range Radiation Monitor RM-RMS-165, -166 RM-RMS-265. -266 GREATER THAN 1.88x102 R/hr or b) Loss of RCS integrity as indicated by any of the following:

RCS pressure greater than 2735 psig OR Loss of Reactor Coolant in progress c) Loss of containment integrity as indicated by any of the following:

Containment pressure greater than 60 psia and not decreasing Release path to environment -EXISTS

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM EVENT PG

~~~~~~~ ~~~~~9_of

_42 CONDITION/APPLICABILITY 2.

Fuel failure with steam generator tube rupture ALL MODES INDICATION 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 p~i/gram dose equivalent I-131 OR 5 or more core exit thermocouples GREATER THAN 1200 OF DE High Range Letdown radiation monitor CLASSIFICATION GENERAL EMERGENCY 1-CH-RI-128 or 2-CH-Ri-228 GREATER THAN 5.9 x 10 mR/hr b) Steam Generator tube rupture as indicated by both of the following:

  • SI coincidence - SATISFIED AND
  • Steam Generator tube rupture -IN PROGRESS c) Loss of secondary integrity associated with ruptured steam generator pathway as indicated by any of the following:

OPEN OR Loss of secondary coolant outside containment - IN PROGRESS

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB B)

PG REACTOR COOLANT SYSTEM EVENT 1

10 of_42 CONDITIONIAPPLICABILITY

3. RCS leak rate exceeds makeup capacity MODES 1. 2, 3. & 4 INDICATION

.Primary system leak (LOCA)

- IN PROGRESS CLASSIFICATION SITE AREA EMERGENCY AND Safety Injection -

REQUIRED AND RCS subcooling based on Core Exit Thermocouples -

LESS THAN 300 F 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 Vent A MGPI Monitor SITE AREA EMERGENCY RM-VG-179 GREATER THAN I 1.25 x 108 1ICi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122.

-222 RM-SS-123.

-223 RM-SS-124.

-224 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 EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM EVENT PG

~~~ ~~~~ ~~~~~11 of 42 -

CONDITION/APPLICABILITY

5. RCS leak rate limit EXCEEDED MODES 1. 2. 3. & 4 INDICATION Pressurizer level cannot be maintained greater than 20%

with one (1) Charging/SI pump in operation CLASSIFICATION ALERT AND a

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 secondary leakage with loss of offsite power MODES 1. 2. 3. & 4 Intentional reduction in ower, load or temperature MAW T.S. 3.4.13 primary-to-secondary leakage LCO Action Statement AND ALERT Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 1.73 x 106 pCi/sec l

OR 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-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB B)

PAGE L- -1

~

~~~~REACTOR COOLANT SYSTEM EVENT PAGEf CONDITION/APPLICABILITY

8. RCS operational leakage requiring Dlant shutdown AW T.S. 3.4.13 INDICATION Intentional reduction in power load or temperature IAW T.S.

3.4.13 leakage limit action statement - HAS COMMENCED CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT MODES 1, 2. 3, & 4

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)

PG FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1_

13 of 42 CONDITION/APPLICABILITY

1. Probable large radioactivity release initiated by LOCA with ECCS failure leading to core degradation ALL MODES INDICATION Loss of reactor coolant in progress AND RCS specific activity -

greater than 300 pCi/gram dose equivalent I-131 OR Containment High Range Radiation Monitor CLASSIFICATION GENERAL EMERGENCY RM-RMS-165, -166 or RM-RMS-265. -266 GREATER THAN 1.88x102 R/hr AND High or low head ECCS flow not being delivered to the core (if expected by plant conditions)

CAUTION:

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

A.1.

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

'-I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 14 of 42 CONDITIONIAPPLICABILITY INDICATION CLASSIFICATION GENERAL EMERGENCY

3. Probable large radioactivity release initiated by failure of rotection system to bring Rx subcritical and causing core degradation ALL MODES Rx nuclear power after a trip - greater than 5%

RCS pressure greater than or equal to 2485 psig '

OR Containment temperature increasing pressure and rapidly

4. Probable large radioactivity release initiated by

.loss of AC power and all feedwater ALL MODES Loss of all onsite and offsite AC power AND 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 /> GENERAL EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)CI D

E L

--1 I

~

~~FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE o

CONDITION/APPLICABILITY

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

AND Containment RS sump tem perature greater than 190OF and NOT decreasing OR All Quench Spray and Recirculation Spray systems

- NOT OPERABLE GENERAL EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)CI D

E FUEL FAILURE OR FUEL HANDLING ACCIDENT PG 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 following:

RCS Specific activity greater than 60 pCi/gram dose equivalent I-131 CLASSIFICATION SITE AREA EMERGENCY 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 OF OR Core delta T - zero OR Core delta T -

rapidly diverging

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT PG 1

1~~

~~~~~~7 of 42.

CONDITTON/APPLICABTLITY

7. Major fuel damage accident with radioactivity release to containment or fuel buildings ALL MODES INDICATION Water level in Rx vessel during refueling below the top of core CLASSIFICATION SITE AREA EMERGENCY Water level in spent fuel pool below top of spent fuel AND Verified damage to irradiated fuel resulting in readings on Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN I 2.69 x 108 pCi/sec l
8. Severe Fuel Clad Damage MODES 1. 2. 3. & 4 High Range Letdown radiation monitor ALERT 1-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 RCS specific activity -

greater than 300 pCi/gram dose equivalent I-131

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)

PG FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1

18 of_42 CONDITION/APPLICABILITY

9. Fuel damage accident with release of radioactivity to containment or fuel buildings ALL MODES INDICATION Verified accident involving damage to irradiated fuel CLASSIFICATION ALERT AND Health Physics confirms fission product release from fuel OR Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 1.99 x 106 pCi/sec I
10. Potential for fuel Continuing uncontrolled ALERT damage to occur decrease of water level in during refueling Reactor Refueling Cavity or MODE 6 Spent Fuel Pool

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

19 of_42 CONDITION/APPLICABILITY

11. Fuel clad damage indication MODES 1, 2, 3. & 4 INDICATION Intentional reduction in ower. load or temperature qAW reactor coolant activity T.S. Action Statement - HAS COMMENCED OR High Range Letdown radiation monitor CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT 1-CH-RI-128 or 2-CH-RI-228 Increases to GREATER THAN Hi Alarm setioint (representin? 0.1i tluel failure) within 30 minutes and remains for for at least 15 minutes
12. Independent Spent Fuel Storage Installation (ISFSI) event ALL MODES Verified Sealed Surface Storage Cask (SSSC) seal leakage OR Sealed Surface Storage Cask (SSSC) dropped or mishandled NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB 0)

PAGE CONTAINMENT EVENT 1

~

~

~

20 of_42 CONDITION/APPLICABILITY

1. Extremely high containment radiation, pressure and temperature MODES 1. 2, 3, & 4 INDICATION CLASSIFICATION Containment High Range radiation monitor GENERAL EMERGENCY RM-RMS-165, -166 or RM-RMS-265. -266 GREATER THAN 336 x 102 R/hr AND Containment pressure greater than 45 psia and not decreasing

.OR Containment temperature greater than 28 OF

2. High-high containment radiation, pressure, and temperature MODES 1. 2. 3, & 4 Containment High Range radiation monitor SITE AREA EMERGENCY RM-RMS-165, -166

-RM-RMS-265, -266 GREATER THAN 1.88 x 10 R/hr or AND Containment pressure -

greater than 27.75 psia and not decreasing OR Containment temperature -

greater than 200 'F

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB D)

PAGE CONTAINMENT EVENT 21 of 42 CONDITION/APPLICABILITY

3. High Containment radiation, pressure and temperature MODES 1. 2. 3. & 4 INDICATION Containment High Range radiation monitor CLASSIFICATION ALERT RM-RMS-165. -166 RM-RMS-265. -266 GREATER THAN 81.5 R/hr or AND Containment pressure -

greater than 17 psia OR Containment temperature -

greater than 150OF

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT I_

22 of 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 INDICATION HP assessment indicates actual or projected doses at or beyond site boundary greater than 1.0 Rem TEDE or 5.0 Rem Thyroid CDE CLASSIFICATION GENERAL EMERGENCY ALL MODES
2. Release imminent or in progress and site boundary doses rojected to exceed 9.1 Rem TEDE or 0.5 Rem Thyroid CDE ALL MODES HP assessment indicates actual or projected dose at or beyond Site Boundary exceeds 0.1 Rem TEDE or 0.5 Rem Thyroid CDE SITE AREA EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT 1

~~~ ~~~~~~~~~23 of 42 CONDITION/APPLICABILITY

3. Effluent release greater than 10 times ODCM allowable limit ALL MODES INDICATION a) Any of the following monitors indicate valid readings above the specified values for greater than 15 minutes CLASSIFICATION ALERT
  • Clarifier Effluent S

S RM LW-11i GREATER THAN 1

[4.8 x 10 cpm Discharge Canal RM-SW-130 or -230 GREATER lTHAN 5 x 104 cpm Vent Vent A MGPI

[ RM-VG-179 GREATER THAN 11.73 x 106 JLCi/sec Vent Vent B MGPI RM-VG-180 GREATER THAN l1.99 x 106 pCi/sec Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 107 pCi/sec l

0 OR b) HP assessment (sample results or dose projections) indicate greater than 10 times ODCM allowable limit

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB E)

PAGE RADIOACTIVITY EVENT

__I___

24 of 42 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 RM-VG-106 or -105 CLASSIFICATION ALERT Control Room Area lRS157 Aux. Bldg. Control Area lLRl-154 Decon. Bldg. Area l R -151 l

Fuel Pool Bridge Area l RU Z153 New fuel storage Area l RMS-152 Laboratory Area S RMS-158 R

Sample Room Area lRS1561

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB E)

PAGE 1

RADIOACTIVITY EVENT

_ i25 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 CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT 0

0 0

0

[ RM-LW-11J GREATER THAN 4.8 x 10 cpm Discharge Canal IRM-SW-130 os -230 GREATER lTHAN 5 x 10 cpm Vent Vent A MGPI

.RM-VG-179 GREATER THAN l

[1.73 x 105 pCi/secl Vent Vent B MGPI RM-VG-180 GREATER THAN 11.99 x 105 pCi/sec Process Vent MGPI I

RM-GW-178 GREATER THAN 1.35 x 106 pCi/sec OR b) HP assessment (sample results or dose projections) indicates greater than ODCM allowable limit

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB G)

PG LOSS OF SECONDARY COOLANT PAGE I__

26 of 42 CONDITION/APPLICABILITY

1. Major secondary line break with significant primary to secondary leakage and fuel damage indicated MODES 1. 2, 3. & 4 INDICATION Conditions a) and b) exist with c):

a) Uncontrolled loss of secondary coolant - IN PROGRESS CLASSIFICATION SITE AREA EMERGENCY AND b) RCS specific activity exceeds limits of T.S. Figure 3.4.16-1 OR High Range Letdown radiation monitor I1-CH-RI-128 or 2-CH-RI-228 I GREATER THAN Hi Alarm setpoint c) Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 6.21 x 107 pCi/sec DR Affected pathway Steam Generator Blowdown monitor RM-SS-122. -123. -124,

-222, -223, -224 GREATER THAN 1 x 106 cpm OR Affected pathway Main Steam Line High Range monitor RM-MS-170. -171. -172.

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB G)

PAGE L- -1 I

~

~~~~LOSS OF SECONDARY COOLAINT 1

2of4 CONDITION/APPLICABILITY

2. Major secondary line break with significant primary to secondary leakage MODES 1. 2, 3, & 4 INDICATION Uncontrolled loss of secondary coolant - IN PROGRESS AND Vent Vent A MGPI Monitor l RM-VG-179 GREATER THAN 1 1.76 x 106 pCi/sec l

CLASSIFICATION ALERT OR Steam Generator Blowdown monitor.on affected pathway RM-SS-122. -123. -124 RM-SS-222. -223, -224 GREATER THAN 1x105 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 break secondary line Uncontrolled loss of secondary coolant - IN PROGRESS NOTIFICATION OF UNUSUAL EVENT MODES 1. 2. 3. & 4

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB H)

PAGE ELECTRICAL FAILURE

__28-of

_42 CONDITION/APPLICABILITY

1. Loss of offsite and onsite AC power for more than 15 minutes ALL MODES INDICATION The following conditions exist for greater than 15 minutes:

Ammeters for 4160V Reserve Station Service Buses D. E.

& F all indicate - zero (0) amps AND Ammeters for 4160V Station Service Buses A, B. & C all indicate - zero (0) amps AND CLASSIFICATION SITE AREA EMERGENCY Ammeters for 4160V Emergency Buses H & J both indicate - zero (0) amps

2. Loss of all onsite DC power for greater than 15 minutes ALL MODES The following conditions exist for greater than 15 minutes:

All station battery voltmeters indicate zero (0) volts AND No light indication available to Reserve Station Service breakers 15D1. 15E1 and 15F1 SITE AREA EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB H)

PAGE ELECTRICAL FAILURE 1

~~~ ~~~~~~~~~29 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION CAUTION:

EAL A.1 is duplicated below for cross-reference/comparison to EAL H.3:

A.1.

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

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 a

Ammeters for 4160V Station Service Buses A, B. & C all indicate - zero (0) amps AND Ammeters for 4160V Emergency Buses H and 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 15D1. 15E1 and 15F1

NUMBER ATTACHMENT TITLE REVISION

. EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB H)

PAGE L- -1 ELECTRICAL FAILURE 30~~~~~~~~~~~S of_42 CONDITION/APPLICABILITY INDICATION

5. Loss of offsite power or onsite AC power capability ALL MODES Unit main generator and both emergency diesel generators out of service OR Loss of all 34.5 KV reserve station service buses CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB I)

PAGE

_____FIRE I

- 1 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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

MODES 1. 2, 3. & 4 Specs.

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 EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB ~J)

PAGE SECURITY EVENT 1

_____________~ ~

~

~

~ ~ ~ ~ ~ ~ ~~.

32 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of physical Station control ALL MODES Shift Manager/Station Emergency Manager has been informed that the security force has been neutralized by attack, resulting in loss of physical control of station GENERAL EMERGENCY OR Shift Manager/Station Emergency Manager has been informed of intrusion into one or more Vital Areas which are occupied or controlled by an aggressor
2. Imminent loss of Security Shift Supervisor has SITE AREA physical Station notified the Operations.Shift EMERGENCY control Manager/Station Emergency Manager of imminent intrusion ALL MODES into a Vital Area
3. Ongoing Security Security Shift Supervisor has ALERT compromise notified the Operations Shift Manager/Station Emergency ALL MODES Manager of a confirmed unneutralized intrusion into the Protected Area or ISFSI

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB J)

PAGE SECURITY EVENT

__33 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

4. Security threat.

unauthorized attempted entry. or attempted sabotage ALL MODES Any of the following when determined to have potential for degrading the level of safety of the plant or ISFSI Receipt of a credible site-specific threat from Security, NRC or FBI NOTIFICATION OF UNUSUAL EVENT Confirmed hostage situation Civil disturbance Discovery of a bomb device (other-than on or near a safety-related system which represents an on-going security compromise)

Confirmed attempted intrusion (Protected Area or ISFSI)

Attempted sabotage

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION 34 of 42 CONDITION/APPLICABILITY

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

SITE AREA EMERGENCY 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 -

REQUIRED OR Significant degradation of plant safety systems resulting in loss of a safety system function required for protection of the public

NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION

~~~ ~~~~~~~~~~~~~35 of 4 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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

-MODES 1. 2. 3. & 4

5. Aircraft crash on Aircraft crash within the ALERT the facility.

Protected Area or Switchyard ALL MODES

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:

facility Evacuation of personnel ALL MODES from plant areas

~~~~AND Safety related equipment is rendered inoperable

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB K)

PG HAZARD TO STATION OPERATION PAGE 1

36X of_42 CONDITION/APPLICABILITY

9. Missile damage to safety related equipment or structures INDICATION Notification of missile impact causing damage to safety related equipment or structures CLASSIFICATION ALERT MODES 1, 2, 3. & 4
10. Aircraft crash or unusual aircraft activity ALL MODES Confirmed notification of aircraft crash within the site boundary NOTIFICATION OF UNUSUAL EVENT Unusual aircraft activity in the vicinity of the site as determined by the Operations Shift Manager/

Station Emergency Manager or the Security Shift Supervisor

11. Train derailment Confirmed report of train NOTIFICATION within Protected derailment within Protected OF UNUSUAL Area Area 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 release of toxic or flammable liquids or gases ALL MODES Notification of unplanned release of toxic or flammable agents which may affect safety of station personnel or equipment NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB OA PAGE HAZARD TO STATION OPERATION PG 1

~~~~~~~~~~~~37 of 42 I

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 CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB L)

PAGE NATURAL EVENTS 1

38 _of _42 CONDITION/APPLICABILITY

1. Earthquake greater than or equal to DBE levels MODES 1, 2, 3. & 4 INDICATION Confirmed earthquake which activates the Event Indicator on the Strong Motion Accelerograph CLASSIFICATION SITE AREA EMERGENCY Alarms on the Peak Shock Annunciator indicate 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 winds in Sustained-winds 150 mph SITE AREA excess of design OR GREATER experienced EMERGENCY levels experienced or projected or projected MODES 1. 2, 3, & 4
3. NOT USED

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB L)

PAGE L -1 I

~

~~~~~NATURAL EVENTS PG

~~~~~~~~~~~~39 of _4 CONDITION/APPLICABILITY

4. Earthquake greater than or equal to OBE levels ALL MODES INDICATION
  • Confirmed earthquake which activates Event Indicator on the Strong Motion Accelerograph 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 CLASSIFICATION ALERT
5. Tornado striking Tornado visually detected ALERT facility 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 Flood in the Lake Anna Reservoir with indicated level -

greater than 263 feet MSL ALERT ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB L)

PAGE NATURAL EVENTS

_ _40 of_42 CONDITION/APPLICABILITY

8. Earthquake detected ALL MODES INDICATION Confirmed earthquake which activates the Event Indicator on the Strong Motion Accelerograph CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT
9. Tornado within Tornado visually detected NOTIFICATION Protected Area or within Protected Area or OF UNUSUAL Switchyard Switchyard EVENT ALL MODES
10. Hurricane force Confirmation by Weather NOTIFICATION winds projected Center that hurricane force OF UNUSUAL onsite within 12 winds (greater than 73 mph)

EVENT hours projected onsite within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ALL MODES

11. 50 year flood Flood in the Lake Anna Reservoir with indicated level -

greater than 254 feet MSL NOTIFICATION OF UNUSUAL EVENT ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB M)

PG MISCELLANEOUS ABNORMAL EVENTS PAGE 1

41 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION GENERAL EMERGENCY

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 Manager judgement
2. Station conditions Shift Manager/Station Emergency SITE AREA which may warrant Manager judgement EMERGENCY notification of the public near the site 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-1.01 EMERGENCY ACTION LEVEL TABLE 39 ATTACHMENT (TAB M)

PG MISCELLANEOUS ABNORMAL EVENTS 1

l _

42 of 42 CONDITION/APPLICABILITY

4. Station conditions which warrant increased awareness of state and/or local authorities ALL MODES INDICATION Shift Manager/Station Emergency Manager judgement that any of the following exist:

CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT a

Unit shutdown is other than a controlled shutdown OR Unit is in an uncontrolled condition during operation ODR A condition exists which has the potential for escalation and therefore warrants notification

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 TURNOVER CHECKLIST 39 ATTACHMENT PAGE l

2 1

l 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 status of primary responder notification.
2. Determine the status of "Report of Emergency to State and Local Governments," EPIP-2.01. Attachment 2. Get completed copies if available.
3. Determine status of the "Report of Radiological Conditions to the State." 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 classification and initial PAR status.
6. Review present plant conditions and status. Get copy of Critical Safety Functions form.
7. Review status of station firewatches and re-establish if conditions allow.
8. Determine readiness of TSC for activation.
9. After all information is obtained, transfer location to TSC. (Consider direct transfer of State & local notifications to LEOF/CEOF.)
10. Call the Control Room and assess any changes that may have occurred during transition to the TSC.

11.-When sufficient personnel are available, the relief SEM is to assume the following responsibilities from the onshift Station Emergency Manager:

a. Reclassification.
b. Protective Action Recommendations until LEOF activated.
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. Formally relieve the Interim SEM and assume control in the TSC.

Announce name and facility activation status to facility.

l NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 CONSIDERATIONS FOR OPERATIONS RESPONSE 39 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 3

1 of 1 This attachment provides procedural guidance for controlling 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 is not all-inclusive.

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

IF 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.

IF 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.

(Consider having Corporate Security notify corporate emergency response organization only using CPIP-3.4, INNSBROOK SECURITY SUPPORT, and notifying personnel in unaffected areas on-site selectively.)

IF notifying augmentation could create a safety hazard for personnel coming to the station, THEN consider postponing augmentation notification.

(Consider having Corporate Security notify corporate emergency response organization only using CPIP-3.4.

INNSBROOK SECURITY SUPPORT, or defering notifications until hazardous conditions are resolved.)

ANTICIPATED SITUATION (e.g.. forecasted severe weather or grid disturbance):

IF all or part of the ERO has been staged in anticipation of a predicted event, THEN notify Security to omit performance of augmentation notification (as described in EPIP-3.05, AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION).

IF adequate controls have been established to continually account for personnel staged in anticipation of a predicted event, THEN notify Security to omit performance of initial accountability (as described in EPIP-5.03, PERSONNEL ACCOUNTABILITY).

IF a decision has been made to staff the Central EOF in lieu of the LEOF, THEN notify Security that performance of EPIP-3.04, ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY, is not required.

IF environmental conditions are hazardous, THEN consult with Security Team

'Leader about suspending procedural requirements for staging road blocks (1AW EPIP-5.04, ACCESS CONTROL).

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