ML021710762

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Revision to Emergency Plan Implementing Procedure
ML021710762
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/06/2002
From: Heacock D
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
02-344, NAPS/MPW
Download: ML021710762 (57)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMIPANY RICHIMOND, VIRGINIA 23261 June 6, 2002 U.S. Nuclear Regulatory Commission Serial No.02-344 Attention: Document Control Desk NAPS/MPW Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 Gentlemen: NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REVISION TO EMERGENCY PLAN IMPLEMENTING PROCEDURE Pursuant to 10 CFR 50.54(q), enclosed is recent revision to a North Anna Power Station Emergency Plan Implementing Procedure. The 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, D. A. Heacock Site 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. J. Morgan NRC Senior Resident Inspector North Anna Power Station AC/f

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

Emergency Plan Privacy and Proprietary Material has been removed. Reference Generic Letter No. 81-27.

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 36 (With 3 Attachments) PAGE 7

1 of PURPOSE To assess 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 Supervisor.

' LEVEL 2 DISTIBUTION This Documen Should Be vere And Annotated Fo A Contoled ource As Required to Perlform Wo-A Approvals on File Effective Date f 1/5 -

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 36 PAGE 2 of 7 ACTION/EXPECTED RESPONSE F-]

l RESPONSE NOT OBTAINED F-I CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made.

NOTE: The ERFCS is potentially unreliable in the event of an earthquake.

Therefore, ERFCS parameters should be evaluated for accuracy should this situation 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, ERFCS, 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 36 PAGE 3 of 7 ACTION/EXPECTED RESPONSE H-] l RESPONSE NOT OBTAINED F-l 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 FOR IF deviation from normal emergency NORMAL IMPLEMENTATION OF 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) IF classification/assembly announcement deferred, THEN GO TO Step 4.

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 36 PAGE 3 of 7

-LJ-t ACTION/EXPECTED RESPONSE

[-1 u RESPONSE NOT OBTAINED F-l 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 FOR IF deviation from normal emergency NORMAL IMPLEMENTATION OF EMERGENCY response actions warranted, THEN RESPONSE ACTIONS do the following:

a) Refer to Attachment 4, Considerations for Operations Response Under Abnormal Conditions.

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 36 PAGE 4 of 7

-LIIEJ-E ACTION/EXPECTED RESPONSE F- RESPONSE NOT OBTAINED F-3 NOTIFY 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-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 36 PAGE 5 of 7

-LFi-C S m ACTION/EXPECTED RESPONSE [-1 RESPONSE NOT OBTAINED H-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-2.01, 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 36 PAGE 6 of 7 ACTION/EXPECTED RESPONSE

-I  !

RESPONSE NOT OBTAINED H-

__ 5 CHECK TSC - ACTIVATED IF TSC NOT activated, THEN do the following:

a) Have STA report to the Control Room.

b) Notify Superintendent 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 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 36 PAGE 7 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDO 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:

"*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 36 ATTACHMENT PAGE 1 INDEX

____ ____ ____1 pF 415 CAUTION: a 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.

NOTE:

  • Design Change Package 99-006, Replacement of Ventilation Radiation Monitors (NAPS Units 1 & 2), replaces KAMAN process and vent stack particulate, iodine and gaseous radiation monitors with a radiation monitor system manufactured by MGP Instruments (MGPI). Affected EALs are: B-4, B-7, C-7, C-9, E-3, E-5, G-1 and G-2. Both KAMAN and MGPI indications are provided for classification depending upon which system is in service. During the interim period when neither system is in service, indications are provided for classification based on HP monitoring and assessments.
  • Two versions of EALs B-8, B-9 and L-3 address use before and after ITS is implemented. Also, EAL G-l's references to a renumbered Technical Specification figure lists both figure numbers.

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.

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT

____________2 of_45 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 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 Feedwater and Auxiliary Feedwater systems
2. Failure of the Reactor trip setpoint and SITE AREA Reactor Protection coincidences - EXCEEDED EMERGENCY System to initiate and complete a AND required trip while at power Automatic trip from RPS FAILED MODES 1 & 2 AND Manual trip from Control Room - FAILED

NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT

____________ 3of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Inability to monitor
  • Most (>75%) or all SITE AREA a significant 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., plant computer, ERFCS) - 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 any one 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 EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT

____________4 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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 S Component Cooling 0 RHR AND

  • RCS temperature GREATER THAN 140 OF
6. Failure of the "* Reactor trip setpoint and ALERT Reactor Protection coincidences - EXCEEDED System to complete a trip which takes the AND Reactor Subcritical

"* Automatic trip from RPS MODES 1 & 2 FAILED AND

"* Manual trip - REQUIRED AND

"* Manual trip from Control Room - SUCCESSFUL

NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT

_____________5_of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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., plant MODES 1, 2, 3 & 4 computer, ERFCS) - 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 Evacuation of the Control Room ALERT Control Room with shutdown control required established within 15 minutes ALL MODES
9. Inability to reach
  • Intentional reduction in NOTIFICATION required mode within power, load or temperature OF UNUSUAL technical IAW 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 EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT

_____________ 6 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

10. Failure of a safety 0 RCS NOTIFICATION 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 NDT 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

"* 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 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 EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT

____________7 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

12. Loss of
  • Station PBX phone system NOTIFICATION communications FAILED OF UNUSUAL capability EVENT AND ALL MODES
  • Station Gai-tronics system - FAILED AND
  • Station UHF radio system FAILED

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT PAGE 1

____________8 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of 2 of 3 Any two of a), b) or c) exist GENERAL fission product and the third is imminent: EMERGENCY barriers with potential loss of a) Fuel clad integrity failure 3rd barrier as indicated by any of the following:

ALL MODES RCS specific activity greater than or equal to 300.0 ýiCi/gram dose equivalent 1-131 OR 5 or more core exit thermocouples greater than 1200 OF OR Containment High Range Radiation Monitor RM-RMS-165, -166 or RM-RMS-265, -266 GREATER THAN 1.88x10 2 R/hr 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 OR Release path to environment -EXISTS

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT PAfE 1

____________9 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

2. Fuel failure 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 indicated by any of the following:

"*RCS specific activity greater than 300 pCi/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 -IN 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 OR Loss of secondary coolant outside containment - IN PROGRESS

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT 1

____________10 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. RCS leak rate "* Loss of Reactor Coolant in SITE AREA limit - EXCEEDED Srogress and inventory EMERGENCY alance indicates leakage MODES 1, 2, 3, & 4 GREATER THAN 300 gpm AND

"* Pressurizer level cannot be maintained with two (2) or more Charging/SI pumps in operation

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT 1

___________11 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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 Vent A Kaman Monitor RM-VG-179 GREATER THAN 1.3 x 10d pCi/sec OR HP determines Site Boundary DDE GREATER THAN 50 mrem/hr OR Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN]

1.25 x 108 uCi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122, -222 RM-SS-123, -223 RM-SS-124, -224 6 GREATER THAN 1x10 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 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT PAfE 1

____________12 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. RCS leak rate limit "* Pressurizer level cannot be ALERT

- EXCEEDED maintained greater than 20%

with one (1) Charging/Sl 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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT PAGE 1

_____________I1 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

7. Excessive primary to "* Intentional reduction in ALERT secondary leakage ower, load or temperature with loss of offsite ecause the unit has power entered an Action Statement or will exceed an LCO MODES 1, 2, 3, & 4 AND

"* Vent Vent A Kaman Monitor RM-VG-179 GREATER THAN 1.83 x 106 jiCi/sec OR HP assessment of sample results indicates GREATER THAN 10 times ODCM allowable limit (Alert per EAL E-3)

OR Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 1.73 x 106 tCi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122, -222 RM-SS-123, -223 RM-SS-124, -224 5 GREATER THAN jx10 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 36 ATTACHMENT (TAB B) PAGE ATTACHMENT REACTOR COOLANT SYSTEM EVENT 1

____________14 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION IPROR NL **PLEMENTA AFoR IS TIO IF ITS Implemented, THEN:

8. RCS operational Intentional reduction in power NOTIFICATION leakage requiring load or temperature IAW T.S. OF UNUSUAL plant shutdown 3.4.13 leakage limit action EVENT IAW T.S. 3.4.13 statement - HAS COMMENCED MODES 1, 2, 3, & 4 PERFORM ONL AFE IT IMLMNATIO 4, PERFORM With CURRENT, UNIMPROVED TECH SPECS ONLY IF Current, Unimproved Tech Spec. Implemented, THEN:

IF

8. RCS leak rate or Intentional reduction in NOTIFICATION leakage requiring Sower, load or temperature OF UNUSUAL plant shut down ecause the unit has EVENT IAW T.S. 3.4.6.2 entered an action statement or will exceed an LCO MODES 1, 2, 3, & 4 AND Unidentified RCS leakage greater than 1 gpm OR Identified leakage greater than 10 gpm OR Controlled leakage to RCP Seals - greater than 30 gpm total OR Any pressure boundary leakage - EXISTS t

iT PERFORM With CURRENT, UNIMPROVED TECH SPECS ONLY

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT PAGE 1

_______1* of4 CONDITION/APPLICABILITY INDICATION CLASSIFICATION IEROR ONLY AFTER I-T IMPL E EN A IF ITS Implemented. THEN:

9. Classify Primary to Secondary leakage - greater than 1 gpm under provisions of Tab B, Condition 8..

P ONL A I A 4, PERFORM With CURRENT, UNIMPROVED TECH SPECS ONLY IF Current. Unimproved Tech Spec, Implemented. THEN:

9. Primary to Secondary Intentional reduction in NOTIFICATION leakage - greater than 1 gpm gower, load or temperature OF UNUSUAL ecause the unit has EVENT entered an action statement MODES 1, 2, 3, &4 or will exceed an LCO AND Primary to Secondary leakage greater than 1 gpm OR N-16 monitor indicates primary to secondary leakage greater than T. S.

allowable limits PERFORM With CURRENT, UNIMPROVED TECH SPECS ONLY A

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1AGE 1

____________16 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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 specific activity greater than 300 jiCi/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.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 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 EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 A 4E 1

_____________17 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Probable large "* Rx nuclear power after a GENERAL radioactivity 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 offsite 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-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1

____________18 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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)

AND

"* Containment RS sump temperature greater than 190OF and NOT decreasing OR All Quench Spray and Recirculation Spray systems

- NOT OPERABLE

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1

____________19 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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

MODES 1, 2, 3, & 4 RCS Specific activity greater than 60

ý+/-Ci/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 OF OR Core delta T - zero OR Core delta T - rapidly diverging

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

_____________20 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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 OR buildings Water level in spent fuel ALL MODES pool below top of spent fuel AND Verified damage to irradiated fuel resulting in readings on Vent Vent "B" Kaman monitor RM-VG-180 GREATER THAN]

2.74 x 108 jiCi/sec OR HP determines Site Boundary DDE GREATER THAN 50 mrem/hr OR Verified damage to irradiated fuel resulting in readings on Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 2.69 x 108 j.Ci/sec

8. Severe Fuel Clad High Range Letdown ALERT Damage radiation monitor MODES 1, 2, 3, &4 1-CH-RI-128 or 2-CH-RI-228 Increases to GREATER THAN Hi Hi Alarm setpoint within 30 minutes and remains for at least 15 minutes

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1

____________21 of_45 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 buildings Health Physics confirms fission ALL MODES product release from fuel OR Vent Vent "B" Kaman monitor I RM-VG-180 GREATER THAN 1.83 x 106 pCi/sec II OR HP assessment of sample results indicates GREATER THAN 10 times ODCM allowable limit (Alert per EAL E-3)

OR Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 1.99 x 106 pCi/sec

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 36 ATTACHMENT (TAB C) PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT P 1

____________22 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB D) PAGE ATTACHMET 1 ICONTAINMENT EVENT

_____________23 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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 AND Containment pressure greater than 45 psia and not decreasing OR Containment temperature greater than 280OF
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 AND Containment pressure greater than 27.75 psia and not decreasing OR Containment temperature greater than 200 OF

NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB D) PAGE CONTAINMENT EVENT 1 ____________24 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. High Containment 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 81.5 R/hr AND Containment pressure greater than 17 psia OR Containment temperature greater than 150OF

NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB E) PAGE RADIOACTIVITY EVENT 1

_____________25 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Release imminent or HP assessment indicates GENERAL in progress and site actual or projected doses 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-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB E) PAGE ATTACMENT iRADIOACTIVITY EVENT 1

_____________26 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Effluent release a) Any of the following ALERT greater than 10 monitors indicate valid times ODCM allowable readings above the limit specified values for greater than 15 minutes ALL MODES
  • Clarifier Effluent RM-LW-111 GREATER THAN 4.8 x 105 cpm Discharge Canal RM-SW-130 or -230 GREATER THAN 5 x 104 cpm Vent Vent A Kaman RM-VG-179 GREATER THAN 1.83 x 106 TCi/sec Vent Vent A MGPI RM-VG-179 GREATER THAN 1.73 x 106 jCi/sec Vent Vent B Kaman RM-VG-180 GREATER THAN 1.83 x 106 jICi/sec Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 106 jCi/sec Process Vent Kaman RM-GW-178 GREATER THAN 2.0 x 107 fiCi/sec Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 107 9 Ci/sec 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 36 ATTACHMENT (TAB E) PAGE ATTACMENT iRADIOACTIVITY EVENT 1

_____________27 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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

"* Aux. Bldg. Control Area IRMI5

"* Decon. Bldg. Area IRMS-151

"* Fuel Pool Bridge Area RMS-153

"* New fuel storage Area IIRMS-152

"* Laboratory Area S RMS-158

" Sample Room Area IRMS-156I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB E) PAGE ATTAC-MENT RADIOACTIVITY EVENT

_____________28 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. Effluent release a) Any of the following NOTIFICATION 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 103Icpm Vent Vent A Kaman RM-VG-179 GREATER THAN 1.83 x 105 ICi/sec Vent Vent A MGPI RM-VG-179 GREATER THAN 1.73 x 105 Ci/sec I Vent Vent B Kaman RM-VG-180 GREATER THAN 1.83 x 105 pCi/sec Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 105 jiCi/sec Process Vent Kaman RM-GW-178 GREATER THAN 2.0 x 106 JLCi/sec Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 106 jICi/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 36 ATTACHMENT (TAB G) PAGE LOSS OF SECONDARY COOLANT 1

____________29 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Major secondary Conditions a) and b) exist with c): SITE AREA line break with a) Uncontrolled loss of secondary EMERGENCY significant primary coolant - IN PROGRESS to secondary leakage and fuel AND damage indicated b) RCS specific activity exceeds MODES 1, 2, 3, & 4 limits of T.S. Figure 3.4-1 (ITS Figure 3.4.16-1)

OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 GREATER THAN Hi Alarm setpoint AND c) Vent Vent A Kaman Monitor I RM-VG-179 GREATER THAN 6.45 x 107 tCi/sec OR HP determines Site Boundary DDE GREATER THAN 50 mrem/hr OR Vent Vent A MGPI Monitor I RM-VG-179 GREATER THAN 6.21 x 107 ýtCi/sec OR Affected pathway Steam Generator Blowdown monitor RM-SS-122, -123, -1g4, -222, -223, -224 GREATER THAN 1 x 10 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 36 ATTACHMENT (TAB G) PAGE I LOSS OF SECONDARY COOLANT PAGE

____________30 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

2. Major secondary line
  • Uncontrolled loss of ALERT break with secondary coolant - IN significant primary PROGRESS to secondary leakage AND MODES 1, 2, 3, &4
  • Vent Vent A Kaman Monitor RM-VG-179 GREATER THAN 1.83 x 106 pCi/sec OR HP assessment of sample results indicates GREATER THAN 10 times ODCM allowable limit (Alert per EAL E-3)

OR Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 1.76 x 106 iLCi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122, -123, -124 RM-SS-222, -223, -224 GREATER THAN 1x10 5 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 NOTIFICATION break coolant - IN PROGRESS OF UNUSUAL EVENT MODES 1, 2, 3, & 4

NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB H) PAGE ATTACHMENT ELECTRICAL FAILURE 1

____________31 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. 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, & C all indicate - zero (0) amps AND

  • Ammeters for 4160V Emergency Buses H & J both indicate - zero (0) amps
2. Loss of all onsite The following conditions exist SITE AREA DC power for greater for greater than 15 minutes: EMERGENCY than 15 minutes
  • All station battery ALL MODES voltmeters indicate zero (0) volts AND No light indication available to Reserve Station Service breakers 15D1, 15E1 and 15F1

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB H) PAGE ELECTRICAL FAILURE 1

32 of 45 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 I 3. Loss of all offsite

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

& F all indicate - zero (0)

ALL MODES amps AND

"* Ammeters for 4160V Station Service Buses A, B, & 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 36 ATTACHMENT (TAB H) PAGE 1ELECTRICAL ATTACHMET FAILURE 1

_____________33 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB I) PAGE FIRE 1

_____________34 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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.

MODES 1, 2, 3, & 4 Specs.

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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB J) PAGE ATTACHMENT SECURITY EVENT 1

_____________35_of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of physical Shift Supervisor has been GENERAL Station control informed that the security EMERGENCY force has been neutralized ALL MODES by attack, resulting in loss of physical control of station OR Shift Supervisor 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 Supervisor of imminent intrusion into a Vital Area ALL MODES
3. Ongoing Security Security Shift Supervisor has ALERT compromise notified the Operations Shift Supervisor of a confirmed ALL MODES unneutralized intrusion into the Protected Area or ISFSI
4. Security threat, Any of the following when NOTIFICATION unauthorized determined to have potential OF UNUSUAL attempted entry, or for degrading the level of EVENT attempted sabotage safety of the plant or ISFSI ALL MODES "* Receipt of a credible site-specific threat from Security, NRC or FBI

"* 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) 0 Attempted sabotage

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB K) PAGE I HAZARD TO STATION OPERATION PAGE

____________36 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Aircraft damage to Aircraft crash which affects 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 Uncontrolled release of SITE AREA flammable gases into toxic or flammable agents EMERGENCY plant vital areas greater than life other than the threatening or explosive Control Room limits in Vital Areas 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-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB K) PAGE HAZARD TO STATION OPERATION 1 ___37 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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 facility Protected Area ALL MODES or Switchyard
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 Failure of turbine/generator ALERT missile impact rotating equipment resulting in casing penetration MODES 1 & 2

NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB K) PAGE HAZARD TO STATION OPERATION E 1

____________38 of 45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

9. Missile damage to Notification of missile impact ALERT safety related causing damage to safety equipment or related equipment or structures structures MODES 1, 2, 3, & 4
10. Aircraft crash or Confirmed notification of NOTIFICATION unusual aircraft aircraft crash within the OF UNUSUAL activity site boundary EVENT ALL MODES OR Unusual aircraft activity in the vicinity of the site as determined by the Operations Shift Supervisor 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 Notification of unplanned NOTIFICATION release of toxic or release of toxic or flammable OF UNUSUAL flammable liquids or agents which may affect safety EVENT gases of station personnel or equipment ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB K) PAGE HAZARD TO STATION OPERATION 1

_____________39 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

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-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB L) PAGE LTTCHEN1 i NATURAL EVENTS

____________40 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Earthquake greater Confirmed earthquake SITE AREA than or equal to DBE which activates the Event EMERGENCY levels Indicator on the Strong Motion Accelerograph MODES 1. 2, 3, &4 AND 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

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB L) PAGE AI FCMN 1 NATURAL EVENTS 1

___________41 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION PEFR ONLY AFE IT IMPEMNTAIO IF ITS Implemented. THEN:

3. Flood or low water Either condition a) or b) exists SITE AREA level above design EMERGENCY levels a) Flood in the Lake Anna Reservoir with indicated MODES 1, 2. 3, &4 level - greater than 264 feet MSL OR b) Low water level in the Lake Anna Reservoir with indicated level - less than 244 feet MSL AND Inability to satisfy action requirements of TR 3.7.4 for North Anna Reservoir PERFORM With CURRENT, UNIMPROVED TECH SPECS ONLY IF Current. Unimproved Tech Spec. Implemented, THEN:
3. Flood or low water Either condition a) or b) exists SITE AREA level above design EMERGENCY levels a) Flood in the Lake Anna Reservoir with indicated MODES 1, 2, 3, & 4 level - greater than 264 feet MSL OR b) Low water level in the Lake Anna Reservoir with indicated level - less than 244 feet MSL AND Inability to satisfy action requirements of T.S. 3.7.5.1 for Ultimate Heat Sink PERFORM With CURRENT, UNIMPROVED TECH SPECS ONLY

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB L) PAGE NATURAL EVENTS 1

____________42 of 45 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 O.04g
5. Tornado striking Tornado visually detected ALERT facility striking structures within the ALL MODES Protected Area or Switchyard
6. Hurricane winds Hurricane winds 120 mph ALERT near design basis OR GREATER experienced level experienced or projected or projected ALL MODES
7. Flood or low water Flood in the Lake Anna ALERT level near design Reservoir with indicated levels level - greater than 263 feet MSL ALL MODES OR Low water level in the Lake Anna Reservoir with indicated level - less than 244 feet MSL

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB L) PAGE NATURAL EVENTS 1 ___________43_of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

8. Earthquake detected Confirmed earthquake which NOTIFICATION activates the Event Indicator OF UNUSUAL ALL MODES on the Strong Motion EVENT Accelerograph
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 or low Flood in the Lake Anna NOTIFICATION water level Reservoir with indicated OF UNUSUAL level - greater than 254 EVENT ALL MODES feet MSL OR Low water level in the Lake Anna Reservoir with indicated level less than 246 feet MSL

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB M) PAGE MISCELLANEOUS ABNORMAL EVENTS PAGE 1

___________44 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Any major internal Shift Supervisor/Station GENERAL or external events Emergency 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 Supervisor/Station SITE AREA which may warrant Emergency Manager judgement EMERGENCY notification of the public near the site ALL MODES
3. Station conditions Shift Supervisor/Station ALERT which have the Emergency Manager judgement potential to degrade or are actually degrading the level of safety of the station ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 36 ATTACHMENT (TAB M) PAGE MISCELLANEOUS ABNORMAL EVENTS 1

____________45 of_45 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

4. Station conditions Shift Supervisor judgement that NOTIFICATION which warrant any of the following exist: OF UNUSUAL increased awareness EVENT of state and/or local authorities Unit.shutdown is other than ALL MODES a controlled shutdown OR Unit is in an uncontrolled condition during operation OR A condition exists which has the potential for escalation and therefore warrants notification

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 TURNOVER CHECKLIST 36 ATTACHMENT PAGE 2 1 of 1 I 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 Attachment 1).
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.

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 CONSIDERATIONS FOR OPERATIONS RESPONSE 36 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 (IAW EPIP-5.04, ACCESS CONTROL).

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