ML020880668
| ML020880668 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/18/2002 |
| From: | Heacock D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 02-158 | |
| Download: ML020880668 (58) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 18, 2002 U.S. Nuclear Regulatory Commission Serial No.02-158 Attention: Document Control Desk NAPS/JHL Washington, D.C. 20555 Docket Nos.
50-338 50-339 Gentlemen:
License Nos.
NPF-4 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 a 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
ATTACHMENT I TABULATION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY REVISION TO NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE Enclosed is a recent revision 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.
DATE:
2002-03-13 PAGE:
1 NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION DOCUMENT NUMBER EPIP-1I.01 EPIP-1.02 EPIP-1.03 EPIP-1.04 EPIP-1.05 EPIP-1.06 EPIP-2.01 EPIP-2.02 EPIP-2.04 EPIP-3.02 EPIP-3.03 EPIP-3.04 EPIP-3.05 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 REV 035 011 014 014 016 004 024 014 003 018 012 015 001 017 012 011 009 009 009 014 013 012 APPROVAL N*DATEN*
02/11/02 09/07/99 09/07/99 09/07/99 09/07/99 09/05/01 09/24/01 01/04/99 08/07/92 12/17/97 12/20/93 07/14/98 09/07/99 10/09/01 07/25/00 12/20/93 11/21/94 01/28/00 12/21/95 09/29/00 07/26/01 07/26/01 EFFECT**
- DATEN*
02/14/02 10/01/99 10/01/99 10/01/99 10/01/99 09/05/01 09/26/01 01/29/99 08/07/92 01/07/98 01/01/94 07/20/98 10/01/99 10/17/01 08/02/00 01/01/94 11/28/94 02/04/00 12/28/95 10/06/00 09/13/01 09/13/01 DOCUMENT TITLE EMERGENCY MANAGER CONTROLLING PROCEDURE RESPONSE TO NOTIFICATION OF UNUSUAL EVENT RESPONSE TO ALERT RESPONSE TO SITE AREA EMERGENCY RESPONSE TO GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS NOTIFICATION OF STATE AND LOCAL GOVERNMENTS NOTIFICATION OF NRC TRANSMITTAL OF PLANT, RADIOLOGICAL AND EMERGENCY STATUS ACTIVATION OF TECHNICAL SUPPORT CENTER ACTIVATION OF OPERATIONAL SUPPORT CENTER ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE EMERGENCY PERSONNEL RADIATION EXPOSURE RESPIRATORY PROTECTION AND KI ASSESSMENT PERSONNEL MONITORING AND DECONTAMINATION PROTECTIVE MEASURES INITIAL OFFSITE RELEASE ASSESSMENT SOURCE TERM ASSESSMENT 010 04/23/98 04/28/98 DETERMINATION OF X/Q EPIP-4. 10
DATE:
2002-03-13 PAGE:
2 NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION DOCUMENT NUMBER EPIP-4.13 EPIP-4.14 EPIP-4.15 EPIP-4.16 EPIP-4.17 EPIP-4.18 EPIP-4.21 EPIP-4.22 EPIP-4.23 EPIP-4.24 EPIP-4.25 EPIP-4.26 EPIP-4.28 EPIP-4.30 EPIP-4.31 EPIP-4.33 EPIP-4.34 EPIP-5.01 EPIP-5.03 EPIP-5.04 EPIP-5.05 EPIP-5.07 REV 009 007 011 014 014 011 008 013 013 011 008 011 007 004 003 003 002 011 016 008 013 011 APPROVAL N*DATE*3 09/29/00 12/20/93 02/18/00 02/18/00 08/12/98 08/12/98 12/20/93 04/02/93 03/13/96 01/25/02 07/23/93 07/26/01 01/09/97 01/04/99 06/20/94 11/28/00 02/18/00 12/11/96 02/18/00 07/20/99 06/25/96 07/25/00 EFFECT**
- DATE**
10/06/00 01/01/94 02/28/00 02/28/00 08/14/98 08/14/98 01/01/94 04/02/93 03/18/96 01/28/02 07/23/93 09/13/01 01/14/97 01/08/99 06/20/94 11/30/00 02/28/00 12/17/96 02/28/00 07/22/99 07/02/96 08/02/00 DOCUMENT TITLE OFFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA INPLANT MONITORING ONSITE MONITORING OFFSITE MONITORING MONITORING OF EMERGENCY RESPONSE FACILITIES MONITORING OF LEOF EVACUATION AND REMOTE ASSEMBLY AREA MONITORING POST ACCIDENT SAMPLING OF CONTAINMENT AIR POST ACCIDENT SAMPLING OF REACTOR COOLANT GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY LIQUID 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 COMMUNICATIONS FIELD TEAM RADIO OPERATOR INSTRUCTIONS TRANSPORTATION OF CONTAMINATED INJURED PERSONNEL PERSONNEL ACCOUNTABILITY ACCESS CONTROL SITE EVACUATION ADMINISTRATION OF RADIOPROTECTIVE DRUGS 007 11/28/00 11/30/00 DAMAGE CONTROL GUIDELINE EPIP-5. 08
DATE:
2002-03-13 PAGE:
3 NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION DOCUMENT NUMBER EPIP-5.09 APPROVAL REV 3*DATE*3 003 03/26/99 EFFECT3*
- DATE**
03/31/99 DOCUMENT TITLE SECURITY TEAM LEADER CONTROLLING PROCEDURE 007 05/12/99 05/17/99 RE-ENTRY/RECOVERY GUIDELINE EPIP-6.01
VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 35 (With 4 Attachments)
PAGE 1 of 7 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.
:7 Sthis Doc Xi**",-....
ced Th Afldclhe Approvals on File Effective Date
/
LF STEP ACTION/EXPECTED RESPONSE I
I RESPONSE NOT OBTAINED 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 Therefore, ERFCS parameters should be evaluated for this situation occur.
1 EVALUATE EMERGENCY ACTION LEVELS:
a)
Determine event category using, EMERGENCY ACTION LEVEL TABLE INDEX b)
Review EAL Tab associated with event category c)
Use Control Room monitors,
- ERFCS, and outside reports to get indications of emergency conditions listed in the EAL Table d) Verify EAL CURRENTLY EXCEEDED an earthquake.
accuracy should 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.
o GO TO VPAP-2802, NOTIFICATIONS AND REPORTS, to make one-hour, non-emergency reports for classification without declaration.
IF EAL was NOT exceeded, THEN RFTURN TO procedure in effect.
(STEP 1 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 35 PAGE 2 of 7 H-I
ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED Ii 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 NORMAL IMPLEMENTATION OF EMERGENCY RESPONSE ACTIONS IF deviation from normal emergency response actions warranted, THEN 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 35 PAGE 3 of 7 E
STEP:H
ACTION/EXPECTED RESPONSE 3 NOTIFY PLANT STAFF OF ALERT OR HIGHER CLASSIFICATION:
a)
Check classification ALERT OR HIGHER b) Check if emergency assembly and accountability PREVIOUSLY CONDUCTED RESPONSE NOT OBTAINED a)
GO TO Step 4.
b)
Do 1) the following:
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 35 PAGE 4 of 7 F-H STEPH I
ACTION/EXPECTED RESPONSE I -
RESPONSE NOT OBTAINED CAUTION:
Continue through this and all further instructions unless otherwise directed to hold.
4 INITIATE SUPPORTING PROCEDURES:
a) Direct Emergency Communicators to initiate the following procedures:
- 1) EPIP-2.01, 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 35 PAGE 5 of 7 F-I
-1EH
ACTION/EXPECTED RESPONSE F-]
5 CHECK TSC ACTIVATED STEP 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
SITE AREA EMERGENCY TO
- General Emergency GO TO EPIP-1.05.
RESPONSE TO GENERAL EMERGENCY NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 35 PAGE 6 of 7 RESPONSE NOT OBTAINED 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,,
Turnover Checklist.
STE ACTION/EXPECTED RESPONSE I
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:
"* 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 PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 35 PAGE 7 of 7
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.
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.
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-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT PAGE INDEX 1
pf 413
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 I & 2 AND Manual trip from Control Room -
FAILED NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB A)
PAGE
- SAFETY, SHUTDOWN, OR ASSESSMENT 1
SYSTEM EVENT 2 f 43
CONDITION/APPLICABILITY INDICATION CLASSIFICATION
- 3.
Inability to monitor a significant transient in progress MODES 1, 2, 3 & 4 Most (>75%)
or all annunciator alarms on panels "A" to "K" -
NOT AVAILABLE AND All computer monitoring capability (e.g., 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 Control Room with control not established within 15 minutes Evacuation of the Control Room with local shutdown control not established within 15 minutes ALL MODES NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB A)
PAGE
- SAFETY, SHUTDOWN, OR ASSESSMENT 1
SYSTEM EVENT 3Of_43 SITE AREA EMERGENCY SITE AREA EMERGENCY
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 0
0 0
Service Water Component Cooling RHR AND RCS temperature GREATER THAN 140 OF
- 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 AND Manual trip - REQUIRED AND Manual trip from Control Room SUCCESSFUL NUMBER ATTACHMENT TITLE
-REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB A)
PAGE
- SAFETY, SHUTDOWN, OR ASSESSMENT 1
SYSTEM EVENT
____________4 of_43 ALERT
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 "K" for GREATER THAN 15 minutes AND
"* All computer monitoring capability (e.g., plant
- 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 required mode within technical specification limits Intentional reduction in power, load or temperature IAW T.S. Action Statement HAS COMMENCED NOTIFICATION OF UNUSUAL EVENT MODES 1,
- 2. 3 & 4 AND T.S. Action Statement time limit for mode change CANNOT BE MET NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB A)
PAGE
- SAFETY, SHUTDOWN, OR ASSESSMENT 1
SYSTEM EVENT 5of_43 CLASSIFICATION ALERT
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 RCS RCS pressure THAN 2000 psig OR NDT Protection IN SERVICE CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT LESS System -
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 Unplanned loss of most
(>75%)
or all annunciators on panels "A" to "K" for GREATER THAN 15 minutes NOTIFICATION OF UNUSUAL EVENT MODES 1, 2, 3 & 4 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB A)
PAGE
- SAFETY, SHUTDOWN, OR ASSESSMENT 1
SYSTEM EVENT
____________6 of_43
CONDITION/APPLICABILITY
- 12.
Loss of communications capability ALL MODES INDICATION Station PBX phone system FAILED AND
- Station Gai-tronics system FAILED AND CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT a
Station UHF radio system FAILED NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB A)
PAGE
- SAFETY, SHUTDOWN, OR ASSESSMENT 1
SYSTEM EVENT
____________7 of_43 I--
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:
a)
Fuel clad integrity failure as indicated by any of the following:
RCS specific activity greater than or equal to 300.0 liCi/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 RM-RMS-265,
-266 GREATER THAN 1.88x10 2 R/hr or b)
Loss of RCS integrity as indicated by any of the fol 1 owing:
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-I.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT N.
(TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT 1
____________8 of_43 GENERAL EMERGENCY
CONDITION/APPLICABILITY INDICATION CLASSIFICATION
- 2.
Fuel failure with steam generator tube rupture ALL MODES Any two of a),
b) or c) exist and the third is imminent:
a)
Fuel clad integrity failure as indicated by any of the following:
RCS specific activity greater than 300 PCi/gram dose equivalent 1-131 OR 5 or more core exit thermocouples GREATER THAN 1200 OF OR High Range Letdown radiation monitor I-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 35 ATTACHMENT (TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT PAfE 1
____________9 of_43 GENERAL EMERGENCY
CONDITION/APPLICABILITY
- 3. RCS leak rate limit -
EXCEEDED MODES 1, 2,
3,
& 4 INDICATION Loss of Reactor Coolant in progress and inventory balance indicates leakage GREATER THAN 300 gpm CLASSIFICATION SITE AREA EMERGENCY 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 35 ATTACHMENT (TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT 1
____________10 of_43
CONDITION/APPLICABILITY
- 4.
Gross primary to secondary leakage with loss of offsite power MODES 1, 2,
3,
& 4 INDICATION CLASSIFICATION Steam Generator Tube Rupture -
IN PROGRESS SITE AREA EMERGENCY AND Safety Injection REQUIRED AND
"* Vent Vent A Kaman Monitor RM-VG-179 GREATER THAN 1.3 x 108 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 GREATER THAN 1x10 6 cpm AND A subsequent loss of offsite power indicated by zero volts on voltmeters for 4160V buses D, E, & F NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT 1
1 of_43
CONDITION/APPLICABILITY
- 5.
RCS leak rate limit EXCEEDED MODES 1, 2,
3,
& 4 INDICATION CLASSIFICATION Pressurizer level cannot be maintained greater than 20%
with one (1) Charging/SI pump in operation ALERT AND RCS inventory balance indicates leakage - greater than 50 gpm
- 6.
Gross primary to secondary leakage MODES 1, 2, 3,
& 4 Steam Generator Tube Rupture IN PROGRESS AND Safety Injection REQUIRED NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT 1
___________12 of_43 ALERT
CONDITION/APPLICABILITY
- 7.
Excessive primary to secondary leakage with loss of offsite power MODES 1, 2,
3,
& 4 INDICATION
"* Intentional reduction in power, load or temperature because the unit has entered an Action Statement or will exceed an LCO AND
"* Vent Vent A Kaman Monitor RM-VG-179 GREATER THANI 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 jiCi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122,
-222 RM-SS-123,
-223 RM-SS-124,
-224 GREATER THAN jx10 5 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 35 ATTACHMENT (TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT 1
____________13 of_43 CLASSIFICATION ALERT
CONDITION/APPLICABILITY
- 8.
RCS leak rate or leakage requiring plant shutdown IAW T.S. 3.4.6.2 MODES 1. 2, 3,
& 4 INDICATION
"* Intentional reduction in power, load or temperature because the unit has entered an action statement or will exceed an LCO AND
"* Unidentified RCS leakage greater than 1 gpm OR Identified leakage greater than 10 gpm OR CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT Controlled leakage to RCP Seals - greater than 30 gpm total OR Any pressure boundary leakage -
EXISTS
- 9.
Primary to Secondary leakage
- greater than 1 gpm MODES 1, 2, 3,
& 4 Intentional reduction in power, load or temperature because the unit has entered an action statement or will exceed an LCO NOTIFICATION OF UNUSUAL EVENT AND Primary to Secondary leakage greater than 1 gpm OR N-16 monitor indicates rimary to secondary eakage greater than T.
S.
allowable limits NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB B)
PAGE REACTOR COOLANT SYSTEM EVENT 1
____________14_of_43
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 jiCi/gram dose equivalent 1-131 OR CLASSIFICATION GENERAL EMERGENCY 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)
- 2.
Probable large radi oacti vi ty release initiated by loss of heat sink leading to core degradation Loss of Main Feedwater System, Condensate System and Auxiliary Feedwater System MODES 1, 2,
3 & 4 NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 AGE 1
____________15 of_43 CAUTION:
EAL A.1 is duplicated below for cross-reference/comparison to EAL C.2:
A.I.
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 GENERAL EMERGENCY
CONDITION/APPLICABILITY
- 3.
Probable large radioactivity release initiated by failure of rotection system to ring Rx subcritical and causing core degradation ALL MODES INDICATION Rx nuclear power after a trip - greater than 5%
AND RCS pressure greater than or equal to 2485 psig OR Containment pressure and temperature rapidly increasing CLASSIFICATION GENERAL EMERGENCY
- 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 /> NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1
____________16_of_43 GENERAL EMERGENCY
CONDITION/APPLICABILITY
- 5.
Probable large radioactivity release initiated by LOCA with loss of ECCS and containment cooling ALL MODES INDICATION Loss of reactor coolant in progress AND
"* High or low head ECCS flow not being delivered to the core (if expected by plant conditions)
AND
"* Containment RS sump temperature greater than 190OF and NOT decreasing OR All Ouench Spray and Recirculation Spray systems NOT OPERABLE NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1
AfE 1
_____________17 of 43 CLASSIFICATION GENERAL EMERGENCY
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 jiCi/gram dose equivalent 1-131 OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 GREATER THAN 1.2xlO4 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 35 ATTACHMENT (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT PaGE 1
8 of_43 CLASSIFICATION SITE AREA EMERGENCY
CONDITION/APPLICABILITY
- 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 OR Water level in spent fuel pool below top of spent fuel CLASSIFICATION SITE AREA EMERGENCY AND Verified damage to irradiated fuel resulting in readings on Vent Vent "B" Kaman monitor RM-VG-180 GREATER THAN 2.74 x 108 uCi/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 liCi/sec
- 8. Severe Fuel Clad
- 8.
Severe Fuel Clad Damage MODES 1. 2. 3. & 4 High Range Letdown radiation monitor NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1AGE 1
_____________19 of_43 ALERT 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
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" Kaman monitor RM-VG-180 GREATER THAN 1.83 x 1O6 iiCi/sec 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 35 ATTACHMENT
%ý (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 2 A4E 1
____________20 of_43
CONDITION/APPLICABILITY
- 11.
Fuel clad damage indication MODES 1, 2, 3, & 4 INDICATION Intentional reduction in ower, load or temperature AW reactor coolant activity T.S. Action Statement -
HAS COMMENCED CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT O R High Range Letdown radiation monitor
- 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 35 ATTACHMENT (TAB C)
PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT PAG 1
____________21 of_43 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
CONDITION/APPLICABILITY
- 1.
Extremely high containment radiation, pressure and temperature MODES 1, 2, 3,
& 4 INDICATION Containment High Range radiation monitor RM-RMS-165,
-166 or RM-RMS-265,
-266 GREATER THAN 3.76 x 102 R/hr CLASSIFICATION GENERAL EMERGENCY AND Containment pressure greater than 45 psia and not decreasing OR Containment temperature greater than 2800F
- 2.
High-high containment radiation, pressure, and temperature MODES 1, 2, 3,
& 4 Containment High Range radiation monitor RM-RMS-165,
-166 RM-RMS-265,
-266 GREATER THAN 1.88 x 102 R/hr or AND Containment pressure greater than 27.75 psia not decreasing and OR Containment temperature greater than 200 OF NUMBER ATTACHMENT TITLE
-REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB D)
PAGE ATTACHMENT CONTAINMENT EVENT 1
____________22 of_43 SITE AREA EMERGENCY
CONDITION/APPLICABILITY INDICATION CLASSIFICATION
- 3.
High Containment radiation, pressure and temperature MODES 1, 2,
3,
& 4 Containment High Range radiation monitor 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 35 ATTACHMENT (TAB D)
PAGE ALrACHENT iCONTAINMENT EVENT 1
____________23 of_43 ALERT
CONDITION/APPLICABILITY INDICATION CLASSIFICATION
- 1.
Release imminent or in progress and site boundary doses projected to exceed 1.0 Rem TEDE or 5.0 Rem Thyroid CDE HP assessment indicates actual or projected doses at or beyond site boundary greater than 1.0 Rem TEDE or 5.0 Rem Thyroid CDE ALL MODES
- 2.
Release imminent or in progress and site boundary doses projected to exceed 0.1 Rem TEDE or 0.5 Rem Thyroid CDE ALL MODES HP assessment indicates actual or projected dose at or beyond Site Boundary exceeds 0.1 Rem TEDE or 0.5 Rem Thyroid CDE NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB E)
PAGE ATTACHMENT RADIOACTIVITY EVENT 1
____________24 of_43 GENERAL EMERGENCY SITE AREA EMERGENCY
CONDITION/APPLICABILITY 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
- Clarifier Effluent RM-LW-111 GREATER THAN 4.8 x 105cpm 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 ýiCi/sec Vent Vent A MGPI RM-VG-179 GREATER THAN 1.73 x 106 ýiCi/sec Vent Vent B Kaman RM-VG-180 GREATER THAN 1.83 x 106 ECi/sec Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 106 g=Ci/sec Process Vent Kaman RM-GW-178 GREATER THAN 2.0 x 107 9iCi/sec Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 107 ýiCi/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 35 ATTACHMENT (TAB E)
PAGE ATTACHMET 1RADIOACTIVITY EVENT 1
_______2 of43 3.
CLASSIFICATION ALERT
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 1 Control Room Area I RMS-157 Aux.
Bldg. Control Area I RMS-154 Decon.
Bldg. Area I
5RMS-1I Fuel Pool Bridge Area IRMI53 New fuel storage Area I M-52 Laboratory Area I M-58 77 Sample Room Area IRMS-156 1
NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB E)
PAGE RADIOACTIVITY EVENT 1
_____________26 of 43 CLASSIFICATION ALERT
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 RM-LW-111 GREATER THAN 4.8 x 104 cpm Discharge Canal RM-SW-130 or -230 GREATER THAN 5 x 103 cpm Vent Vent A Kaman I RM-VG-179 GREATER THAN 1.83 x 105 jiCi/sec Vent Vent A MGPI RM-VG-179 GREATER THAN 1.73 x 105 ACi/sec Vent Vent B Kaman RM-VG-180 GREATER THAN 1.83 x 105 pjCi/sec Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 105 ACi/sec Process Vent Kaman RM-GW-178 GREATER THAN 2.0 x 106 jiCi/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-.01.
EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB E)
PAGE ATTACHMENT RADIOACTIVITY EVENT 1
7 of_43
CONDITION/APPLICABILITY INDICATION CLASSIFICATION
- 1.
Major secondary line break with significant primary to secondary leakage and fuel damage indicated MODES 1, 2, 3, & 4 Conditions a) and b) exist with c):
a)
Uncontrolled loss of secondary coolant IN PROGRESS AND SITE AREA EMERGENCY b)
RCS specific activity exceeds limits of T.S. Figure 3.4-1 (See Attachment 2)
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 RM-VG-179 GREATER THAN 6.45 x 107 PCi/sec OR HP determines Site Boundary DDE GREATER THAN 50 mrem/hr OR Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 6.21 x 107 PCi/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 35 ATTACHMENT (TAB G)
PAGE L
LOSS OF SECONDARY COOLANT 2
AGE 1
_____________28 of_43
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 Kaman Monitor RM-VG-179 GREATER THAN 1.83 x 106 iiCi/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 uCi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122,
-123,
-124 RM-SS-222,
-223,
-224 GREATER THAN lx105 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 break MODES 1, 2, 3, & 4 Uncontrolled loss of secondary coolant -
IN PROGRESS NOTIFICATION OF UNUSUAL EVENT NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB G)
PAGE 1---- C1MEN I
LOSS OF SECONDARY COOLANT 9 of_43 CLASSIFICATION ALERT
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
"* Ammeters for 4160V Emergency Buses H & J both indicate - zero (0) amps CLASSIFICATION SITE AREA EMERGENCY
- 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 NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB H)
PAGE ELECTRICAL FAILURE 1
____________30 of_43 SITE AREA EMERGENCY
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 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 0
All station battery ALERT DC power voltmeters indicate - zero (0) volts ALL MODES AND
"* No light indication available to Reserve Station Service Breakers
- 15D1, 15EI and 15F1 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB H)
PAGE ATTACHMENT ELECTRICAL FAILURE 1
3 of_43
CONDITION/APPLICABILITY
- 5.
Loss of offsite power or onsite AC power capability ALL MODES INDICATION Unit main generator and both emergency diesel generators out of service OR Loss of all 34.5 KV reserve station service buses CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB H)
PAGE ELECTRICAL FAILURE 2_of_43
CONDITION/APPLICABILITY
- 1. Fire resulting in degradation of safety systems MODES 1, 2,
3,
& 4 INDICATION Fire which causes major degradation of a safety system function required for protection of the public CLASSIFICATION SITE AREA EMERGENCY AND Affected systems are caused to be NOT operable as defined by Tech.
Specs.
- 2.
Fire potentially Fire which has potential for ALERT affecting station causing a safety system not to safety systems be operable as defined by Tech.
Specs.
MODES 1, 2,
3,
& 4
- 3.
Fire lasting greater than 10 minutes in Protected Area or Service Water Pump/Valve House 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 ALL MODES NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB I)
PAGE SFIRE 1
_____________33 of_43
CONDITION/APPLICABILITY
- 1.
Loss of physical Station control ALL MODES INDICATION CLASSIFICATION Shift Supervisor has been GENERAL informed that the security EMERGENCY force has been neutralized 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, 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 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)
NOTIFICATION OF UNUSUAL EVENT Attempted sabotage NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB J)
PAGE SECURITY EVENT L
-1_______1__1 34 of_43
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
- 3.
Entry of toxic or flammable gases into plant vital areas other than the Control Room Explosion which results in severe degradation of any of the following systems required for safe shutdown:
CVCS System OR ECCS System OR Main/Auxiliary Feedwater System Uncontrolled release of toxic or flammable agents greater than life threatening or explosive limits in Vital Areas MODES 1, 2,
3,
& 4 AND Evacuation other than REQUIRED of Vital Area Control Room 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 35 ATTACHMENT (TAB K)
PAGE HAZARD TO STATION OPERATION 1
1_ 35 of 43 SITE AREA EMERGENCY SITE AREA EMERGENCY
CONDITION/APPLICABILITY
- 4.
Severe missile damage to safety systems MODES 1, 2, 3, & 4 INDICATION Missile impact causing severe degradation of safety systems required for unit shutdown CLASSIFICATION SITE AREA EMERGENCY
- 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 MODES 1 & 2 Failure of turbine/generator rotating equipment resulting in casing penetration NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB K)
PAGE ATTACHMENT HAZARD TO STATION OPERATION 1
_____________36 of_43 ALERT
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 0R 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 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 35 ATTACHMENT (TAB K)
PAGE ATTACHMEN iHAZARD TO STATION OPERATION 37_of_43
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 35 ATTACHMENT (TAB K)
PAGE HAZARD TO STATION OPERATION 1
3 of_43
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 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 O.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.
Flood or low water level above design levels MODES 1, 2, 3, & 4 Either condition a) or b) exists a)
Flood in the Lake Anna Reservoir with indicated 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 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB L)
PAGE NATURAL EVENTS 11 39 of 43 SITE AREA EMERGENCY
CONDITIONIAPPLICABILITY
- 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 O.04g
- 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 or low water level near design levels ALL MODES Flood in the Lake Anna Reservoir with indicated level
- greater than 263 feet MSL 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 35 ATTACHMENT (TAB L)
PAGE ATTACHMENT NATURAL EVENTS 40 of_43 CLASSIFICATION ALERT ALERT I
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 or low water level ALL MODES Flood in the Lake Anna Reservoir with indicated level
- greater than 254 feet MSL NOTIFICATION OF UNUSUAL EVENT 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 35 ATTACHMENT (TAB L)
PAGE NATURAL EVENTS 1
____________41 of_43
CONDITION/APPLICABILITY INDICATION CLASSIFICATION
- 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 Shift Supervisor/Station Emergency Manager judgement 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 which have the potential to degrade or are actually degrading the level of safety of the station ALL MODES Shift Supervisor/Station Emergency Manager judgement NUMBER ATTACHMENT TITLE REVISION EPIP-I.01 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB M)
PAGE MISCELLANEOUS ABNORMAL EVENTS 4
AGE
____________42 of_43 GENERAL EMERGENCY ALERT
CONDITION/APPLICABILITY
- 4.
Station conditions which warrant increased awareness of state and/or local authorities ALL MODES INDICATION Shift Supervisor judgement that any of the following exist:
Unit shutdown is other than 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 EMERGENCY ACTION LEVEL TABLE 35 ATTACHMENT (TAB M)
PAGE MISCELLANEOUS ABNORMAL EVENTS 4
AGE
____________43 of_43 CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT
275 250 225 200 175 150 125 100 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER: T.S.
FIGURE 3.4-1 DOSE EOUIVALENT 1-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0 ýtCi/gm Dose Equivalent 1-131 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 TECH SPEC FIGURE 3.4-1 35 ATTACHMENT PAGE 2
1 of 1 I
II I
j OPERATION I---zzzOPERATION_
II I
-i ACCEPTABLEU T
OPPERATION D
0 S
E E
0 U
I V
A L
E N
T 1
3 1
3 1
m i
C r
0 C
i
/
m 75 50 25 0
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.
NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 TURNOVER CHECKLIST 35 ATTACHMENT PAGE 3
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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).
NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 CONSIDERATIONS FOR OPERATIONS RESPONSE 35 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 4
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