ML031140382
| ML031140382 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/11/2003 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031140382 (65) | |
Text
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Davis Besse Power Station Transmittal / Receipt Acknowledgement Control Copy Number: 1665 Transmittal Number:
0304-26355 Transmittal Date:
04-11-2003 Mtop I Adlre-S-NRCDIVISION OF EMERGENCY PREPARDNESS WASHINGTON, D.C. 20555 Document holders are responsible for control and maintenance of documents in accordance with the actions specified by this transmittal. Outdated material shall either be removed and destroyed or marked to reflect that it is superseded or voided and is no longer considered controlled.
Note: Destroy Safeguard information by shredding.
File documents in tab order as identified on the Table of Contents Contact Document Control with any questions at (419)-321-7483
-G
(
Davis Besse Power Station Transmittal / Receipt Acknowledgement Dnuiimpnt Control Copy Number: 1665 Transmittal Number:
0304-26355 Transmittal Date:
04-11-2003
.-I.........
TOC I old EPIA new EPIA TOC 2 Type EPOC PROC EPOC PROC Number RA-EP-0l1500 RA-EP-01500 Sht/Sec Changes Rev COO-0352, C95-131 1, C96-1869, C98-0966 0001 0002 Status APPROVED APPROVED
Page 1 of 62 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE RA-EP-01500 EMERGENCY CLASSIFICATION REVISION 02 Prepared by:
Procedure Owner:
Effective Date:
APR I 1 2003 Procedure Classification:
X Safety Related
_ Quality Related Non-Quality Related Paul F. Timmerman Manager - Security LEVEL OF USE:
IN-FIELD REFERENCE
2 RA-EP-01500 Revision 02 TABLE OF CONTENTS Page 1.0 PURPOSE
.3
2.0 REFERENCES
3 3.0 DEFINITIONS 4
4.0 RESPONSIBILTIES 5
5.0 INITIATING CONDITIONS 5
6.0 PROCEDURE 6
6.1 Classification of Emergency
.6 6.2 Downgrading Emergency Classification.
6.3 Terminating Emergency Classification
.9 INDEX OF EMERGENCY ACTION LEVEL CONDITIONS 10
- 1. Primary System Events.12
- 2. Reactor Coolant System Leak Rate.21
- 3. Safety System Functions.24
- 4. Electrical Failures................................................................................
28
- 5. Secondary System Events.31
- 6. Radiation Release Events.34
- 7. Hazards to Station Operations.41
- 8. Natural Events.51
- 9. M iscellaneous......................................................................................
55
- 10. Downgrading Guidelines.57
- 11. Terminating Guidelines.58 7.0 FINAL CONDITIONS.59 8.0 RECORDS.59 ATTACHMENT 1. Summary of Emergency Action Levels.60 COMMITMENTS.........................................................................................................
61
3 RA-EP-01500 Revision 02 1.0 PURPOSE This procedure provides guidelines for conditions at which specific emergency classifications must be declared.
2.0 REFERENCES
2.1 Developmental 2.1.1 NUREG-0654/FEMA REP-1, Rev. 1 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.1.2 Updated Safety Analysis Report, DBNPS 2.1.3 Davis-Besse Nuclear Power Station Emergency Plan 2.1.4 Technical Specifications, DBNPS Unit No. 1, Appendix A and B to License No.
NPF3 2.1.5 NUMARC NESP-007, Methodology for Development of Emergency Action Levels, Revision 1 2.1.6 Davis-Besse Offsite Dose Calculation Manual 2.1.7 NRC Branch Position on acceptable deviation to Appendix I to NUREG-0654IFEMA-REP-1 dated July 11, 1994.
2.2 Implementation 2.2.1 RA-EP-01600, Unusual Event 2.2.2 RA-EP-01700, Alert 2.2.3 RA-EP-0 1800, Site Area Emergency 2.2.4 RA-EP-01900, General Emergency 2.2.5 RA-EP-02710, Reentry 2.2.6 RA-EP-02720, Recovery Organization 2.2.7 RA-EP-028 10, Tornado 2.2.8 RA-EP-02820, Earthquake 2.2.9 RA-EP-02830, Flooding 2.2.10 RA-EP-02840, Explosion 2.2.11 RA-EP-02850, Hazardous Chemical and Oil Spills
4 RA-EP-01500 Revision 02 2.2.12 DB-OP-02544, Security Events 2.2.13 DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture 2.2.14 DB-CH-01814, Steam Generator Leak Rate Determination 2.2.15 Technical Specifications 2.2.16 Davis-Besse Offsite Dose Calculation Manual 3.0 DEFINITIONS 3.1 ALERT - Event(s) are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the DBNPS. Any releases are expected to be limited to small fractions of the EPA Protective Action Guidelines exposure levels.
3 2 CORE MELT SEOUENCE - A situation in which the core would be uncovered and there is no means for restoring cooling to the core. Without cooling, overheating and melting of the fuel will occur.
3.3 EMERGENCY ACTION LEVELS (EALs) - Radiological dose rates, specific contamination levels of airborne, waterborne, or surface-deposited concentrations of radioactive materials; or specific instrument readings and indications (including their rate of change) that may be used as thresholds for initiating such specific emergency measures as designating a particular classification of emergency, initiating a notification procedure, or initiating a particular protective action.
3.4 FUNCTIONAL - A system, subsystem, train, component or device though degraded in equipment condition or configuration, is FUNCTIONAL if it is capable of maintaining respective system parameters within acceptable design limits.
3.5 GENERAL EMERGENCY - Event(s) are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
3.6 LOSS - A state of inoperability in which FUNCTIONAL AND OPERABLE status cannot be maintained. A system, subsystem, train, component or device is NOT LOST if its FUNCTIONALITY is assured.
3.7 OPERABLE - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functions(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s), are also capable of performing their stated support function(s).
3.8 SITE AREA EMERGENCY - Event(s) are in progress or have occurred which involve actual or likely major failures of the DBNPS functions needed for the protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.
5 RA-EP-01500 Revision 02 3.9 TRANSITORY EVENT - An event which is classifiable in accordance with RA-EP-01500, Emergency Classification, but becomes a lower classification or non-classifiable event before being declared.
3.10 UNUSUAL EVENT - Event(s) are in progress or have occurred which indicate a potential degradation of the level of safety of the DBNPS. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
4.0 RESPONSIBILITIES 4.1 The Shift Manager shall be responsible for the initial implementation of this procedure.
4.2 The individual having formal control as Emergency Director is the final authority on upgrading or downgrading the emergency classification. This responsibility to classify an event may not be delegated.
5.0 INITIATING CONDITIONS 5.1 Station personnel report an abnormal or unusual situation to the operating shift crew, or they observe an off-normal event.
5.2 A supplementary action step in a plant procedure (e.g., the Emergency Operating Procedure, Alarm Procedure, Abnormal Procedures, etc.) refers to this procedure for classification of the indicated plant conditions.
6 RA-EP-01500 Revision 02 6.0 PROCEDURE 6.1 Classification of Emergency:
6.1.1 When indications of abnormal occurrences are received by the Control Room staff, the Shift Manager shall:
- a.
Verify the indications of the off-normal event or reported sighting.
b Ensure that the immediate actions (e.g., use of the Emergency Operating Procedure and Abnormal Procedures) are taken for the safe and proper operation of the plant.
- c.
Compare the abnormal conditions with those listed in the Index of Emergency Action Levels (EAL).
- d.
Turn to the appropriate tab which corresponds to the condition picked from the EAL Index.
NOTE 6 1. L.e The specific emergency action levels described in this procedure are not all inclusive. The Emergency Director shall declare an appropriate emergency classification whenever, in his judgment, the station status warrants such a declaration. A "Miscellaneous" category is included to provide guidance in classifying events not specifically listed elsewhere.
CAUTION 6.1.1.e Many of the emergency action levels described in this procedure are not intended to be used during maintenance and/or testing situations where abnormal temperature, pressure, equipment status, etc., is expected. Each EAL contains information on the Mode(s) of Operation during which it is applicable.
- e.
Assess the information available from valid indications or reports and classify the situation.
- 1.
When an event is classified, the Shift Manager shall become the Emergency Director during activation of the Davis-Besse Emergency Plan and shall be responsible for coordinating the actions of the emergency organization until relieved.
7 RA-EP-01500 Revision 02
- 2.
The Unit Supervisor may assume the Emergency Director duties only if the Shift Manager is not in the Control Room or is incapable of performing those duties.
- 3.
The Shift Engineer (Shift Technical Advisor) may assume the Emergency Director duties only if neither the Shift Manager nor the Unit Supervisor is in the Control Room and capable of performing those duties.
- 4.
Upon arrival in the Control Room, the Emergency Assistant Plant Manager or Emergency Plant Manager may relieve the Emergency Director.
- 5.
The Emergency Plant Manager may assume the Emergency Director duties from the Technical Support Center (TSC) if the TSC and Emergency Control Center/Emergency Operations Facility (ECCIEOF) are activated.
- 6.
The Emergency Director shall remain in the Control Room until the TSC and ECC/EOF have been activated.
CAUTION 6.1.L.f
- 1.
If it appears that several emergencies of different classes have occurred at the same time, the highest classification indicated should be declared.
- 2.
If a Transitory Event has occurred, notification of the offsite agencies is still required.
- f.
Use the RA-EP-01600, Unusual Event; RA-EP-01700, Alert; RA-EP-01800, Site Area Emergency; or RA-EP-01900, General Emergency procedure to ensure that immediate notification requirements are met and the proper Emergency Plan response is taken
- 1.
Transitory Events
- a.
IF the emergency starts at a higher classification, but before the event is classified, the event is mitigated to a lower classifications, THEN
- 1.
Identify current emergency classification status on the Initial Notification Form and provide a brief description of the transitory event.
8 RA-EP-01500 Revision 02
- b.
IF the emergency is mitigated before an emergency classification can be made and no emergency classification initiating condition exists, THEN
- 1.
The Shift Manager, or designee, will contact the Emergency Offsite Manager (EOM). The EOM will collect the needed information and phone the State of Ohio, Ottawa County, and Lucas County Emergency Management Agencies. If the agencies can not be contacted, the EOM will fax the information to the offsite agencies and the Supervisor - Emergency Preparedness, or designee, will provide a follow-up phone call the following morning.
- c.
IF it is discovered that an emergency classification was missed during a review, i.e., logs, paper work, etc.
THEN
- 1.
The Shift Manager, or designee, will contact the Emergency Offsite Manager (EOM). The EOM will collect the needed information and phone the State of Ohio, Ottawa County, and Lucas County Emergency Management Agencies. If the agencies can not be contacted, the EOM will fax the information to the offsite agencies and the Supervisor - Emergency Preparedness, or designee, will provide a follow-up phone call the following morning.
- g.
Continually evaluate the plant conditions to ensure the proper emergency classification is being utilized and the classification is upgraded as conditions dictate in accordance with Steps 6.1.1.c. through 6.1.1.e.
- h.
Downgrade the emergency classification as conditions improve, utilizing Section 6.2 as a guide.
6.2 Downgrading Emergency Classification:
6.2.1 Compare the existing conditions with information contained in Tab 10, Downgrading Guidelines.
6.2.2 Downgrade the emergency classification, if appropriate.
6.2.3 Continue to observe existing conditions.
6.2.4 Upon downgrading of the emergency classification refer to RA-EP-01600, Unusual Event; RA-EP-01700, Alert; RA-EP-01800, Site Area Emergency; or continue to Section 6.3, Terminating Emergency Classification.
6.2.5 Perform any necessary reentry actions per RA-EP-027 10, Reentry.
9 RA-EP-01500 Revision 02 6.3 Terminating Emergency Classification 6.3.1 Existing conditions have been compared with the Emergency Action Levels and judgment made that conditions have stabilized and termination is appropriate.
6.3.2 Compare the existing conditions with information contained in Tab 11, Termination Guidelines.
6.3.3 Terminate emergency classification.
6.3.4 Perform any necessary reentry actions per RA-EP-027 10, Reentry.
NOTE 6.3.5 Recovery actions are required for all classifiable emergencies.
6.3.5 Perform any necessary recovery actions per RA-EP-02720, Recovery Organization.
10 RA-EP-01500 Revision 02 INDEX OF EMERGENCY ACTION LEVEL CONDITIONS Tab Condition Page No(s)
- 1.
Primary System Events A.
Failure of a primary relief valve..............................................
12 B.
Core fuel damage.............................................
13-15 C.
Loss of fission product barriers.............................................
16 D.
Abnormal CTMT atmosphere.............................................
17-20
- 2.
Reactor Coolant System Leak Rate A.
Abnormal RCS leak rate......................
21-23
- 3.
Safety System Functions A.
CRD, RPS.............................................
24 B.
SW, DH, CCW, MU, BPI, LPI/DH, MFW, AFW............................................ 25-26 C.
Loss of CTRM alarms, Indication, or Communications................................... 27
- 4.
Electrical Failures A.
AC......
28-29 B.
DC......
30
- 5.
Secondary System Events A.
Major steam leak.................
31-32 B.
Main steam safety valve failure...........................
33 6
Radiation Release Event A.
High radiation levels in plant..........................
34 B.
Fuel handling accident..........................
35 C.
Abnormal effluent release..........................
36-37 D.
Abnormal radiation levels at site boundary.38-40
11 RA-EP-01500 Revision 02 INDEX OF EMERGENCY ACTION LEVEL CONDITIONS Tab Condition Page No(s).
- 7.
Hazards to Station Operations A.
Fire..................
41 B.
Aircraft crash.................
42 C.
Train derailment.................
43 D.
Explosion.................
44 E.
Toxic or flammable gas.................
45-46 F.
Turbine damage.................
47 G.
Missile impact.................
48 H.
Control Room evacuation.................
49 I.
Security threat..............
... 50
- 8.
Natural Events (Within Ottawa County)
A.
Earthquake......................
51 B.
Tornado......................
52 C.
Hurricane Force Winds......................
53 D
Flooding, Low Water......................
54
- 9.
Miscellaneous......................
55-56
- 10.
Downgrading Guidelines......................
57
- 11.
Termination Guidelines..................................................................................................58
12 RA-EP-0 1500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 1. PRIMARY SYSTEM EVENTS A. FAILURE OF A PRIMARY RELIEF VALVE Emergency Class-i ficationn
('n"rnt; nn Tnclicatinn(s)
- 1. Failure of safety related safety valve, or relief valve, to close following a pressure reduction
- 1.
Indication of flow through Pressurizer Reliefs (as indicated on Panel C5798, C5799 and C5705)
AND
- 2.
RCS Pressure drop to
<1600 psig Unusual Event RA-EP-01600 All Modes See Also: Abnormal RCS Leak Rate (2-A-1 thru 4)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
13 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 1. PRIMARY SYSTEM EVENTS B. CORE FUEL DAMAGE Emergency Classificationn Cnnditinn Ind icit inn (-)
- 1. High reactor coolant activity sample requiring plant shutdown per T.S. 3 4 8
- 1. Confirmed primary coolant activity sample results indicate > T.S. 3.4.8 AND
- 2. Plant shutdown required and in progress Unusual Event RA-EP-01600 Modes 1 & 2
- 2. Very high coolant activity Confirmed primary coolant Alert sample results indicate >300 RA-EP-01700
[tCi/gram DOSE EQUIVALENT All Modes I-131 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
14 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 1. PRIMARY SYSTEM EVENTS B. CORE FUEL DAMAGE (Cont.)
Emergency 1--Antl:--
'..A..JL JUL (lULL IL IL1.!
lL.QL.IWII Y
.U3 tUfJ
- 3.
Core damage with in-adequate core cooling determined
- 1.
Confirmed primary coolant sample results indicate:
A. DOSE EQUIVALENT 1-131
>T.S. 3.4.8 OR B. 100/ E jtCi/gram specific activity, AND
- 2.
The incore thermocouples indicate superheated con-ditions in the core Site Area Emergency RA-EP-01800 All Modes
- 4. Core damage with other plant conditions making a release of large amounts of radioactivity possible
- 1.
Confirmed primary coolant sample results indicate
>300 liCi/gram DOSE EQUIVALENT I-131 AND
- 2.
Incore thermocouple temperatures correspond to region 3 or 4 of DB-OP-02000 Figure 2 General Emergency RA-EP-01900 All Modes AND
- 3.
A. Containment radiation level is> 104 R/hr (RE 4596A/RE 4596B)
OR B. SFAS level 4 trip (Containment high-high pressure)
See Also:
Loss of Fission Product Barriers (1-C-1)
Abnormal Containment Atmosphere (l-D-1 thru 3)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
15 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 1. PRIMARY SYSTEM EVENTS B. CORE FUEL DAMAGE (Cont.)
Emergency
('lassiftcatinn Condition Indirntinn(c)
- 5. Core melt situations
- 1.
Any sequence of events has occurred in which severe core damage (such as core melting) has taken place AND
- 2.
A failure of containment is ready to take place (imminent)
General Emergency RA-EP-01900 All Modes NOTE Examples of some scenarios which could place the plant in this conditions are:
- 1. Either a small or large LOCA occurs with a concurrent failure of the ECCS to perform, leading to severe core degradation or melting OR
- 2. A transient is initiated by a loss of the main feedwater system followed by a failure of the auxiliary feedwater system for an extended period with core melting resulting OR
- 3. A transient occurs requiring operating of shutdown systems with failure to trip which results in core damage, or additional failures of core cooling and makeup systems occur which lead to a core melt OR
- 4. A failure of offsite and onsite power along with total loss of auxiliary feedwater makeup capability occurs for several hours which leads to a core melt OR
- 5. A small LOCA occurs with initially successful ECCS, however, a subsequent failure of RCS heat removal systems over a period of several hours leads to a core melt.
See Also:
Loss of Fission Product Barriers (1-C-1)
Abnormal Containment Atmosphere (1-D-1 through 3)
Abnormal RCS Leak Rate (2-A-1 through 4)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
16 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 1. PRIMARY SYSTEM EVENTS C. LOSS OF FISSION PRODUCT BARRIERS Emergency Condition Indication(s)
Classification
- 1. Loss of 2 of 3 fission product barriers with a potential loss of the 3rd barrier Any TWO of the following conditions exist and the third is ready to take place (imminent):
- 1.
Fuel clad rupture as indicated by confirmed primary coolant sample results indicating
>300 ItCi/gm DOSE EQUIVALENT 1-131
- 2.
A rupture of the RCS has been confirmed with the leak rate >50 gpm.
(Makeup tank level decreasing at a rate greater than 2 inches per minute)
- 3.
Containment integrity has been breached and cannot be restored. Refer to T.S.
3.6.1.3 and T.S. 3.6.3.1.
General Emergency RA-EP-01900 All Modes See Also:
Abnormal RCS Leak Rate (2-A-I thru 4)
Major Steam Leak (5-A-I thru 3)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
17 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- l. PRIMARY SYSTEM EVENTS D. ABNORMAL CONTAINMENT ATMOSPHERE Emergency Cl ncc;frnntan nnnrl;t;nn
%tVIJU I ull114 tUJJEI
- 1.
Abnormal containment radiation and temperature Both of the following:
- 1.
Containment radiation level corresponds to an Alert as determined from the Containment Radiation EAL Plot on pages 18 or 19 AND
- 2.
Containment average air temperature indicates
>170'F Cr11356, 1357, 1358)
Alert RA-EP-01700 All Modes
- 2. High containment radiation pressure and temperature
- 1.
Containment radiation levels correspond to a Site Area Emergency as determined from the Containment Radiation EAL Plot on pages 18 or 19 AND
- 2.
A. Containment average air temperature indicates
>2000F (TI1356, 1357, 1358)
OR B. Safety Features Actuation System (SFAS) level 2 has activated Site Area Emergency RA-EP-01800 All Modes See Also:
Abnormal RCS Leak Rate (2-A-1 thru 4)
Loss of Fission Product Barriers (1-C-1)
Core Fuel Damage (1-B-1 thru 5)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
18 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 1. PRIMARY SYSTEM EVENTS D. ABNORMAL CONTAINMENT ATMOSPHERE (Cont.)
Emergency rinecssir-itian Tnrficatinnfec
\\_UI~~~~tlUII~~~
II~b~§J\\>\\zOI EI
- 3.
Very high containment radiation and pressure
- 1.
Containment radiation level correlates to a General Emergency as determined from the Containment Radiation EAL Plot on pages 18 or 19 AND
- 2.
SFAS level 4 actuation (Containment high-high pressure)
General Emergency RA-EP-01900 All Modes See Also:
Abnormal RCS Leak Rate (2-A-1 thru 4)
Loss of Fission Product Barrier (1-C-1)
Core Fuel Damage (1-B-i thru 5)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
19 RA-EP-0 1500 Revision 02 CONTAINMENT RADIATION EAL PLOT C
0 n
a n
m eM 11 t
R a
d i
a i
0 5xlO I
2 5xl0441 5x10 I
31 1x10 I
21 5x10 I
EMERGENCY ACTION LEVELS I
I I
I l
BASED ON CONTAINMENT II I
I RADIATION LEVELS
\\l I
I I
I I
_ I I
I. _
I I
I I
I I t GENERAL EMERGENCf I
l l
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I
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I I
I I
\\I I
I I
I I
I
\\ l i
I I
I I
I I
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I lSITE AREA EIERGENCYI I
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I I
I I
I I
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e I
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lx10 I
I I
I II
_ I I_
III I
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_ I I_
I
_ I II I
I-I I
ALERTI I
I I (loss of coolant) I I
J (5% gap release)
I
!1.
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5x10I hr)
III I
I I__
_I_
I I
I I
I I
I I
I I
I _ _
I I
I I
r A L TIME 5hr 10hr 15hr 20hr Z.5hr
.3unL CONTAINMENT RADIATION EAL PLOT INSTRUCTIONS The curves represent readings for monitors RE 4596A or B, Containment High Range Radiation Detector.
The procedure for their use is as follows:
- 1.
Determine the time after reactor shutdown
- 2.
Determine the RE 4596 Channel A or B radiation reading
- 3.
Find the point on the figure where these two numbers intersect
- 4.
Read the classification level of the line immediately below this point. This is the classification to use in correlation to the "Abnormal Containment Atmosphere" section of the Emergency Action Levels.
20 RA-EP- 01500 Revision 02 CONTAINMENT RADIATION EAL PLOT L00 N
300 0
b 1
200 e
G 100 3
S 77.5 n
55 C
0 n
32.5 t
a I
10 n
m e
7.8 n
t 5.5 (tici 3.3 1
I I I
I I
EMERGENCY ACTION LEVELS I
I I
I I
BASED ON CONTAINMENT lI I
I I
ATMOSPHERE
]
I I
I I
I I
I I
~
I l______
I GENERAL EHERGENCY I I
I I
1-(10% fuel melt)-j I
I I
I I
I I
I 1--
I
__-II ISITE AREA EMERGENCY I
I I
I I l (5OX gap release)]
I I
I I
I I
I I
I I
I I
I I
I \\
I l l
ALERT I
I I
I t t(loss of coolant)
I I
I _
l t5X gap release)
TIME 5hr lOhr 15hr 20hr 25hr 30hr CONTAINMENT RADIATION EAL PLOT INSTRUCTIONS The curves represent readings for monitors RE 4597AB or BB, Containment Atmosphere Radiation Detector. The procedure for their use is as follows:
- 1.
Determine the time after reactor shutdown
- 2.
Determine the RE 4597AB or BB Channel I or 2 radiation reading 3
Find the point on the figure where these two numbers intersect
- 4.
Read the classification level of the line immediately below this point. This is the classification to use in correlation to the "Abnormal Containment Atmosphere" section of the Emergency Action Levels.
21 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 2. REACTOR COOLANT SYSTEM LEAK RATE A. ABNORMAL RCS LEAK RATE Condition
- 1. Reactor Coolant System leak requiring shutdown per T.S. 3.4.6.2 (includes primary leakage, and primary to secondary leakage)
Indication(s)
>1 GPM unidentified leakage Emergency Classification Unusual Event RA-EP-0 1600 Modes 1, 2, 3,&4 OR C. Primary to Secondary leakage through the tubes of any one steam generator > 150 GPD OR D. RCS inventory balance indicates
>10 GPM identified leakage OR E. Controlled leakage from Reactor Coolant Pump seals is > 10 GPM total OR F. Leakage from any RCS pressure isolation valve listed in T.S. Table 3.4-2 >5 GPM AND
- 2. Plant shutdown required and in progress See Also:
Major Steam Leak (5-A-i through 3)
Loss of Fission Product Barriers (1-C-1)
Abnormal Radiation Levels at Site Boundary (6-D-1 through 7)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
22 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 2. REACTOR COOLANT SYSTEM LEAK RATE A. ABNORMAL RCS LEAK RATE (Cont.)
Emergency Classification Cr;ndtion Tndicationn(s)
- 2.
Reactor Coolant System leak rate >50 gpm, but within High Pressure Injection capacity (includes primary leakage, and primary to secondary leakage)
- 1.
Makeup tank level decreasing at a rate greater than 2 inches per minute, while RCS temperature remains steady Alert RA-EP-01700 All Modes OR 2.
RCS inventory balance indicates >50 gpm total leakage
- 3. Reactor Coolant System leak rate >50 gpm, but within High Pressure Injection Capacity (includes primary leakage, and primary to secondary leakage) AND loss of offsite power
- 1.
A. Makeup tank level decreasing at a rate greater than 2 inches per minute, while RCS temperature remains steady OR B. RCS inventory balance indicates >50 gpm total leakage Site Area Emergency RA-EP-01800 All Modes AND
- 2.
The 13.8 KV busses are de-energized See Also:
Loss of Fission Product Barrier (1-C-1)
Electrical Failures (4-A-1 thru 5)
Safety/Relief Valve Failure (1-A-1)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
23 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 2. REACTOR COOLANT SYSTEM LEAK RATE A. ABNORMAL RCS LEAK RATE (Cont.)
Emergency ClI azssifirn ti on Conldition Indicantinn(r)
- 4. Loss of Coolant Accident > High Pressure Injection system capacity
- 1.
High Pressure Injection system running AND
- 2.
A. RCS pressure/pressurizer level continue to decrease OR B. RCS temperature/
pressure reach saturation conditions Site Area Emergency RA-EP-01800 All Modes See Also:
Loss of Fission Product Barrier (1-C-1)
Electrical Failures (4-A-i thru 5)
Failure of a Primary Relief Valve (I-A-i)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
24 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
-II
]
a a!!
j"
LI i 1
- 1. An uncontrolled control rod withdrawal from a subcritical reactor
- 1.
Outward control rod motion is indicated without a command for such motion AND
- 2.
The reactor is initially subcritical Unusual Event RA-EP-01600 Modes 2, 3, 4, 5
- 2. Failure of Reactor
- 1.
Any time plant parameters Alert Protection System (RPS) meet conditions requiring RA-EP-01700 to initiate and complete a trip Modes 1 & 2 a trip which brings the AND reactor subcritical.
- 2.
RPS fails to initiate and complete a trip (either automatic or manual) which brings the reactor subcritical
- 3. Transient requiring
- 1.
Any time plant parameters Site Area operation of shutdown meet conditions requiring Emergency systems with failure to a trip RA-EP-01800 trip the reactor AND Modes 1 & 2 (continued power
- 2.
RPS fails to initiate and generation but no core complete a trip (either automatic damage immediately or manual) which brings the evident).
reactor subcritical AND
- 3.
Power interruption from the Control Room fails to bring the reactor subcritical.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
25 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
{r n
1 i
Ai
".
. -1.
Y
- 1. Complete loss of any functions needed for plant cold shutdown Loss of the Low Pressure Injection/Decay Heat System (BOTH TRAINS)
Alert RA-EP-01700 Modes 1, 2, 3 & 4
- 2. Inability to maintain plant in cold shutdown
- 1.
Loss of any cooling system function needed to maintain cold shutdown (Decay Heat, Component Cooling Water, Service Water) (BOTH TRAINS).
AND
- 2.
- a. An operational mode change due to temperature increase.
- b. A 30'F rise in RCS temperature.
- c.
Core cooling by feed and bleed has been initiated.
Alert RA-EP-01700 Modes 5 & 6 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
26 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
Emergency
'inc Cfir tinn trn dIti
- 3.
Complete loss of any function needed for plant hot shutdown Loss of any of the following systems:
- 1.
Service Water System (BOTH TRAINS)
Site Area Emergency RA-EP-01800 Modes 1,2,3 & 4 OR 2.
OR 3.
OR 4.
Component Cooling Water (BOTH TRAINS)
A. Makeup System AND B. High Pressure Injection System (BOTH TRAINS)
A. Main Feedwater System AND B. Auxiliary Feedwater System AND C. Motor Driven Feed Pump
- 4. Loss of water level in the reactor vessel that has or will uncover fuel in the reactor vessel
- 1.
Loss of any cooling system function needed to maintain cold shutdown (Decay Heat, Component Cooling Water, Service Water) (BOTH TRAINS).
AND
- 2.
Indication that the core is uncovered (e.g. incores indicate superheat, containment radiation levels increasing, source range detectors increasing, etc.).
Site Area Emergency RA-EP-01800 Modes 5 & 6 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
I --
27 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 3. SAFETY SYSTEM FUNCTIONS C. LOSS OF CONTROL ROOM ALARMS, INDICATION. OR COMMUNICATIONS Emergency r'Inccifie-ntirmn Pr'--Ai;r.-
%-Vilulti"11 I
- 1. Communication capability lost to an extent requiring plant shutdown or other significant loss of assessment Complete loss of the plant telephone system AND Gai-tronics system Unusual Event RA-EP-01600 All Modes
- 2. Most or all alarms Any simultaneous loss Alert (annunciators) lost of all annunciator RA-EP-01700 alarms AND the station Modes 1 & 2 computer
- 3.
Most or all alarms
- 1.
Complete loss of all Site Area (annunciators) lost annunciator alarms Emergency and plant transient AND RA-EP-01800 initiated or in
- 2.
Loss of the station Modes I & 2 progress computer AND
- 3.
Plant transient in progress NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
28 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 4. ELECTRICAL FAILURES A. AC Emergency
('PncCifirntinnf.
Tn A i-ntin-n(c
- 1. Loss of offsite power or loss of onsite AC power capability
- 1.
Loss of power to A and B busses from the following transformers:
A. Startup 01 AND B. Startup 02 AND C.
Aux 11 Unusual Event RA-EP-01600 All Modes OR 2.
OR 3.
A. Loss of power to C-l AND D-1 busses from AC AND BD transformers.
AND B. Onsite power capability has been degraded to either 4160 VAC vital bus C-1 or D-1 powered from a diesel generator.
Loss of all diesel generators.
- 2. AC power capability to
- 1.
Loss of power to Alert vital busses reduced to C-1 AND D-1 busses from RA-EP-01900 a single power source for AC AND BD transformers for Modes 1,2,3 & 4 greater than 15 minutes greater than 15 minutes.
such that any additional AND single failure would
- 2.
Onsite power capability result in a station has been degraded to either blackout.
4160 VAC vital bus C-1 or D-1 powered from a diesel generator.
NOTE Diesel generator includes the Emergency Diesel Generators and Station Blackout Diesel Generator.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
29 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 4. ELECTRICAL FAILURES A. AC (Continued)
Emergency Clasification Cannrltian Tntlintirn(c)
- 3. Loss of offsite power and loss of all onsite AC power 4160 VAC vital busses C-I AND D-1 de-energized longer than momentarily during transfers (see below for extended loss)
Alert RA-EP-01700 All Modes
- 4. Loss of offsite power 4160 VAC vital busses Site Area and loss of onsite AC C-I AND D-1 de-energized Emergency power for more than 15 more than 15 minutes RA-EP-01800 minutes All Modes
- 5. Prolonged loss of all
- 1.
Loss of power to A and B General Emergency offsite power and busses from the following RA-EP-01900 prolonged loss of all transformers:
Modes 1,2,3 & 4 onsite AC power.
A. Startup 01 AND B. Startup 02 AND C. Aux 11 AND
- 2.
4160 VAC vital busses C-I AND Dl are de-energized for more than 15 minutes.
AND
- 3.
A. Restoration of at least one vital bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOT likely.
OR B. Indication of continuing degradation of core cooling based on fission product barrier monitoring.
See Also: Abnormal RCS Leak Rate With a Loss of Offsite Power (2-A-3).
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
30 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 4. ELECTRICAL FAILURES B. DC Emergency Condition Indication(s)
Classification
Alert RA-EP-01700 All Modes
- 2. Loss of all vital onsite All in plant DC busses Site Area DC power for more than de-energized for more than Emergency 15 minutes 15 minutes RA-EP-01800 All Modes NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
31 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 5. SECONDARY SYSTEM EVENTS A. MAJOR STEAM LEAK Emergency Condition Indication(s)
Classification
- 1. Rapid depressurization of secondary side
- 1.
A. Increasing containment pressure (if leak is inside containment)
Unusual Event RA-EP-01600 Modes 1,2,3 &4 OR B. Unusually loud noise OR C. Visual sighting outside containment AND
- 2.
Valid Steam and Feedwater Rupture Control System (SFRCS) automatic initiation on low main steam line pressure
- 2.
Steam line break with
>10 gpm primary to secondary leak rate
- 1.
Indication of a major steam leak (see 5.A. 1)
AND
- 2.
Main steam line radiation monitor(s) indicate in-creased activity (RE 600/609)
AND
- 3.
RCS leak rate >10 gpm as indicated by:
A. Makeup tank decreasing
>1/2 inch per minute OR B. RCS inventory balance indicates >10 gpm leak rate OR C. DB-CH-01814, Steam Generator Leak Determination Alert RA-EP-01700 Modes 1,2,3&4 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
32 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 5. SECONDARY SYSTEM EVENTS A. MAJOR STEAM LEAK (Cont.)
Emergency T-Ali-t-nn(c%
bUIIU~~~~~tlUII~~~
Ii~bllIt}tfibll~i
- 3.
Steam line break with
>50 gpm primary to secondary leakage AND indication of fuel damage
- 1.
Indication of a major steam leak (see 5.A.1)
AND
- 2.
Main steam line radiation Monitor(s) indicate increased activity (RE 6001 609)
AND
- 3.
RCS leak rate >50 gpm as indicated by:
A. Makeup tank decreasing
>2 inches per minute OR B. RCS inventory balance indicates >50 gpm leak rate AND
- 4.
Confirmed primary coolant sample results indicate activity above acceptable limits of T.S. 3.4.8 Site Area Emergency RA-EP-01800 Modes 1, 2,3 &4 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
33 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 5. SECONDARY SYSTEM EVENTS B. MAIN STEAM SAFETY VALVE FAILURE Emergency Condition Indication(s)
Classification
- 1. Failure of safety
- 1.
Rapid and continuing Unusual Event related safety valves, decrease in steam generator RA-EP-01600 or relief valves, to pressure to <500 psig Modes 1,2,3 & 4 close following a pressure reduction AND
- 2.
Visual or audible observation of a safety valve being open See Also Major Steam Leak (5-A-1 through 5-A-3)
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
34 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 6. RADIATION RELEASE EVENTS A. HIGH RADIATION LEVELS WITHIN THE PROTECTED AREA Emergency (1,
eifra-tinn vo--A:#;-r 4-UH1UILIVII IIJUIj,. t,,aV M a
- 1. Radiation levels or airborne contamination which indicates a severe degradation in the control of radioactive materials (such as an increase of a factor of 1000 in direct radiation readings)
A. An area radiation survey indicates radiation levels
>1000 times normal OR B. Airborne radioactivity sample indicates activity levels >1000 times normal OR C. If an area of the plant is inaccessable, a radiation monitor reading indicating radiation levels >1000 times normal Alert RA-EP-01700 All Modes NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
35 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 6. RADIATION RELEASE EVENTS B. FUEL HANDLING ACCIDENT Emergency Condition Indication(s)
Classification
- 1. Fuel handling accident Direct information from Alert which results in the fuel handling personnel RA-EP-01700 release of radioactivity indicating that an irradiated All Modes to containment or fuel fuel assembly has been handling area damaged and radioactive gases are escaping
- 2. Major damage to spent
- 1.
Indications of fuel handling Site Area fuel in containment or accident which results in Emergency fuel handling area the release of radioactivity RA-EP-01800 (e.g., large object to containment or spent fuel All Modes damages fuel or water pool area loss below fuel level)
AND
- 2.
A. SFAS Incident Level 1 actuation on radiation in Containment.
OR B. Valid alarm on a radiation detector monitoring spent fuel in Containment or the fuel handling area.
OR C. Isolation of ventilation in containment or spent fuel pool area based on radiation.
NOTE The USAR analyzed fuel handling accident (Chapter 15) postulates the failure of 56 fuel pins from an assembly at maximum burnup, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reactor shutdown.
Fuel repair activities involving the handling of an individual fuel pin are covered under the maintenance exception of Section 6.1.1.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
I
36 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 6. RADIATION RELEASE EVENTS C. ABNORMAL EFFLUENT RELEASE Emergency 0-14iti-T-Ali-tin-(cN bUII~tIII llulati~l\\:l
_4:I!i~llD~\\JI
- 1. Effluent release >
limits allowed by the Offsite Dose Calculation Manual (ODCM):
ODCM Section 2.3.1 ODCM Section 2.4.1 ODCM Section 3.3.1 ODCM Section 3.7.1 ODCM Section 3.8.1 The following combination:
- 1.
Any confirmed effluent release exceeding the limits of the ODCM.
Unusual Event RA-EP-01600 All Modes OR 2.
A high alarm is received on any of the following Radiation Monitoring System monitors for greater than 15 minutes during a release (alarm setpoint established by the Chemistry Department)
A. 1878A or B, Miscellaneous Waste Outlet OR B. 1770A or B, Clean Waste Outlet OR C. 1822A or B, Waste Gas Outlet AND
- 3.
The associated discharge valve fails to close (automatically OR manually)
AND
- 4.
Chemistry/Radiation Protection Section confirms that an ODCM limit has been exceeded.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
37 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 6. RADIATION RELEASE EVENTS C. ABNORMAL EFFLUENT RELEASE (Cont.)
Emergency fl--A:.:--
L-1I U ILII ilUIUOLt Il l, OP
- 2. Effluent release >10 times limits allowed by the Offsite Dose Calculation Manual (ODCM):
ODCM Section 2.3.1 ODCM Section 2.4.1 ODCM Section 3.3.1 ODCM Section 3.7.1 ODCM Section 3.8.1 The following combination:
- 1.
Any confirmed effluent release exceeding the ODCM Limits by >10 times the limits Alert RA-EP-0 1700 All Modes OR 2.
A high alarm is received on any of the following Radiation Monitoring System monitors at 10 times setpoint (as established by the Chemistry Department)
A. 1878A or B, Miscellaneous Waste Outlet OR B. 1770A or B, Clean Waste Outlet OR C. 1822A or B, Waste Gas Outlet AND
- 3.
The associated discharge valve fails to close (automatically OR manually)
AND
- 4.
Chemistry/Radiation Protection Section confirms that an ODCM limit has been exceeded.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
I
38 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 6. RADIATION RELEASE EVENTS D. ABNORMAL RADIATION LEVELS AT SITE BOUNDARY NOTE 6.D 1 RE 4598 indication is based on average meteorological conditions: stability class D, wind speed 10 mph.
Emergency Condition Indication(s)
Classification
- 1. Projected or actual
- 1. Station Vent RE 4598 Alert site boundary radiation Channel 1 reading RA-EP-01700 levels that indicata a 2 3.6E-3 ici/cc All Modes potential dose of about (Noble Gas) for 1 mrem at the site 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> boundary if continued OR over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 2. 0.5 mrem/hr measured at the Site Boundary for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> NOTE 6 D.2 RE 4598 indications are based on adverse meteorological conditions: stability class F, wind speed 2 mph.
Emergency Condition Indication(s)
Classification
- 2. Projected or measured
- 1.
Station Vent RE 4598 Site Area site boundary Total Channel 1 (Noble Gas)
Emergency Effective Dose indicates 1.6E-2 gci/cc RA-EP-01800 Equivalent (TEDE) rate or greater for l/2 hour All Modes 2 50 mrem/hr for l/2 hour.
- 2.
50 mrem/hr by direct measurement at the site boundary for 1/2/2 hour NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
39 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 6. RADIATION RELEASE EVENTS D. ABNORMAL RADIATION LEVELS AT SITE BOUNDARY (Cont.)
NOTE 6.D.3. 6.D.4 and 6.D.5 RE 4598 indications are based on adverse meteorological conditions: stability class F, wind speed 2 mph.
- 3. Projected or measured
- 1.
Station Vent RE 4598 Site Area site boundary TEDE rate Channel 1 (Noble Gas)
Emergency
Ž 500 mrem/hr for indicates 1.6E-1 uci/cc RA-EP-01800 2 minutes or greater for 2 minutes All Modes OR
- 2.
500 mrem/hr by direct measurement at the site boundary for 2 minutes
- 4. Projected or measured
- 1.
Station Vent RE 4598 Site Area site boundary thyroid Channel 3 (Iodine)
Emergency dose rate 2 250 mrem/hr indicates 3.7E-6 pci/cc RA-EP-01800 for 1/2 hour or greater for 1/2 hour All Modes OR
- 2.
Radioiodine of 7.9E-8 pci/cc by direct measurement at the Site Boundary for Liz hour
- 5. Projected or measured
- 1.
Station Vent RE 4598 Site Area site boundary thyroid Channel 3 (Iodine)
Emergency dose rate 2 2500 mrem/hr indicates 3.7E-5 pci/cc RA-EP-01800 for 2 minutes or greater for 2 minutes All Modes OR
- 2.
Radioiodine of 7.8E-7 pci/cc by direct measurement at the Site Boundary for 2 minutes NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
40 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS RA-EP-01500 Revision 02
- 6. RADIATION RELEASE EVENTS D. ABNORMAL RADIATION LEVELS AT SITE BOUNDARY (Cont.)
NOTE 6.D.6 and 6.D 7 RE 4598 indications are based on adverse meteorological conditions: stability class D, wind speed 10 mph.
- 6. Projected or measured
- 1.
Station Vent RE 4598 General Emergency TEDE rate of 1 rem/hr Channel 1 (Noble Gas)
RA-EP-01900 or greater at the Site indicates 6.9E-1 pci/cc All Modes Boundary.
or greater.
- 2.
1 rem/hr by direct measurement at the Site Boundary.
- 7. Projected or measured
- 1.
Station Vent RE 4598 General Emergency thyroid dose rate of Channel 3 (Iodine)
RA-EP-01900 5 rem/hr or greater indicates 1.8E-3 pci/cc All Modes at the Site Boundary or greater.
- 2.
Radioiodine of 1.7E-6 pci/cc by direct measurement at the Site Boundary.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
I
41 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS A. FIRE Emergency Condition Indication(s)
Classification
- 1. Fire within the plant lasting
- 1.
Any fire within the protected Unusual Event lasting more than 10 minutes area lasting more than RA-EP-01600 10 minutes from the initiation All Modes of fire suppression (manually OR automatically), NO safety systems affected OR
- 2.
Any fire which requires offsite assistance
- 2. Fire potentially Any fire at the station that has Alert affecting safety the potential to damage or RA-EP-01700 systems degrade a safety system All Modes
- 3. Fire resulting in the Any fire that defeats the Site Area loss of redundant capability of both trains Emergency trains of a safety of a safety system RA-EP-01800 system All Modes NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
42 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS B. AIRCRAFT CRASH Emergency Condition Indication(s)
Classification
- 1. Aircraft crash onsite Control room informed by Unusual Event or unusual aircraft station personnel who have RA-EP-01600 activity over facility made a visual sighting All Modes
- 2. Aircraft crash, affecting Control room informed by Alert plant structures station personnel who have RA-EP-01700 made a visual sighting All Modes
- 3.
Aircraft crash damaging
- 1.
Control room informed by Site Area vital structures by station personnel who have Emergency impact or fire.
made a visual sighting RA-EP-01800 AND Modes 1,2,3&4
- 2.
Instrumentation readings on vital systems indicate equipment problems NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
43 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS C. TRAIN DERAILMENT Emergency r'l -c rc --fir *;
Tnrlirnt;rgnRcE 1JJU1at1V1Jt.,)Y
%-1aa3111V-aL1V11
- 1. Train derailment onsite
- 1.
Control room informed by station personnel who have made a visual sighting AND
- 2.
A. Station structures have been damaged OR B. Danger to station personnel exists Unusual Event RA-EP-01600 All Modes NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
44 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS D. EXPLOSION Emergency Cls sificatinn CAnditinn Tndica-tinn(-z1
- 1. Near or onsite explosion Control room informed by station personnel who have made a visual sighting Unusual Event RA-EP-01600 All Modes
- 2. Onsite explosion affecting
- 1.
Control room informed by Alert plant operations station personnel who have RA-EP-01700 made a visual sighting All Modes AND
- 2.
Instrumentation readings on plant systems indicate equipment problems
- 3. Explosion causing Explosion causing loss of:
Site Area severe damage to safe
- 1.
Makeup system AND HPI Emergency shutdown equipment system RA-EP-01800 OR Modes 1,2,3&4
- 2.
Ability to supply feedwater to the OTSG's NOTE RA-EP-02840, Explosion, contains further detailed information.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
45 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS E. TOXIC OR FLAMMABLE GAS Emergency
('I0 ifl-t-(^n-A1 ti -n
- 1. -1.
,
- 1. Near or onsite toxic or flammable gas release
- 1.
Report or detection of toxic or flammable gases that could enter within the Owner Controlled Area in amounts that can affect normal operation of the plant.
Unusual Event RA-EP-01600 All Modes OR 2.
Report by local, county or State officials for potential evacuation of Owner Controlled Area personnel based on offsite events.
- 2. Entry into facility environs of uncontrolled toxic or flammable gas
- 1.
Report or detection of toxic or flammable gas within a Protected Area structure in concentrations that will be threatening to plant personnel.
Alert RA-EP-01700 All Modes OR 2.
Report or detection of toxic or flammable gases within a Protected Area structure in concentrations that will affect the safe operation of the plant.
NOTE RA-EP-02850, Hazardous Chemical and Oil Spills, contains further information.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
46 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS E. TOXIC OR FLAMMABLE GAS (Continued)
Emergency Condition Indication(s)
Classification
- 3.
Entry of uncontrolled
- 1.
Report or detection of Site Area flammable gases into toxic or flammable gases Emergency vital areas. Entry of within Vital Areas where RA-EP-01800 uncontrolled toxic gases lack of access to the area Modes 1,2,3&4 into vital areas where prevents operation of BOTH lack of access to the TRAINS of a safety system.
area constitutes a safety problem. (Plant not in cold shutdown.)
NOTE RA-EP-02850, Hazardous Chemical and Oil Spills, contains further detailed information.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
47 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS F. TURBINE DAMAGE Emergency Condition Indication(s)
Classification
- 1. Turbine rotating
- 1.
High turbine vibration trip Unusual Event component failure causing AND RA-EP-01600 rapid plant shutdown
- 2.
Reactor trip Modes 1 & 2
- 2. Turbine failure causing Control room informed by Alert casing penetration Station personnel who have RA-EP-01700 made a visual inspection Modes 1 & 2 of turbine casing NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
48 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS G. MISSILE IMPACT Emergency Condition Indication(s)
Classification
- 1. Missile impact from Control room informed by Alert whatever source on Station personnel of any RA-EP-01700 the facility missile All Modes
- 2. Missile impact causing
- 1.
Control Room informed by Site Area severe damage to safe Station personnel of any Emergency shutdown equipment missile impact on safe RA-EP-01800 shutdown equipment Modes 1,2,3&4 AND
- 2.
Instrumentation readings on safe shutdown equipment indicate equipment problems NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
49 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS H. CONTROL ROOM EVACUATION Emergency Condition Indication(s)
Classification
- 1. Evacuation of control Any evacuation of the Alert room anticipated control room anticipated RA-EP-01700 or required or required with control of All Modes shutdown systems established from local stations within 15 minutes
- 2. Evacuation of control Any evacuation of the Site Area room and control of control room with shutdown Emergency shutdown systems NOT control NOT established RA-EP-01800 established from local locally within 15 minutes All Modes stations in 15 minutes NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
I-----------------------------------------------------------------------------------------------.........................
50 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 7. HAZARDS TO STATION OPERATIONS I. SECURITY THREAT rnn he ; t; nn Tn rnctinn(c)
- 1. Security threat or attempted entry or attempted sabotage
- 1.
Report by plant personnel of a security threat with a potential for industrial sabotage (i.e. attempted forcible entry into a vital area, armed entry into the protected area, discovery of suspected bombs or incendiary devices, etc.)
Emergency Classification Unusual Event RA-EP-0 1600 All Modes OR 2.
- 2. Ongoing security compromise 1.
Site Specific Credible Threat Report by a member of the security force that a security emer-gency is in progress Alert RA-EP-01700 All Modes I
OR 2.
OR Protected Area Intrusion
- 3.
Protected Area Credible Threat of Imminent Attack
- 3. Loss of physical control Physical attack on the Site Area of the plant is ready to plant involving imminent Emergency take place (imminent) occupancy of the Control RA-EP-01800 Room OR local shutdown All Modes stations that control vital equipment
- 4. Loss of physical control of the facility
- 1.
Physical attack on the plant which has resulted in occupation of the control room OR
- 2.
Unauthorized personnel in control of vital plant equipment General Emergency RA-EP-01900 All Modes NOTE DB-OP-02544, Security Events contain further detailed information.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
51 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 8. NATURAL EVENTS (WITHIN OTTAWA COUNTY)
A. EARTHQUAKE Emergency Condition Indication(s)
Classification
- 1. Any earthquake felt in-plant Any earthquake felt in-plant Unusual Event or detected on station seismic OR detected by station seismic RA-EP-01600 instrumentation instrumentation All Modes
- 2. Earthquake > Operating
- 1.
Ground motion felt Alert Basis Earthquake (OBE)
AND RA-EP-01700 levels
- 2.
OBE alarm on seismic All Modes alarm panel C5764A
- 3. Earthquake >Safe
- 1.
Ground motion felt Site Area Shutdown Earthquake AND Emergency (SSE) levels 2
SSE alarm on seismic RA-EP-01800 alarm panel C5764A Modes 1,2,3&4 NOTE RA-EP-02820, Earthquake, contains further detailed information.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
52 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 8. NATURAL EVENTS (WITHIN OTTAWA COUNTY)
B. TORNADO Emergency Condition Indication(s)
Classification
- 1. Any tornado onsite Control room informed by Unusual Event station personnel who have RA-EP-01600 made a visual sighting of a All Modes tornado crossing the site boundary
- 2. Any tornado striking Control room informed by Alert facility station personnel who have RA-EP-01700 made a visual sighting of a All Modes tornado striking the facility NOTE RA-EP-028 10, Tornado, contains further detailed information.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
53 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS RA-EP-01500 Revision 02
- 8. NATURAL EVENTS (WITHIN OTTAWA COUNTY)
C. HURRICANE FORCE WINDS Emergency Condition Indication(s)
Classification
- 1. Hurricane force Control room informed Unusual Event winds (greater of hurricane force winds RA-EP-01600 than 74 mph) forecast for Ottawa All Modes County
- 2. Hurricane force winds
- 1.
Control Room informed Alert near design basis of hurricane force winds RA-EP-01700 levels (greater than occurring in Ottawa County All Modes 74 mph, but less than AND 90 mph)
- 2.
Two successive 15 minute averages from the station meteorological tower are of winds of 74 mph to 90 mph
- 3. Hurricane force winds
- 1.
Control room informed Site Area
> design basis levels of hurricane force winds Emergency (greater than 90 mph) occurring in Ottawa County RA-EP-01800 AND Modes 1,2,3&4
- 2.
Two successive 15 minute averages from the station meteorological tower are of winds above 90 mph NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
I
54 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS RA-EP-01500 Revision 02 8 NATURAL EVENTS (WITHIN OTTAWA COUNTY)
D. FLOODING. LOW WATER Emergency Condition Indication(s)
Classification
- 1. 50 year flood or low Forebay level observed to be:
Unusual Event water, surge or seiche
- 1.
High (>580 feet IGLD)
RA-EP-01600 OR All Modes
- 2.
Low (<562 feet IGLD)
- 2. Flood, low water, surge Forebay level observed to be:
Alert or seiche near design
- 1.
High (584 feet IGLD)
RA-EP-01700 levels OR All Modes
- 2.
Low (<560 feet IGLD)
- 3. Flood, low water, surge Forebay level observed to be:
Site Area or seiche > design
- 1.
High (>584 feet IGLD)
Emergency levels with plant not OR RA-EP-01800 in cold shutdown
- 2.
Low (<558 feet IGLD)
Modes 1,2,3,&4 NOTE RA-EP-02830, Flooding, contains further detailed information on high water situations.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
55 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 9. MISCELLANEOUS Emergency Condition Indication(s)
Classification
- 1. Inability to reach Plant is NOT brought to Unusual Event required shutdown a required operating RA-EP-01600 within technical mode within a Technical Modes 1,2,3,&4 specification limits.
Specification Limiting Condition for Operation (LCO) Action Statement Time.
- 2. Miscellaneous Other plant conditions exist Unusual Event that warrant increased RA-EP-01600 awareness on the part of the All Modes plant operations staff or State and/or local offsite authorities which are not covered under any other existing station procedures.
- 3. Miscellaneous Other plant conditions exist Alert that warrant precautionary RA-EP-01700 activation of the Technical All Modes Support Center and Emergency Control Center and placing other key emergency personnel on standby.
- 4. Miscellaneous Other plant conditions exist Site Area that warrant activation of Emergency emergency centers and RA-EP-01800 monitoring teams or a All Modes precautionary notification to the public near the site.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
56 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 9. MISCELLANEOUS (Cont.)
Emergency Condition Indication(s)
Classification
- 5. Miscellaneous Other plant conditions exist, General Emergency from whatever source, that RA-EP-01900 make release of large amounts All Modes of radioactivity in a short time period possible, e.g.,
any core melt situation.
NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
57 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 10. DOWNGRADING GUIDELINES A.
Existing conditions no longer meet the emergency criteria AND it appears unlikely that conditions will deteriorate further.
B.
Nonroutine releases of radioactive material to the environment are under control or terminated C.
Any fire, flood, earthquake, or similar emergency conditions are controlled or have ceased.
D All specified corrective actions have occurred OR the plant has been placed in the appropriate operational mode.
E.
All required notifications have been completed.
F.
Agreement between the Control Room, Technical Support Center and the Emergency Control Center/Emergency Operations Facility that downgrading is appropriate (if they were activated).
G.
After issuance of offsite protective actions has occurred, State and County officials must concur with the downgrading.
58 RA-EP-01500 Revision 02 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS
- 11. TERMINATING GUIDELINES A.
The conditions which caused the emergency have stabilized, are under control, and are unlikely to deteriorate further.
B.
No surveillance relative to offsite protective actions is needed, except for the control of foodstuffs, water, and offsite contamination, or environmental assessment activities.
C.
Radiation levels in affected plant areas are acceptable, and/or are stable or decreasing.
D.
Releases of radioactive material to the environment greater than Offsite Dose Calculation Manual are under control or have ceased.
E.
The potential for an uncontrolled release of radioactive material is at an acceptable, low level.
F.
Containment pressure is within Technical Specification requirements related to the existing mode of operation G.
The reactor is in a stable, safe shutdown condition and long-term core cooling is available, as required.
H.
Any fire, flood, earthquake, or similar emergency conditions no longer exist.
I.
All offsite notifications are complete.
J.
Offsite conditions will not limit access of personnel and resources.
K.
Discussions have been held with those federal, state and local organizations that have mobilized in support of the emergency, and that are in direct communication with DBNPS.
L.
The Technical Support Center (TSC) staff, if activated, has evaluated plant status with respect to Technical Specifications and concurs with termination of the emergency.
59 RA-EP-01500 Revision 02 7.0 FINAL CONDITIONS Abnormal plant conditions have been terminated and an Emergency Director is no longer required.
8.0 RECORDS 8.1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106:
8.1.1 None 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management in accordance with NG-NA-00106:
8.2.1 None
60 RA-EP-01500 Revision 02 ATTACHMENT 1:
SUMMARY
OF EMERGENCY AMFON LEVELS
61 RA-EP-01500 Revision 02 COMMITMENTS Section Reference Comments Table of EALs, throughout Table of EALs, EAL 7-A-2 Table of EALs, EAL 3-C-3 Table of EALs, EAL 8-A-I Table of EALs, EAL 7-F-i Table of EALs, EAL 4-A-3 Caution 6.1. Le.
Table of EALs, EAL 2-A-2 Table of EALs, EAL 7-A-I Section 6..1.e.3.
Table of EALs, EAL 8-A-2 and 8-A-3 Table of EALs, throughout TERMS 0 05702 TERMS 0 13375 TERMS 0 13377 TERMS 0 13380 TERMS 0 13383 TERMS 0 13384 TERMS 0 13477 TERMS 0 13482 TERMS 0 13525 TERMS 0 13601 TERMS 0 13670 TERMS 0 13672 TERMS 0 14181 Reliable instrument readings where applicable Fire at alert level needing offsite assistance Deleted 15 minute time duration for loss of all annunciators at Site Area Emergency Unusual Event declared if earthquake is felt but not detected by monitors Add turbine failure Unusual Event Alert EAL for loss of onsite and offsite power Reviewed/revised EAL applicability mode of plant operation Clarify indications of
> 50 gpm RCS leak Make fire Unusual Event conform to NUREG 0654 Specifies conditions under which the Shift Manager (STA) may assume Emergency Director duties OBE and SSE Earthquakes Highlighting of AND and OR Table of EALs, EAL 1-B-i thru 1-B-5 TERMS 0 14855 Clarify fuel failure
62 RA-EP-01500 Revision 02 COMMITMENTS (Continued)
Section Reference Comments Table of EALs, EAL 3-A-3 Table of EALs throughout Table of EALs, EAL l-D-2 Table of EALs, EAL 1-C-i Section 3.2 Table of EALs, EAL 1-C-I TERMS 0 14974 TERMS 0 14986 TERMS 0 14988 TERMS 0 15157 TERMS 018734 TERMS Q 00052 Ensure ATWS conditions are correctly classified.
Cross reference to other EALs High containment radiation, pressure and temperature indicated by any SFAS function activated Clarify loss of fission product barriers Definition of a core melt Sequence EAL for loss of containment integrity Entire Procedure TERMS Q 03113 Procedure for Emergency Classification