Text

Transmittal of Emergency Plan Implementing Procedure, RA-EP-01500, Revision 3
	ML031990226
Person / Time
Site:	Davis Besse
Issue date:	07/10/2003
From:	; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML031990226 (66)
	v • d • e

Davis Besse Power Station Control Copy Number 1665 Transmittal / Receipt Acknowledgement Transmittal Number: 0307-32691 Transmittal Date: 07-10-2003 To: DOC. CONTROL DESK Mail Stop / Address: USNRC DIVISION 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 Outdated material shall either be removed and destroyed or marked to reflect that it is superseded or voided and is no longer considered controlled.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

Davis Besse Power Station Control Copy Number 1665 Transmittal / Receipt Acknowledgement Transmittal Number: 0307-32691 Transmittal Date: 07-10-2003 I ,

, .., f, t Type Number Sht/Sec Changes Rev Status TOC I TOC 2 RA-EP-01500 0002 APPROVED old EPIA EPOC PROC 0003 APPROVED new EPIA EPOC PROC RA-EP-01500

Page 1 of 62 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE RA-EP-01500 EMERGENCY CLASSIFICATION REVISION 03 Prepared by: B. W. Cope Procedure Owner: Director - Organizational Development Effective Date: JUL I 0 a203 Procedure Classification:

LEVEL OF USE:

X Safety Related IN-FIELD REFERENCE Quality Related Non-Quality Related

2 RA-EP-01500 Revision 03 TABLE OF CONTENTS Page 1.0 PURPOSE .. 3

2.0 REFERENCES

.3 3.0 DEFINITIONS .4 4.0 RESPONSBILITIES .5 5.0 INITIATING CONDITIONS .5 6.0 PROCEDURE .6 6.1 Classification of Emergency .6 6.2 Downgrading Emergency Classification .8 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. Miscellaneous....................................................................................... 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 03 1.0 PURPOSE This procedure provides guidelines for conditions at which specific emergency classifications must be declared.

2.0 REFERENCES

2.1 Develonmental 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 1 to NUREG-0654/FEMA-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-01800, 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 03 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 03 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 RESPONSIBIL1TIES 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 03 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 6.1.1 .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 03

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.l1. Lf 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-O1900, 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 03

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 offsihe 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. .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-02710, Reentry.

9 RA-EP-01500 Revision 03 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-02710, 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 03 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, HPI, 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 03 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-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDiTIONS

1. PRIMARY SYSTEM EVENTS A. FAILURE OF A PRIMARY RELIEF VALVE Emergency d--Aitirs tAJUjUl~tJui Tn-A-d-finn njJKtuI001....ao~

% nULAWJn

1. Failure of safety 1. Indication of flow through Unusual Event related safety valve, Pressurizer Reliefs (as RA-EP-01600 or relief valve, to indicated on Panel C5798, All Modes close following a C5799 and C5705) pressure reduction AND

2. RCS Pressure drop to

<1600 psig See Also: Abnormal RCS Leak Rate (2-A-I 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

1. PRIMARY SYSTEM EVENTS B. CORE FUEL DAMAGE Emergency Conndition Indicrtinn(s) Classificatinn

1. High reactor coolant I. Confirmed primary coolant Unusual Event activity sample requiring activity sample results RA-EP-01600 plant shutdown per indicate > T.S. 3.4.8 Modes 1 & 2 T.S. 3.4.8 AND

2. Plant shutdown required and in progress

2. Very high coolant activity Confirmed primary coolant Alert sample results indicate >300 ' RA-EP-01700 ItCi/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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

1. PRIMARY SYSTEM EVENTS B. CORE FUEL DAMAGE (Cont.)

Emergency nnntl;tionS..AJS~ti~tflt~flSJZ~tL&L~ctfl- - ....... fl0 A~Ut,

3. Core damage with in- 1. Confirmed primary coolant Site Area adequate core cooling sample results indicate: Emergency determined A. DOSE EQUIVALENT I-131 RA-EP-01800

>T.S. 3.4.8 All Modes OR B. 100 / E pCi/gram specific activity, AND

2. The incore thermocouples indicate superheated con-ditions in the core

4. Core damage with other 1. Confirmed primary coolant General Emergency plant conditions making sample results indicate RA-EP-01900 a release of large >300 ,Ci/gram DOSE All Modes amounts of radioactivity EQUIVALENT I-131 possible AND

2. Incore thermocouple temperatures correspond to region 3 or 4 of DB-OP-02000 Figure 2 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 (1-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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

1. PRIMARY SYSTEM EVENTS B. CORE FUEL DAMAGE (Cont.)

Emergency Condition Indication(s) Classification

5. Core melt situations 1. Any sequence of events General Emergency has occurred in which RA-EP-01900 severe core damage (such All Modes as core melting) has taken place AND

2. A failure of containment is ready to take place (imminent)

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 (I-C-l)

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 03 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 Any TWO of the following General Emergency product barriers with a conditions exist and the RA-EP-01900 potential loss of the third is ready to take place All Modes 3rd barrier (imminent):

1. Fuel clad rupture as indicated by confirmed primary coolant sample results indicating

>300 ,Ci/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.

See Also: Abnormal RCS Leak Rate (2-A-1 thru 4)

Major Steam Leak (5-A-1 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

1. PRIMARY SYSTEM EVENTS D. ABNORMAL CONTAINMENT ATMOSPHERE Emergency tnnflifirsn MIUI%,aLIWIJq 0 1 I-IMODALM.LIM11

1. Abnormal containment Both of the following: Alert radiation and 1. Containment radiation RA-EP-01700 temperature level corresponds to an All Modes Alert as determined from the Containment Radiation EAL Plot on pages 19 or 20 AND

2. Containment average air temperature indicates

>1700 F C11356, 1357, 1358)

2. High containment radiation 1. Containment radiation Site Area pressure and temperature levels correspond to a Emergency Site Area Emergency as RA-EP-01800 determined from the All Modes Containment Radiation EAL Plot on pages 19 or 20 I AND

2. A. Containment average air temperature indicates

>2000 F (T11356, 1357, 1358)

OR B. Safety Features Actuation System (SFAS) level 2 has activated See Also: Abnormal RCS Leak Rate (2-A-1 thru 4)

Loss of Fission Product Barriers (1-C-i)

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.

18 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

1. PRIMARY SYSTEM EVENTS D. ABNORMAL CONTAINMENT ATMOSPHERE (Cont.)

Emergency tnnAlitin .1 Vt.-U.sifirsi

3. Very high containment 1. Containment radiation level General Emergency radiation and pressure correlates to a General RA-EP-01900 Emergency as determined All Modes from the Containment Radiation EAL Plot on pages 19 or 20 I AND

2. SFAS level 4 actuation (Containment high-high pressure)

See Also: Abnormal RCS Leak Rate (2-A-1 thru 4)

Loss of Fission Product Barrier (1-C-i)

Core Fuel Damage (I-B-l thru 5)

NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed

19 RA-EP-01500 Revision 03 CONTAINMENT RADIATION EAL PLOT o 5x1O 4 n0 a 2.5xI04 n

m 1X1O~

n 3

, 5x10 R 3 a 2.5xl03 d

a 1X10 3 o 5x10 n

L 2.5xI02 ev e IXIQ 2 1

(RI 5xI10 1 hr)

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.

RA-EP-01500 20 Revision 03 CONTAINMENT RADIATION EAL PLOT 400 EMERGENCY ACTION LEVELS I I I I I I BASED ON CONTAINMENT ;

I jI lIf ATMOSPHERE N 300 a I\\ I I I I II b

1 200 e I I ~ - l t~lI EHERGENCY I GENERAL I

I I I OT I- (10tfuel melt)-;

G 100 a I I I I I : IA S

77. 5 i I I I I I I I i n II I I I I I i 55 C

0 n 32.5 t I I If I I I I a I1 1 _ _ I _ _ 1 _ _ I _ _ 1 . I

_ _ _ _ 1 1I. _ _ (5 0 X g a p r e l e a s e )

i 10 n

r e 7.8 n

t 5.5 (iiCi 1_ _ !. IA- IAL It IA I

~~~~~~(loss 3.3 ! I l \ l !

I ff I

I I of coolant)

I OX gap release) I 1

TIME 5hr l0hr 15hr Zuhr 25nr 3unr 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

2. REACTOR COOLANT SYSTEM LEAK RATE A. ABNORMAL RCS LEAK RATE Emergency Condition Indication(s) Classification

1. Reactor Coolant System leak 1. A. Any leakage occurs from the Unusual Event requiring shutdown per pressure boundary RA-EP-01600 T.S. 3.4.6.2 (includes OR Modes 1, 2, 3, & 4 primary leakage, and primary B. RCS inventory balance indicates to secondary leakage) >1 GPM unidentified leakage 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-i)

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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

2. REACTOR COOLANT SYSTEM LEAK RATE A. ABNORMAL RCS LEAK RATE (Cont.)

Emergency C'nnAtinn 1"ndicationfeN Clsific~ation

2. Reactor Coolant System 1. Makeup tank level Alert leak rate >50 gpm, but decreasing at a rate RA-EP-01700 within High Pressure greater than 2 inches All Modes Injection capacity per minute, while RCS (includes primary temperature remains leakage, and primary steady to secondary leakage) OR

2. RCS inventory balance indicates >50 gpm total leakage

3. Reactor Coolant System 1. A. Makeup tank level Site Area leak rate >50 gpm, but decreasing at a rate Emergency within High Pressure greater than 2 inches RA-EP-01800 Injection Capacity per minute, while RCS All Modes (includes primary leakage, temperature remains and primary to secondary steady leakage) AND loss of OR offsite power B. RCS inventory balance indicates >50 gpm total leakage AND

2. The 13.8 KV busses are de-energized See Also: Loss of Fission Product Barrier (1-C-i)

Electrical Failures (4-A-I thru 5)

Safety/Relief Valve Failure (1-A-i)

NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.

23 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

2. REACTOR COOLANT SYSTEM LEAK RATE A. ABNORMAL RCS LEAK RATE (Cont.)

Emergency Conditioni Indications) Clingqfiration

4. Loss of Coolant 1. High Pressure Injection Site Area Accident > High Pressure system running Emergency Injection system capacity AND RA-EP-01800

2. A. RCS pressure/pressurizer All Modes level continue to decrease OR B. RCS temperature/

pressure reach saturation conditions See Also: Loss of Fission Product Barrier (1-C-I)

Electrical Failures (4-A-1 thru 5)

Failure of a Primary Relief Valve (1-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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

3. SAFETY SYSTEM FUNCTIONS A. CRD. RPS Emergency 1nnAi;#nn

%-A.F11%41UU11 L11U1"L1U1A1 0 1

1. An uncontrolled control 1. Outward control rod Unusual Event rod withdrawal from a motion is indicated RA-EP-01600 subcritical reactor without a command for Modes 2, 3, 4, 5 such motion AND

2. The reactor is initially subcritical

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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

3. SAFETY SYSTEM FUNCTIONS B. SW. DH. CCW. MU. HPI, LPI/DH. MFW AFW Emergency PnnAitinn W.AUALJW..

1. Complete loss of any Loss of the Low Pressure Alert functions needed for Injection/Decay Heat System RA-EP-01700 plant cold shutdown (BOTH TRAINS) Modes 1, 2, 3 & 4

2. Inability to maintain 1. Loss of any cooling Alert plant in cold shutdown system function needed RA-EP-01700 to maintain cold shutdown Modes 5 & 6 (Decay Heat, Component Cooling Water, Service Water) (BOTH TRAINS).

AND

2. a. An operational mode change due to temperature increase.

OR

b. A 30 0 F rise in RCS temperature.

OR

c. Core cooling by feed and bleed has been initiated.

NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.

26 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

3. SAFETY SYSTEM FUNCTIONS B. SW. DH. CCW. MU. BPI. LPIIDH. MFW. AFW (Continued)

Emergency Cnondition Classificationi

3. Complete loss of any Loss of any of the following Site Area function needed for systems: Emergency plant hot shutdown 1. Service Water System RA-EP-01800 (BOTH TRAINS) Modes 1,2,3 & 4 OR

2. Component Cooling Water (BOTH TRAINS)

OR

3. A. Makeup System AND B. High Pressure Injection System (BOTH TRAINS)

OR

4. A. Main Feedwater System AND B. Auxiliary Feedwater System AND C. Motor Driven Feed Pump

4. Loss of water level in 1. Loss of any cooling Site Area the reactor vessel that system function needed Emergency has or will uncover fuel to maintain cold shutdown RA-EP-01800 in the reactor vessel (Decay Heat, Component Modes 5 & 6 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.).

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 03 TABLE OF EMERGENCY ACTION LEVEL CONDiTIONS

3. SAFETY SYSTEM FUNCTIONS C. LOSS OF CONTROL ROOM ALARMS. INDICATION. OR COMMUNICATIONS Emergency Ctngfltrn" Indicatinnfcl rlavaiflcatinn

1. Communication Complete loss of the Unusual Event capability lost to plant telephone system AND RA-EP-01600 an extent requiring Gai-tronics system All Modes plant shutdown or other significant loss of assessment

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 1 & 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

4. ELECTRICAL FAILURES A. AC Emergency tt--A:*.nn

%-V1JJJL1W11 Jului%1QUU12100

1. Loss of offsite power 1. Loss of power to Unusual Event or loss of onsite AC A and B busses from the RA-EP-01600 power capability following transformers: All Modes A. Startup 01 AND B. Startup 02 AND C. Aux II OR

2. A. Loss of power to C-1 AND D-1 busses from AC AND BD transformers.

AND B. Onsite power capability has been degraded to either 4160 VAC vital bus C-I or D-1 powered from a diesel generator.

OR

3. Loss of all diesel generators.

2. AC power capability to 1. Loss of power to Alert vital busses reduced to C-i 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-I 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDiTIONS

4. ELECTRICAL FAILURES A. AC (Continued)

Emergency Rnnl--A:nn 1k-,U1JU1L1U11 MAU.,aLIUIX% 0 1 Raa ....

3. Loss of offsite power 4160 VAC vital busses Alert and loss of all onsite C-I AND D-I de-energized RA-EP-01700 AC power longer than momentarily during All Modes transfers (see below for extended loss)

4. Loss of offsite power 4160 VAC vital busses Site Area and loss of onsite AC C-I AND D-I 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 II AND

2. 4160 VAC vital busses C-1 AND DI are de-energized for more than 15 minutes.

AND

3. A. Restoration of at least one vital bus within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDNTIONS

4. ELECTRICAL FAILURES B. DC Emergency Condition Indication(s) Classification

1. Loss of all onsite All in plant DC busses Alert DC power de-energized (see below RA-EP-01700 for extended loss) 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

5. SECONDARY SYSTEM EVENTS A. MAJOR STEAM LEAK Emergency Conditinn Tnaisitionnts Classificntinn

1. Rapid depressurization 1. A. Increasing containment Unusual Event of secondary side pressure (if leak is RA-EP-01600 inside containment) 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 1. Indication of a major Alert

>10 gpm primary to steam leak (see 5.A. 1) RA-EP-01700 secondary leak rate AND Modes 1, 2, 3 &4

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 NOTE Personal judgment plays an important role in ensuring that during '

any specific event the appropriate actions are performed.

32 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

5. SECONDARY SYSTEM EVENTS A. MAJOR STEAM LEAK (Cont.)

Emergency Cnnditinn Tndirctinns) Classi6fication

3. Steam line break with 1. Indication of a major Site Area

>50 gpm primary to steam leak (see 5.A.1) Emergency secondary leakage AND RA-EP-01800 AND 2. Main steam line radiation Modes 1,2,3&4 indication of fuel Monitor(s) indicate damage increased activity (RE 600/

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 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.

33 RA-EP-01500 Revision 03 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

6. RADIATION RELEASE EVENTS A. HIGH RADIATION LEVELS WrTHIN THE PROTECTED AREA Emergency Condition Indication(s) Classification

1. Radiation levels or airborne A. An area radiation Alert contamination which indicates survey indicates RA-EP-01700 a severe degradation in the radiation levels All Modes control of radioactive materials >1000 times normal (such as an increase of a factor OR of 1000 in direct radiation B. Airborne radioactivity readings) 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 NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.

35 RA-EP-01500 Revision 03 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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.

36 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

6. RADIATION RELEASE EVENTS C. ABNORMAL EFFLUENT RELEASE Emergency Cnnditinn Indficationns) ClassificatiAn

1. Effluent release > The following combination: Unusual Event limits allowed by 1. Any confirmed effluent RA-EP-01600 the Offsite Dose release exceeding the All Modes Calculation Manual limits of the ODCM.

(ODCM): OR ODCM Section 2.3.1 2. A high alarm is received ODCM Section 2.4.1 on any of the following ODCM Section 3.3.1 Radiation Monitoring ODCM Section 3.7.1 System monitors for ODCM Section 3.8.1 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 O 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 a any --

specific event the appropriate actions are performed.

37 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

6. RADIATION RELEASE EVENTS C. ABNORMAL EFFLUENT RELEASE (Cont.)

Emergency cn"A; tA ^

2. Effluent release >10 times The following combination: Alert limits allowed by the 1. Any confirmed effluent RA-EP-01700 Offsite Dose Calculation release exceeding the All Modes Manual (ODCM): ODCM Limits by >10 times ODCM Section 2.3.1 the limits ODCM Section 2.4.1 OR ODCM Section 3.3.1 2. A high alarm is received ODCM Section 3.7.1 on any of the following ODCM Section 3.8.1 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.

38 RA-EP-01500 Revision 03 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 pci/cc All Modes potential dose of about (Noble Gas) for 1 mrem at the site 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months boundary if continued OR over 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . 2. 0.5 mrem/hr measured at the Site Boundary for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 Aci/cc RA-EP-01800 Equivalent (TEDE) rate or greater for V2 hour All Modes 2 50 mrem/hr for l/2 hour. OR

2. 50 mnrem/hr by direct measurement at the site boundary for 1/2 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 03 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 2 500 mrem/hr for indicates 1.6E-1 pci/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 lci/cc RA-EP-01800 for 1/2 hour or greater for 'A hour All Modes OR

2. Radioiodine of 7.9E-8 pici/cc by direct measurement at the Site Boundary for 1/2 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 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

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.

OR

2. 1 ren/hfr 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.

OR

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.

41 RA-EP-01500 Revision 03 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 fure 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 03 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

7. HAZARDS TO STATION OPERATIONS C. TRAIN DERAILMENT Emergency d'-Anst.- ...

tiscci o

1. Train derailment onsite 1. Control room informed by Unusual Event station personnel who have RA-EP-01600 made a visual sighting All Modes AND

2. A. Station structures have been damaged OR B. Danger to station personnel exists NOTE Personal judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.

44 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

7. HAZARDS TO STATION OPERATIONS D. EXPLOSION Emergency Cnnd1ition TnMdication"(Q1 Classification

1. Near or onsite Control room informed by Unusual Event explosion station personnel who have RA-EP-01600 made a visual sighting 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

7. HAZARDS TO STATION OPERATIONS E. TOXIC OR FLAMMABLE GAS Emergency (nnli;*;n (larci-fc-ati n.

1. Near or onsite toxic or 1. Report or detection of toxic Unusual Event flammable gas release or flammable gases that RA-EP-01600 could enter within the Owner All Modes Controlled Area in amounts that can affect normal operation of the plant.

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 1. Report or detection of toxic Alert environs of uncontrolled or flammable gas within a RA-EP-01700 toxic or flammable gas Protected Area structure in All Modes concentrations that will be threatening to plant personnel.

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 03 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 03 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 I & 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 03 TABLE OF EMERGENCY ACTION LEVEL CONDMTIONS

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 03 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.

50 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

7. HAZARDS TO STATION OPERATIONS

1. SECURITY THREAT Emergency I Classification

1. Security threat or 1. Report by plant personnel Unusual Event attempted entry or of a security threat with RA-EP-01600 attempted sabotage a potential for industrial All Modes sabotage (i.e. attempted forcible entry into a vital area, armed entry into the protected area, discovery of suspected bombs or incendiary devices, etc.)

OR

2. Site Specific Credible Threat

2. Ongoing security 1. Report by a member Alert compromise of the security force RA-EP-01700 that a security emer- All Modes gency is in progress OR

2. Protected Area Intrusion OR

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 1. Physical attack on the General Emergency of the facility plant which has resulted RA-EP-01900 in occupation of the All Modes control room OR

2. Unauthorized personnel in control of vital plant equipment 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 03 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- 1500 Revision 03 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-02810, 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 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

8. NATURAL EVENTS (WITHN 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 RA-EP-01500 Revision 03 TABLE OF EMERGENCY ACTION LEVEL CONDITIONS

8. NATURAL EVENTS (WTHN 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 03 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.

- - - - - - - - - - - - - - - - - - I

56 RA-EP-01500 Revision 03 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 03 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 03 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 03 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 03 ATTACHMENT 1:

SUMMARY

OF EMERGENCY ACTION LEVELS

'I R UNUSUAL ALERT SITE AREA GENERAL P EVENT EMERGENCY EMERGENCY A-1 Failure of safety related relief B-1 High RCS activity B-2 Very high RCS activity -3 Core damage with B-4 Core damage with requiring shutdown inadequate core large release of cooling radioactivity possible 1-5 Core melt situation C-1 Loss of 2of 3 Fission product barriers D-1 Abnormal CMT D-2 High CTMT radiation, D-3 Very high CTMT radiation and pressure, and radiation and pressure temperature temperature 2 A-1 RCS leak rate A-2 RCS leak rate >50 A-3 RCS leak rate>50GPI requiring shutdown GPM but < HPI but <HPI capacity capacity and loss of site power

_____________ ____________ A-4 LOCA > HPI A-1 Startup accident A-2 Failure of Rx protect A-3 Failure of Rx protection system (ATWS) system to complete a manual trip B-1 Loss d LPI 6-3 Loss of SW, CCW, MU.

HPI orfeedwater B-2 Loss of Di CCW, 6-4 Loss of water level SW while shutdown while drained down C-1 Loss of communica- C-2 Loss of annunciator C-3 Loss of annunicator tions and station computer and computer during transient 4 A-1 Loss of offshe power A-2 Vital bus power A-4 Loss of offsite power A-5 Prolonged station or onsite AC reduced to a and site AC>15 min blackout single source B-2 Loss of onsite DC>1 5 A-3 Loss d offste power min and onsite AC B-1 Loss of all onskte D 5 A-1 Major Stm leak A-2 Major Sim leak with -3 Major Sin leak with

>10 GPM prmary to > 50 GPM primary to secondary leakage secondary leakage B-1 Failure of Stm safety andifued valve to close CAUTION:

THIS ATTACHMENT IS FOR INFORMATION ONLY -

UTILIZE THE ACTUAL EAL TEXT WHEN CLASSIFYING.

RA-EP-011500

R UNUSUAL ALERT SiTE AREA GENERAL R EVENT EMERGENCY EMERGENCY 6 A-1 Radiation level >1000 times normal B-1 Fuel handling accident -2 Fuel handling accident results in release results hISFAS actuation or ventilation C-1 Effluent release> C-2 Effluenbt10times I trip due to radiation Alowed Limits Allowed Limits D-i Projected dose 1 -2 -6 Very high dose rates mrem at site boundary 3 High dose rates at -7 at site boundary

. -~~~~~~~~~~~~~5 7 A-1 Fire lasting more than A-2 Fire afecting safety A-3 Fre resuiting hI loss 10 min. system of safety system B-1 Aircraft crash onsite B-2 Aircraft crash affecting -3 Aircraft crash or unusaul aircraft plant structures damaging vital system activity T-2 Onsite explosion -3 Explosion damaging C-1 Train derailment onsite affecting plant hot shutdown equip D-1 Onslte explosion oprations

-1 Toxic or flanmable gas E-2 Toxic or flammable -3 Toxdc or flammable release near or onsite gas release hiplant gas release In vital area F-1 Turbine failure causing F-2 Turbine falure with plant shutdown casing penetration -2 Missile iaot sut damaging hot shut-G-1 Missile rimpact on down equipment plant structure -2 Evacuation of CTRM H-1 Evacuation of control and local control not room established in 15 min

-2 Ongoing security -3 Loss of physical -4 Loss of physical control I-1 Security threat compromise control Imminent of the plant A-1 Any earthquake A-2 Earthquake>OBE -3 Earthquake > SSE B-1 Tornado onsite B-2 Tornado striking facalit C-1 Hurricane force winds C-2 Winds >74 mph < C-3 Winds > 90 mph forecast 90 mph D-1 50 year flood or low D-2 Flood or low water at -3 Flood or low water >

water design levels design levels Miscellaneo Miscellaneous Miscellaneous Miscellaneous CAUTION.:

THIS ATTACHMENT IS FOR INFORMATION ONLY-UTILIZE THE ACTUAL EAL TEXT WHEN CLASSIFYING.

RA-EP-01500

61 RA-EP-01500 Revision 03 COMMITMENTS Section Reference Comments Table of EALs, TERMS 0 05702 Reliable instrument readings throughout where applicable Table of EALs, TERMS 0 13375 Fire at alert level EAL 7-A-2 needing offsite assistance Table of EALs, TERMS 0 13377 Deleted 15 minute time EAL 3-C-3 duration for loss of all annunciators at Site Area Emergency Table of EALs, TERMS 0 13380 Unusual Event declared EAL 8-A-1 if earthquake is felt but not detected by monitors Table of EALs, TERMS 0 13383 Add turbine failure EAL 7-F-I Unusual Event Table of EALs, TERMS 0 13384 Alert EAL for loss of EAL 4-A-3 onsite and offsite power Caution 6.1.1.e. TERMS 0 13477 Reviewed/revised EAL TERMS 0 13482 applicability mode of plant operation Table of EALs, TERMS 0 13525 Clarify indications of EAL 2-A-2 > 50 gpr RCS leak Table of EALs, TERMS 0 13601 Make fire Unusual Event EAL 7-A-1 conform to NUREG 0654 Section 6.1.1 .e.3. TERMS 0 13670 Specifies conditions under which the Shift Manager (STA) may assume Emergency Director duties Table of EALs, TERMS 0 13672 OBE and SSE Earthquakes EAL 8-A-2 and 8-A-3 Table of EALs, TERMS 0 14181 Highlighting of AND and throughout OR Table of EALs, TERMS 0 14855 Clarify fuel failure EAL 1-B-I thru 1-B-5

62 RA-EP-01500 Revision 03 COMMITMENTS (Continued)

Section Reference Comments Table of EALs, TERMS 0 14974 Ensure ATWS conditions EAL 3-A-3 are correctly classified.

Table of EALs TERMS 0 14986 Cross reference to other throughout EALs Table of EALs, TERMS 0 14988 High containment radiation, EAL i-D-2 pressure and temperature indicated by any SFAS function activated Table of EALs, TERMS 0 15157 Clarify loss of fission EAL 1-C-I product barriers Section 3.2 TERMS 018734 Definition of a core melt Sequence Table of EALs, TERMS Q 00052 EAL for loss of EAL 1-C-i containment integrity Entire Procedure TERMS Q 03113 Procedure for Emergency Classification

ML031990226

Text

2.0 REFERENCES

2.0 REFERENCES

SUMMARY

Navigation menu

Search